E. S. (Hank) Drumhiller
Vice President Operations and
Chief Nuclear Officer
Site Licence Holder – Chalk River
Laboratories
CRL-ACNO-10-0048-L
UNRESTRICTED
2010 September 30
M. Leblanc
Commission Secretary
Secretariat
Canadian Nuclear Safety Commission
280 Slater Street
P.O. Box 1046, Station B
OTTAWA, Ontario K1P 5S9
Dear Mr. Leblanc:
CHALK RIVER LABORATORIES (CRL)
APPLICATION FOR OPERATING LICENCE RENEWAL - 2011 On behalf of Atomic Energy of Canada Limited, I hereby make application for the renewal of the
Nuclear Research and Test Establishment Operating Licence for Chalk River Laboratories (current
licence – NRTEOL 1.07/2011) [1]. This application is made in accordance with the requirements of
the Nuclear Safety and Control Act, and the General Nuclear Safety and Control Regulations. Two
signed copies of the form Application for Licensing [2] are enclosed for the consideration of the
Commission.
This application is submitted for consideration by Commission members for a five year licence
renewal period to commence on 2011 November 01 following expiry of the current licence [1]. This
licence period is consistent with other Class I nuclear facility licences, and is supported by an
Integrated Safety Review that establishes the basis for operating the National Research Universal
(NRU) reactor safely for a 10-year period.
Attachment A summarizes the material required by sections 5 and 7 of the General Nuclear Safety and
Control Regulations, and Attachment B presents the information required by the Act and the
Regulations made pursuant to the Act, to be included in an application for the renewal of a licence.
Specifically, Attachment B provides a clause-by-clause statement for relevant excerpts from the
relevant CNSC Regulations. Additional documentation is enclosed with this letter [3 to 7] which
supports the material and information presented in Attachment B.
Chalk River Laboratories
Chalk River, Ontario
Canada K0J 1J0
(613) 584-8811 + 48021.
Tel.: (613) 584-3311
Laboratoires de Chalk River
Chalk River (Ontario)
Canada K0J 1J0
(613) 584-8811 + poste
Tél. : (613) 584-3311
M. Leblanc
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The timing of this application is consistent with the requested approach as presented in [8], and further
supporting reference material will be submitted to the Secretariat by 2010 November 30, also as
requested in [8].
ABCL looks forward to hearing from the Commission with respect to this application. In the interim,
should you require any further information please contact Mr. Dave Cox, Director - Safety
Engineering and Licensing at 613-584-8811, extension 45159 or myself.
Yours sincerely,
E. S. (Hank) Drumhiller
Vice-President Operations
Chief Nuclear Officer
Site Licence Holder - Chalk River Laboratories
E(H)D/JEC/jc
Attachments
Enclosures
M. Leblanc 3
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References:
[1]
[2]
Chalk River Laboratories, Nuclear Research and Test Establishment Operating Licence,
NRTEOL-01-07/2011. Expiry Date: 2011 October 31.
C
NSC Form, Application for Licensing, (Rev. 2000 July).
[3] Research and Technology Operations Management System Manual, 145-514100-MAN-001,
Revision 0, 2010 September.
[4] Management System Governing Documentation Index, 145-514100-GDI-001, Revision 0,
2010 September.
[5] Sites and Facilities Governing Documentation Index, 145-514100-GDI-002, Revision 0,
2010 September.
[6] Management System Contact and Responsibility List, 145-514100-016-000, Revision 0,
2010 September.
[7] Organization to Support CRL Operations, CRL-514100-ORG-001, Revision 0,
2010 September.
[8] M. Santini, Letter to W.S. Pilkington, Application for the Renewal of the Chalk River
Laboratories Operating Licence, CRL-NOAC-10-0008-L (E-docs: 3542765), 2010 May 10.
c
C. Nache (CNSC)
A. Ashworth
J.E. Chilton
W.C.H. Kupferschmidt
J. McKenna
>CNSC Site Office
N. Riendeau (CNSC)
T. Arthur
D.S. Cox
V. Langman
J. Miller
>CR Licensing
M. Santini (CNSC)
J. Bond
C. de Vries
R.G. Lavoie
J.R. Walker
>SRC
S.J. Bushby
J.D. Garrick
R.M. Lesco
A.J. White
M. Leblanc
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2010 September 30
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Attachment A
Information Required for Licence Renewal Application as per Sections 5 and 7
of the General Nuclear Safety and Control Regulations
Requirements are shown in bold and italic font with AECL responses in regular font.
Application for Renewal of Licence
Section 5
An application for the renewal of a licence shall contain:
(a) The information required to be contained in an application for that licence by the applicable
regulations made under the Act:
AECL is applying for a renewal of the current Chalk River Laboratories Nuclear Research and Test
Establishment Operating Licence (NRTEOL-1.07/2011) [A-1].
Attachment B of this letter presents the information required by the Act and the Regulations made
pursuant to the Act, to be included in an application for the renewal of a licence. Specifically,
Attachment B provides a clause-by-clause statement for relevant excerpted clauses from the CNSC
Regulations. Reference to specific AECL and external documentation is made within Attachment B, as
required, and these are separately listed as references at the end of Attachment B.
Certain key items of AECL supporting documentation that are referenced within Attachment B have
been newly prepared for this application, and are itemized below as references [A-2 to A-6].
Two signed copies of the CNSC form Application for Licensing [A-7] are also enclosed for the
consideration of the Commission.
Supplementary information, in support of this application, will be provided to the CNSC Secretariat by
2010 November 30.
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Incorporation of Material in Application
Section 7
An application for a licence or for the renewal, suspension in whole or in part, amendment,
revocation or replacement of a licence may incorporate by reference any information that is
included in a valid, expired or revoked licence.
Attachment B of this letter replaces the previous stand-alone document [A-8] that was submitted in
2005 November for the previous application to renew the CRL operating licence.
In a similar manner, reference items [A-2 to A-6] enclosed with this application have been newly
prepared by AECL to replace the document [A-9] that was originally submitted in 2005 November for
the previous application to renew the CRL operating licence. AECL believes that the suite of newly
submitted documents comprising reference items [A-2 to A-6], and their subsequent revision on an as
required basis, will provide an improved platform of internal licensing reference material.
References:
[A-1]
halk River Laboratories, Nuclear Research and Test Establishment Operating Licence,
C
NRTEOL-01-07/2011. Expiry Date: 2011 October 31.
[A-2] Research and Technology Operations Management System Manual, 145-514100-MAN-001,
Revision 0, 2010 September.
[A-3] Management System Governing Documentation Index, 145-514100-GDI-001, Revision 0,
2010 September.
[A-4] Sites and Facilities Governing Documentation Index, 145-514100-GDI-002, Revision 0,
2010 September.
[A-5] Management System Contact and Responsibility List, 145-514100-016-000, Revision 0,
2010 September.
[A-6]
Organization to Support CRL Operations, CRL-514100-ORG-001, Revision 0,
2010 September.
CNSC Form, Application for Licensing, (Rev. 2000 July).
Licensing Basis Document for Chalk River Laboratories, CRL-00521-LBD-001, Revision 0,
2005 November.
Information in Support of Site Licence Renewal for Chalk River Laboratories,
CRL-00521-LP-001, Revision 1, 2007 March (Revision 0, 2005 December).
[A-7]
[A-8]
[A-9]
M. Leblanc
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Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Safety Control Act
24(2)
The Commission may issue, renew, suspend in whole or in
part, amend, revoke, or replace a licence on receipt of an
application
(a) in the prescribed form;
This attachment provides the information required by the
Nuclear Safety and Control Act (the Act) and the Regulations
made pursuant to the Act, and constitutes, in part, an
application by AECL to renew the current CRL site operating
licence. See the enclosed subject cover letter [B-1] and
application form [B-2]. Other supporting material will be
provided, as required, under separate cover.
24(2)
(b) containing the prescribed information and
undertakings and accompanied by the prescribed
documents; and
See response to item (a) above.
24(2)
(c) accompanied by the prescribed fee.
AECL is in good standing with respect to the provision of
CNSC licensing fees and will provide all necessary fees, as
and when required, under separate cover.
24(4)
No licence may be issued, renewed, amended or replaced
unless, in the opinion of the Commission, the applicant
(a) is qualified to carry on the activity that the licence will
authorize the licensee to carry on; and
AECL understands that qualification will be determined
through consideration by the Commission of this application
and the associated supporting material as well as deliberation
through the Commission public hearing process.
M. Leblanc
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Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Safety Control Act
24(4)
(b) will, in carrying on that activity, make adequate
provision for the protection of the environment, the
health and safety of persons and the maintenance of
national security and measures required to implement
international obligations to which Canada has agreed.
AECL understands that adequate provision will be determined
through consideration by the Commission of this application
and the associated supporting material as well as deliberation
through the Commission public hearing process.
24(5)
A licence may contain any term or condition that the
Commission considers necessary for the purposes of this
Act, including a condition that the applicant provide a
financial guarantee in a form that is acceptable to the
Commission.
AECL understands the requirement for an acceptable financial
guarantee. AECL is a Schedule III, Part I Crown corporation
under the Financial Administration Act. The existence of an
appropriate financial guarantee for the Chalk River
Laboratories site was previously established [B-3] and [B-4].
25
The Commission may, on its own motion, renew, suspend
in whole or in part, amend, revoke or replace a licence
under the prescribed conditions.
AECL understands the clause and no response is required.
M. Leblanc
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Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
3
(1) An application for a licence shall contain the following
information:
(a) the applicant’s name and business address;
See application form [B-2].
3
(b)
the activity to be licensed and its purpose;
AECL’s major research and development efforts take place at
the Chalk River Laboratories (CRL).
In particular at the CRL site, AECL intends to:
a) possess, transfer, import, export, sell and use nuclear
substances, prescribed equipment and prescribed
information;
b) produce, refine, convert, process, package, transport,
manage, sell, store and dispose of nuclear substances;
c) produce, sell and service prescribed equipment;
d) prepare a site to construct, operate, sell, modify and
decommission a nuclear facility.
3
(c)
the name, maximum quantity and form of any
nuclear substance to be encompassed by the
licence
Three principal types of nuclear substances exist at CRL:
• Heavy Water (Deuterium Compounds and Derivatives)
• Fissile, Fertile and other Radioactive Nuclides
• Sealed and unsealed sources
Nuclear substances are in use at CRL in solid, liquid and
gaseous forms. Limitations on the maximum quantities of
nuclear substances permitted on the CRL site are specified in
the various facility Safety Analysis Reports for nuclear
facilities; in the various Radioisotope Laboratory protocols for
the radioisotope laboratories; in the various Criticality Safety
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
Documents and Approvals; and, in specific procedures
governing the use, handling and storage of nuclear substances.
Reference to these documents may be found through the Sites
and Facilities Governing Documentation Index document
[B-5], section 4.1, and the documents referenced therein.
3
(d)
a description of any nuclear facility, prescribed
equipment or prescribed information to be
encompassed by the licence
The CRL site contains various Class I and Class II nuclear
facilities. A description and information regarding the nuclear
facilities may be found in the RTO Management System
manual [B-6], section 6.2 and more detailed information is
provided in the nuclear facility specific documentation listed
in the Sites and Facilities Governing Documentation Index
document [B-5], sections 4.1.1 and 4.1.2, and associated
references.
Relevant information on prescribed equipment may be found
in the RTO Management System manual [B-6], sections 6.2
and 6.3 and more detailed information in specific
documentation listed in the Sites and Facilities Governing
Documentation Index document [B-5], sections 4.1.2 to 4.1.4
inclusive.
Any specific required information that may be prescribed
information will be provided to the Commission under
separate cover, consistent with clause 21 (2) of the General
Nuclear Safety and Control Regulations which states that
information made public is not prescribed information for the
purposes of the Nuclear Safety and Control Act (the Act).
M. Leblanc
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Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
3
(e)
the proposed measures to ensure compliance
with the Radiation Protection Regulations and
the Nuclear Security Regulations
Compliance with the Radiation Protection Regulations at CRL
is ensured through implementation of the Radiation Protection
(RP) program. This program is addressed by Process 508740,
Provide Radiation Protection, as described in the RTO
Management System manual [B-6], section B.8.12.
Compliance with the Nuclear Security Regulations is ensured
through implementation of the Physical Security program.
This program is addressed by Process 508710, Provide
Physical Security, as described in the RTO Management
System manual [B-6], section B.8.9.
3
(f)
any proposed action level for the purpose of
section 6 of the Radiation Protection
Regulations;
Action levels for the CRL site are defined in the document
Action Levels for Chalk River Laboratories [B-7].
3
(g)
the proposed measures to control access to the
site of the activity to be licensed and the nuclear
substance, prescribed equipment or prescribed
information;
Relevant requirements regarding access to the CRL site are
addressed by Process 508710, Provide Physical Security, as
described in the RTO Management System manual [B-6],
section B.8.9.
3
(h)
the proposed measures to prevent loss or illegal
use, possession or removal of the nuclear
substance, prescribed equipment or prescribed
information;
Relevant requirements regarding loss, illegal use, possession
or removal at the CRL site are addressed by Process 508710,
Provide Physical Security, as described in the RTO
Management System manual [B-6], section B.8.9.
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
3
(i)
a description and the results of any test, analysis
or calculation performed to substantiate the
information included in the application;
Substantiation of the information included with this
application is demonstrated through the implementation of
annual reporting requirements as defined in the current site
operating licence. Annual reports are prepared, as required, to
cover both nuclear facility and program performance areas.
Further specific information on tests, analysis and relevant
calculations may be found in the various nuclear facility
specific Safety Analysis Reports prepared through the
implementation of Process 508770, Provide Safety Analysis
and Operational Safety Assessment, as described in the RTO
Management System manual [B-6], section B.8.15.
3
(j)
the name, quantity, form, origin and volume of
any radioactive waste or hazardous waste that
may result from the activity to be licensed,
including waste that may be stored, managed,
processed, or disposed of at the site of the
activity to be licensed, and the proposed method
for managing and disposing of that waste;
Specific information on radioactive and hazardous wastes may
be found in the annual reports prepared as a requirement of the
current site operating licence for CRL.
Relevant requirements for managing and disposing radioactive
and hazardous waste at the CRL site are addressed by Process
508600, Manage Wastes, as described in the RTO
Management System manual [B-6], section B.8.8.
3
(k)
the applicant’s organizational management
structure insofar as it may bear on the applicant’s
compliance with the Act and the Regulations
made under the Act, including the internal
allocation of functions, responsibilities and
authority;
AECL’s organizational structure for the operation of the Chalk
River Laboratories is documented in the AECL Management
Manual [B-8], and in the document Organization to Support
CRL Operations [B-9].
M. Leblanc
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
3
(l)
3
(m) any other information required by the Act or the
Regulations made under the Act for the activity
to be licensed and the nuclear substance, nuclear
facility, prescribed equipment or prescribed
information to be encompassed by the licence.
3
3
a description of any proposed financial guarantee AECL understands the requirement for an acceptable financial
relating to the activity to be licensed; and
guarantee. AECL is a Schedule III, Part I Crown corporation
under the Financial Administration Act. The existence of an
appropriate financial guarantee for the Chalk River
Laboratories site was previously established [B-3] and [B-4].
Any further required information will be supplied upon
request.
(1.1) The Commission or a designated officer authorized
under paragraph 37(2)(c) of the Act, may require any
other information that is necessary to enable the
Commission or the designated officer to determine
whether the applicant
(a) is qualified to carry on the activity to be licensed; Any further required information will be supplied upon
or
request.
(b) will, in carrying on that activity, make adequate
provision for the protection of the environment,
the health and safety of persons and the
maintenance of national security and measures
required to implement international obligations
to which Canada has agreed.
Any further required information will be supplied upon
request.
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
3
(2)
Subsection (1) does not apply in respect of an
Subsection (1) above is applicable with respect to the current
application for a licence to import or export for which licensing application, and information has been provided
the information requirements are prescribed by the
accordingly.
Nuclear Non-Proliferation Import and Export Control
Regulations, or in respect of an application for a
licence to transport while in transit for which the
information requirements are prescribed by the
Packaging and Transport of Nuclear Substances
Regulations.
4
An application for a licence to abandon a nuclear
substance, a nuclear facility, prescribed equipment or
prescribed information shall contain the following
information in addition to the information required by
section 3 of the General Nuclear Safety and Control
Regulations:
The current licensing application does not relate to the
abandonment of any nuclear substances, nuclear facilities,
prescribed equipment or prescribed information.
4
(a) the name and location of the land, buildings,
structures, components, and equipment that are to be
abandoned;
This clause is not relevant to the current licensing application.
4
(b) the proposed time and location of the abandonment;
This clause is not relevant to the current licensing application.
4
(c) the proposed method of and procedure for
abandonment; and
This clause is not relevant to the current licensing application.
4
(d) the effects on the environment and the health and
safety of persons that may result from the
abandonment, and the measures that will be taken to
prevent or mitigate those effects.
This clause is not relevant to the current licensing application.
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
5
5
An application for the renewal of a licence shall contain
(a) the information required to be contained in an
application for that licence by the applicable
Regulations made under the Act; and
(b) a statement identifying the changes in the information
that was previously submitted.
This attachment constitutes, in part, an application by AECL
to renew the CRL site operating licence. See the enclosed
subject cover letter [B-1] and application form [B-2]. Other
supporting material will be provided, as required, under
separate cover.
Due to the complex and diverse nature of the nuclear
operations and associated compliance programs at CRL, a
simple statement cannot be made regarding changed
information since the previous application for the site
operating licence renewal in 2005.
Furthermore, AECL is fully aware from ongoing interactions
with staff from the CNSC’s Chalk River Laboratories
Compliance and Licensing Division that the proposed
regulatory framework under consideration for the duration of
the renewed licence is substantially different from that
currently in place. Specifically, the format of the proposed
licence and conditions will change substantially, and a new
Licence Conditions Handbook will be issued to provide
guidance on interpretation of the licence conditions.
M. Leblanc
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
6
An application for the amendment, revocation or
replacement of a licence shall contain the following
information:
(a) a description of the amendment, revocation or
This clause is not relevant to the current application for a
replacement and of the measures that will be taken and licence renewal.
the methods and procedures that will be used to
implement it;
6
(b) a statement identifying the changes in the information
contained in the most recent application for the
licence;
This clause is not relevant to the current application for a
licence renewal.
6
(c) a description of the nuclear substances, land, areas,
buildings, structures, components, equipment and
systems that will be affected by the amendment,
revocation or replacement and of the manner in which
they will be affected; and
This clause is not relevant to the current application for a
licence renewal.
6
(d) the proposed starting date and the expected completion This clause is not relevant to the current application for a
date of any modification encompassed by the
licence renewal.
application.
7
An application for a licence or for the renewal, suspension
in whole or in part, amendment, revocation or replacement
of a licence may incorporate by reference any information
that is included in a valid, expired or revoked licence.
The clause is understood, and no response is required.
M. Leblanc
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
8
(1) For the purpose of section 25 of the Nuclear Safety
and Control Act, the Commission may renew a licence
on its own motion if failure to renew the licence could
pose an unreasonable risk to the environment, the
health and safety of persons or national security.
8
(2)
For the purpose of section 25 of the Nuclear Safety
and Control Act, the Commission may, on its own
motion, suspend in whole or in part, amend, revoke
or replace a licence under any of the following
conditions:
(a) the licensee is not qualified to carry on the
licensed activity;
The clause is understood, and no response is required.
The clause is understood, and no response is required.
8
(b)
the licensed activity poses an unreasonable risk
to the environment, the health and safety of
persons or the maintenance of national security;
The clause is understood, and no response is required.
8
(c)
the licensee has failed to comply with the Act,
the Regulations made under the Act or the
licence;
The clause is understood, and no response is required.
8
(d)
the licensee has been convicted of an offence
under the Act;
The clause is understood, and no response is required.
8
(e)
a record referred to in the licence has been
modified in a manner not permitted by the
licence;
The clause is understood, and no response is required.
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
8
(f)
the licensee no longer carries on the licensed
activity;
The clause is understood, and no response is required.
8
(g)
the licensee has not paid the licence fee
prescribed by the Cost Recovery Fees
Regulations; or
The clause is understood, and no response is required.
8
(h)
failure to do so could pose an unreasonable risk
to the environment, the health and safety of
persons or national security.
The clause is understood, and no response is required.
15
15
Every applicant for a licence and every licensee shall
notify the Commission of
(a) the persons who have authority to act for them in their
dealings with the Commission;
(b) the names and position titles of the persons who are
responsible for the management and control of the
licensed activity and the nuclear substance, nuclear
facility, prescribed equipment or prescribed
information encompassed by the licence; and
AECL’s organizational structure for the operation of the Chalk
River Laboratories is documented in the AECL Management
Manual [B-8]; in the document Organization to Support CRL
Operations [B-9]; and, in the document Management System
Contact and Responsibility List [B-10].
Further relevant information regarding organizational
management at the CRL site is provided in the RTO
Management System manual [B-6], section 7.
Relevant information on the position titles are defined in the
RTO Management System manual [B-6], section 7; in the
document Organization to Support CRL Operations [B-9];
and, in the document Management System Contact and
Responsibility List [B-10].
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Section
Requirement
AECL Response
General Nuclear Safety and Control Regulation
15
(c) any change in the information referred to in
paragraphs (a) and (b), within 15 days after the change
occurs.
See response to 15 (b) above.
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Section
Requirement
AECL Response
Radiation Protection Regulation
18
An application for a licence to operate a dosimetry service
shall contain the following information in addition to the
information required by section 3 of the General Nuclear
Safety and Control Regulations:
(a) a description of the proposed operation of the
dosimetry service;
This clause is not relevant to the current application for a
licence to operate the CRL.
18
(b) the proposed quality assurance program;
This clause is not relevant to the current application for a
licence to operate the CRL.
18
(c) the types of dosimetry services proposed to be
provided, including the types of radiation that will be
monitored and their respective energy ranges;
This clause is not relevant to the current application for a
licence to operate the CRL.
18
(d) the precision, accuracy and reliability of the dosimetry
services to be provided; and
This clause is not relevant to the current application for a
licence to operate the CRL.
18
(e) the proposed qualification requirements and training
program for workers.
This clause is not relevant to the current application for a
licence to operate the CRL.
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Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Class I Nuclear Facilities Regulation
3
An application for a licence in respect of a Class I nuclear
facility, other than a licence to abandon, shall contain the
following information in addition to the information
required by section 3 of the General Nuclear Safety and
Control Regulations:
Class I nuclear facilities located at CRL are as follows:
• National Research Universal (NRU) Reactor
• Nuclear Fuel Fabrication Facility (Building 429A & B)
• Nuclear Fuel Fabrication Facility (Building 405)
• Recycle Fuel Fabrication Laboratories
• Heavy-Water Upgrading Plant
• ZED-2 Reactor (Zero Energy Deuterium)
• Building 234 Universal Cells
• Molybdenum-99 Production Facility
• Tritium Laboratory
• Waste Treatment Centre and Associated Facilities
• Fuels and Materials Cells
• Waste Management Areas
• Combined Electrolysis and Catalytic Exchange Upgrading
and Detritiation (CECEUD) Test Facility
Relevant information is provided in the various clauses below.
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(a) a description of the site of the activity to be licensed,
including the location of any exclusion zone and any
structures within that zone;
Relevant information regarding site description may be found
in the document CRL Site Characteristics [B-11].
Additional relevant material for the Class I nuclear facilities is
provided in the facility Safety Analysis Reports. Reference to
these documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5],
section 4.1.1, and the documents referenced therein.
3
(b) plans showing the location, perimeter, areas,
structures, and systems of the nuclear facility;
Relevant requirements regarding plans for, and systems of, the
nuclear facilities on the CRL site are provided in the facility
Safety Analysis Reports. Reference to these documents may
be found through the Sites and Facilities Governing
Documentation Index document [B-5], section 4.1.1, and the
documents referenced therein.
3
(c) evidence that the applicant is the owner of the site or
has authority from the owner of the site to carry on the
activity to be licensed;
Evidence of ownership may be found in the property report
provided with the letter from J.C. Amrouni to B.D. Howden,
CRL Deed, JCA-00-033, 2000 May 02 [B-12].
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3
(d) the proposed quality assurance program for the
activity to be licensed;
Consistent with the global trend towards integration of
management systems, AECL is moving from separate
programs such as Quality Assurance to an Integrated
Management System. Hence this requirement is being
addressed by the RTO Management System manual [B-6],
which is compliant with the Canadian Standards Association
N286-05 entitled The Management System Requirements for
Nuclear Power Plants [B-13]. Where required to satisfy
external legislative and customer requirements, lower tiered
Quality Assurance Programs and supporting Manuals continue
to be maintained.
3
(e) the name, form, characteristics and quantity of any
hazardous substances that may be on the site while the
activity to be licensed is carried on;
Comprehensive information on name, form, characteristics and
quantity of hazardous substances is made available to AECL
staff through the Occupational Safety & Health Program’s
website. Material Safety Data Sheets for all hazardous
substances may be accessed in this way. Specific examples
may be provided upon request from this large amount of
information.
The Workplace Hazardous Materials Information System
(WHMIS) is a Canada-wide system implemented by all levels
of government on 1988 October 31. It is designed to ensure
that suppliers provide, and employers receive, relevant
information in the form of a LABEL and MATERIAL
SAFETY DATA SHEET (MSDS). Such information is
needed by employers to inform and train their employees
about hazardous materials used in the workplace.
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As far as CRL is concerned, the WHMIS triad requirements –
LABEL, MSDS, and EMPLOYEE EDUCATION PROGRAM
– are applicable to hazardous substances as defined in the
Canada Labour Code, Part 2, which includes all controlled
products as defined in the Hazardous Products Act. In other
words, the Canada Labour Code covers a very wide range of
hazardous materials, which may be chemical, biological, or
physical in nature.
3
(f) the proposed worker health and safety policies and
procedures;
The policy in place is entitled Employee Safety and Health
[B-14].
Relevant requirements regarding worker health and safety are
addressed by Process 510400, Ensure Employee Safety and
Well-being, as described in the RTO Management System
manual [B-6], section B.10.3, and more specific information is
provided in the Management System Governing
Documentation Index document [B-15], and associated
references for Process 510400.
3
(g) the proposed environmental protection policies and
procedures;
The policy in place is entitled Environment [B-16].
Relevant requirements regarding environmental protection are
addressed by Process 509200, Provide Environmental
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1, and more specific
information is provided in the Management System Governing
Documentation Index document [B-15] and associated
references for Process 509200.
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3
(h) the proposed effluent and environmental monitoring
programs;
Relevant requirements regarding environmental protection are
addressed by Process 509200, Provide Environmental
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1, and more specific
information is provided in the Management System Governing
Documentation Index document [B-15], and associated
references for Process 509200.
3
(i) if the application is in respect of a nuclear facility
referred to in paragraph 2(b) of the Nuclear Security
Regulations, the information required by section 3 of
those Regulations;
This clause is not relevant to the current application for a
licence to operate CRL since there is no nuclear power plant
encompassed by the application.
3
(j) the proposed program to inform persons living in the
vicinity of the site of the general nature and
characteristics of the anticipated effects on the
environment and the health and safety of persons that
may result from the activity to be licensed; and
Relevant requirements regarding informing persons living in
the vicinity of the site are addressed by Process 513300,
Manage Community Relationships, and Process 513400,
Manage External Communications, as described in the RTO
Management System manual [B-6], section B.13.1 and B.13.2,
respectively.
3
(k) the proposed plan for the decommissioning of the
nuclear facility or of the site.
The most recent decommissioning plan is reference [B-17]. A
revised Comprehensive Preliminary Decommissioning Plan is
currently in final preparation and will shortly be provided to
CNSC staff.
4
An application for a licence to prepare a site for a Class I
nuclear facility shall contain the following information in
addition to the information required by section 3 of the
Class I Nuclear Facilities Regulations:
Any consideration of site preparation for a Class I nuclear
facility at CRL will be provided under separate cover and is
not relevant to this application.
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AECL Response
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4
(a) a description of the site evaluation process and of the
investigations and preparatory work that have been
and will be done on the site and in the surrounding
area;
See response under introduction to clause 4.
4
(b) a description of the site’s susceptibility to human
activity and natural phenomena, including seismic
events, tornadoes and floods;
See response under introduction to clause 4.
4
(c) the proposed program to determine the environmental
baseline characteristics of the site and the surrounding
area;
See response under introduction to clause 4.
4
(d) the proposed quality assurance program for the design
of the nuclear facility; and
See response under introduction to clause 4.
4
(e) the effects on the environment and the health and
safety of persons that may result from the activity to
be licensed, and the measures that will be taken to
prevent or mitigate those effects.
See response under introduction to clause 4.
5
An application for a licence to construct a Class I nuclear
facility shall contain the following information in addition
to the information required by section 3 of the Class I
Nuclear Facilities Regulations:
Any consideration of the construction of a Class I nuclear
facility at CRL will be provided under separate cover and is
not relevant to this application.
5
(a) a description of the proposed design of the nuclear
facility, including the manner in which the physical
and environmental characteristics of the site are taken
into account in the design;
See response under introduction to clause 5.
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5
(b) a description of the environmental baseline
characteristics of the site and the surrounding area;
See response under introduction to clause 5.
5
(c) the proposed construction program, including its
schedule;
See response under introduction to clause 5.
5
(d) a description of the structures proposed to be built as
part of the nuclear facility, including their design and
their design characteristics;
See response under introduction to clause 5.
5
(e) a description of the systems and equipment proposed
to be installed at the nuclear facility, including their
design and their design operating conditions;
See response under introduction to clause 5.
5
(f) a preliminary safety analysis report demonstrating the
adequacy of the design of the nuclear facility;
See response under introduction to clause 5.
5
(g) the proposed quality assurance program for the design
of the nuclear facility;
See response under introduction to clause 5.
5
(h) the proposed measures to facilitate Canada’s
compliance with any applicable safeguards agreement;
See response under introduction to clause 5.
5
(i) the effects on the environment and the health and
safety of persons that may result from the
construction, operation and decommissioning of the
nuclear facility, and the measures that will be taken to
prevent or mitigate those effects;
See response under introduction to clause 5.
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Class I Nuclear Facilities Regulation
5
(j) the proposed location of points of release, the
proposed maximum quantities and concentrations, and
the anticipated volume and flow rate of releases of
nuclear substances and hazardous substances into the
environment, including their physical, chemical and
radiological characteristics;
See response under introduction to clause 5.
5
(k) the proposed measures to control releases of nuclear
substances and hazardous substances into the
environment;
See response under introduction to clause 5.
5
(l) the proposed program and schedule for recruiting,
training and qualifying workers in respect of the
operation and maintenance of the nuclear facility; and
See response under introduction to clause 5.
5
(m) a description of any proposed full-scope training
simulator for the nuclear facility.
See response under introduction to clause 5.
6
An application for a licence to operate a Class I nuclear
facility shall contain the following information in addition
to the information required by section 3 of the Class I
Nuclear Facilities Regulations:
(a) a description of the structures at the nuclear facility,
including their design and their design operating
conditions;
Relevant information on the nuclear facilities structures, their
design and design operating conditions may be found in the
individual facility Safety Analysis Reports.
Reference to these documents may be found through the Sites
and Facilities Governing Documentation Index document
[B-5], section 4.1.1, and the documents referenced therein.
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Class I Nuclear Facilities Regulation
6
(b) a description of the systems and equipment at the
nuclear facility, including their design and their design
operating conditions;
Relevant information on the nuclear facilities systems and
equipment including their design and design operating
conditions may be found in the individual facility Safety
Analysis Reports. Reference to these documents may be found
through the Sites and Facilities Governing Documentation
Index document [B-5], section 4.1.1, and the documents
referenced therein.
6
(c) a final safety analysis report demonstrating the
adequacy of the design of the nuclear facility;
Reference to the final Safety Analysis Reports may be found
through the Sites and Facilities Governing Documentation
Index document [B-5], section 4.1.1, and the documents
referenced therein.
6
(d) the proposed measures, policies, methods, and
procedures for operating and maintaining the nuclear
facility;
Relevant requirements regarding the operation and
maintenance of the nuclear facilities on the CRL site are
addressed by Process 508220, Operate Facilities and Process
508230, Provide Maintenance, as described in the RTO
Management System manual [B-6], sections B.8.2 and B.8.3
respectively.
Reference to the various documents is provided through the
Sites and Facilities Governing Documentation Index document
[B-5], section 4.1.1 and the documents referenced therein.
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6
(e) the proposed procedures for handling, storing, loading, Relevant requirements regarding the handling, storing,
and transporting nuclear substances and hazardous
loading, and transporting of nuclear substances and hazardous
substances;
substances are addressed by Process 508510, Manage Nuclear
Material and Safeguards and Process 508520, Manage
Transportation of Radioactive Materials, as described in the
RTO Management System manual [B-6], sections B.8.5 and
B.8.6 respectively.
6
(f) the proposed measures to facilitate Canada’s
compliance with any applicable safeguards agreement;
Relevant requirements regarding safeguards are addressed by
Process 508510, Manage Nuclear Material and Safeguards as
described in the RTO Management System manual [B-6],
section B.8.5.
6
(g) the proposed commissioning program for the systems
and equipment that will be used at the nuclear facility;
Commissioning of Class I nuclear facilities sub-systems or
systems are administered on a case-by-case basis, in
accordance with Process 505250, Manage Commissioning and
Testing as described in the RTO Management System manual
[B-6], section B.5.3. Any relevant information will be
provided under separate cover.
6
(h) the effects on the environment and the health and
safety of persons that may result from the operation
and decommissioning of the nuclear facility, and the
measures that will be taken to prevent or mitigate
those effects;
The safe operation of the CRL Class I nuclear facilities at CRL
is documented in annual safety reports which separately cover
the nuclear facilities [B-18] and environmental performance in
general [B-19]. Preparation of these reports is a requirement
of the current site operating licence. These reports were most
recently issued in 2010 April and 2010 June respectively.
Relevant requirements regarding environmental protection are
addressed by Process 509200, Environmental Protection
Program as described in the RTO Management System manual
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[B-6], section B.9.1.
Relevant requirements regarding worker health and safety are
addressed by Process 510400, Ensure Employee Safety and
Well-being, as described in the RTO Management System
manual [B-6], section B.10.3.
Relevant requirements regarding decommissioning are
addressed by Process 508300, Decommission Sites and
Facilities, as described in the RTO Management System
manual [B-6], section B.8.4.
6
(i) the proposed location of points of release, the
proposed maximum quantities and concentrations, and
the anticipated volume and flow rate of releases of
nuclear substances and hazardous substances into the
environment, including their physical, chemical and
radiological characteristics;
Specific information on release points and related information
is provided through the Management System Governing
Documentation Index [B-15], section 4.3.9, and references
therein.
Relevant requirements regarding environmental releases of
nuclear substances and hazardous substances are addressed by
Process 509200, Environmental Protection Program as
described in the RTO Management System manual [B-6],
section B.9.1.
6
(j) the proposed measures to control releases of nuclear
substances and hazardous substances into the
environment;
Relevant requirements regarding the control of environmental
releases of nuclear substances and hazardous substances are
addressed by Process 509200, Environmental Protection
Program as described in the RTO Management System manual
[B-6], section B.9.1.
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Class I Nuclear Facilities Regulation
6
(k) the proposed measures to prevent or mitigate the
effects of accidental releases of nuclear substances and
hazardous substances on the environment, the health
and safety of persons and the maintenance of national
security, including measures to
Relevant requirements regarding accidental releases of nuclear
substances and hazardous substances are addressed by Process
508730, Provide Emergency Preparedness as described in the
RTO Management System manual [B-6], section B.8.11.
Relevant requirements regarding security are addressed by
Process 508710, Provide Physical Security as described in the
RTO Management System manual [B-6], section B.8.9.
6(k)
(i) assist off-site authorities in planning and
preparing to limit the effects of an accidental
release,
(ii) notify off-site authorities of an accidental release
or the imminence of an accidental release,
(iii) report information to off-site authorities during
and after an accidental release,
(iv) assist off-site authorities in dealing with the
effects of an accidental release, and
(v) test the implementation of the measures to prevent
or mitigate the effects of an accidental release;
(l) the proposed measures to prevent acts of sabotage or
attempted sabotage at the nuclear facility, including
measures to alert the licensee to such acts;
(m) the proposed responsibilities of and qualification
requirements and training program for workers,
including the procedures for the requalification of
workers; and
See response under introduction to item (k) above.
6(k)
6(k)
6(k)
6(k)
6
6
See response under introduction to item (k) above.
See response under introduction to item (k) above.
See response under introduction to item (k) above.
See response under introduction to item (k) above.
Relevant requirements regarding security are addressed by
Process 508710, Provide Physical Security as described in the
RTO Management System manual [B-6], section B.8.9.
Relevant requirements regarding staff training are addressed
by Process 510200, Train and Develop Employees as
described in the RTO Management System manual [B-6],
section B.10.2.
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AECL Response
Class I Nuclear Facilities Regulation
6
Specific and generic position descriptions exist within each
facility to define responsibilities and qualification
requirements for operators and other workers. Training plans
are established accordingly based on these defined
requirements.
Relevant information on the results of recruitment and training
(n) the results that have been achieved in implementing
the program for recruiting, training and qualifying
exists within each facility. The data is reviewed annually in
workers in respect of the operation and maintenance of the annual safety report [B-18] for the site which is a
the nuclear facility.
requirement of the current site operating licence. This report
was most recently issued in 2010 May.
7
An application for a licence to decommission a Class I
nuclear facility shall contain the following information in
addition to the information required by section 3 of the
Class I Nuclear Facilities Regulations:
The current application to renew the operating licence for CRL
is relevant to the consideration of decommissioning Class I
nuclear facilities, and it is understood that the proposed
licensing documents will include information on the existing
permanently shutdown facilities located at CRL. AECL will
inform the CNSC under separate cover on a case-by-case basis
of the intention to proceed with decommissioning activities
with submission of detailed decommissioning plans, and
obtain all necessary approvals. Further specific information is
provided in items a to k below.
7
(a) a description of and the proposed schedule for the
decommissioning, including the proposed starting date
and the expected completion date of the
decommissioning and the rationale for the schedule;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
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(b) the nuclear substances, hazardous substances, land,
buildings, structures, systems, and equipment that will
be affected by the decommissioning;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
7
(c) the proposed measures, methods and procedures for
carrying on the decommissioning;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding decommissioning are
addressed by Process 508300, Decommission Sites and
Facilities, as described in the RTO Management System
manual [B-6], section B.8.4.
7
(d) the proposed measures to facilitate Canada’s
compliance with any applicable safeguards agreement;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding safeguards are addressed by
Process 508510, Manage Nuclear Materials and Safeguards,
as described in the RTO Management System manual [B-6],
section B.8.5.
7
(e) the nature and extent of any radioactive contamination
at the nuclear facility;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding radioactive contamination are
addressed by Process 509200, Provide Environmental
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1.
7
(f) the effects on the environment and the health and
safety of persons that may result from the
decommissioning, and the measures that will be taken
to prevent or mitigate those effects;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding environmental effects are
addressed by Process 509200, Provide Environmental
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AECL Response
Class I Nuclear Facilities Regulation
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1.
Relevant requirements regarding health and safety are
addressed by Process 510400, PEnsure Employee Safety and
Well-being, as described in the RTO Management System
manual [B-6], section B.10.3.
7
(g) the proposed location of points of release, the
proposed maximum quantities and concentrations, and
the anticipated volume and flow rate of releases of
nuclear substances and hazardous substances into the
environment, including their physical, chemical and
radiological characteristics;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding releases to the environment
are addressed by Process 509200, Provide Environmental
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1.
7
(h) the proposed measures to control releases of nuclear
substances and hazardous substances into the
environment;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding control of releases are
addressed by Process 509200, Provide Environmental
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1.
7
(i) the proposed measures to prevent or mitigate the
effects of accidental releases of nuclear substances and
hazardous substances on the environment, the health
and safety of persons and the maintenance of national
security, including an emergency response plan;
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding accidental releases are
addressed by Process 509200, Provide Environmental
Protection Program, as described in the RTO Management
System manual [B-6], section B.9.1.
Relevant requirements regarding health and safety are
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AECL Response
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addressed by Process 510400, Ensure Employee Safety and
Well-being, as described in the RTO Management System
manual [B-6], section B.10.3.
Relevant requirements regarding maintenance of security are
addressed by Process 508710, Provide Physical Security, as
described in the RTO Management System manual [B-6],
section B.8.9.
Relevant requirements regarding the provision of an
emergency response plan are addressed by Process 508730,
Provide Emergency Preparedness, as described in the RTO
Management System manual [B-6], section B.8.11.
7
(j) the proposed qualification requirements and training
program for workers; and
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding qualification requirements
and training are addressed by Process 510200, Train and
Develop Employees, as described in the RTO Management
System manual [B-6], section B.10.2.
7
(k) a description of the planned state of the site on
completion of the decommissioning.
This information will be provided on a case-by-case basis as
per the introduction to clause 7 above.
Relevant requirements regarding decommissioning end-state
are addressed by Process 508300, Decommission Sites and
Facilities, as described in the RTO Management System
manual [B-6], section B.8.4.
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AECL Response
Class I Nuclear Facilities Regulation
8
An application for a licence to abandon a Class I nuclear
facility shall contain the following information in addition
to the information required by sections 3 and 4 of the
General Nuclear Safety and Control Regulations:
This clause is not relevant to the current application for a
licence to operate CRL.
8
(a) the results of the decommissioning; and
See response above under introduction to clause 8.
8
(b) the results of the environmental monitoring programs.
See response above under introduction to clause 8.
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Section
Requirement
AECL Response
Class II Nuclear Facilities Regulations
3
An application for a licence to construct a Class II nuclear
facility shall contain the following information in addition
to the information required by section 3 of the General
Nuclear Safety and Control Regulations:
There are currently no plans for the construction of Class II
nuclear facilities at CRL. Any change to this situation during
the proposed term of a renewed site operating licence would be
covered on a case-by-case basis, with information provided, as
required.
3
(a) the proposed name and location of the nuclear facility;
See response above under introduction to clause 3.
3
(b) evidence that the applicant is the owner of the
proposed site or has authority from the owner of the
site to construct the nuclear facility;
See response above under introduction to clause 3.
3
(c) a description of the Class II prescribed equipment that
is proposed to be used, including its design operating
conditions;
See response above under introduction to clause 3.
3
(d) the proposed measures to control access within the
nuclear facility and any other safety-related features,
including the schematics of the devices involved and
their wiring;
See response above under introduction to clause 3.
3
(e) the proposed plans, elevations and drawings of the
nuclear facility, showing its layout, location, the
location of its components and the location of adjacent
areas that may be occupied by persons;
See response above under introduction to clause 3.
3
(f) the proposed purpose of the adjacent areas, including a See response above under introduction to clause 3.
description of their uses and the estimated levels of
occupancy;
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AECL Response
Class II Nuclear Facilities Regulations
3
(g) the proposed location, type, composition, thickness,
and density of shielding material, including the
method that will be used to verify the composition and
density and the calculations that will be used to
determine the adequacy of the shielding;
See response above under introduction to clause 3.
3
(h) the proposed location and dimensions of voids in the
shielding, including access ways and service ducts;
See response above under introduction to clause 3.
3
(i) a description of the proposed ventilation system,
including the ventilation flow rate, air circulation and
location of intake and discharge points in respect of
any irradiator or particle accelerator;
See response above under introduction to clause 3.
3
(j) the proposed quality assurance program for the design
and construction of the nuclear facility;
See response above under introduction to clause 3.
3
(k) the type and energy of radiation produced by any
particle accelerator to be encompassed by the licence;
See response above under introduction to clause 3.
3
(l) the anticipated maximum dose of radiation that may be
received by any person as a result of the
commissioning of and during the operation of the
nuclear facility;
See response above under introduction to clause 3.
3
(m) the direction of the direct beam of any teletherapy
machine to be encompassed by the licence and a
description of the physical means that may be used to
limit the direction of that beam;
See response above under introduction to clause 3.
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3
(n) the expected and maximum radiological workloads
during the commissioning and operation of the nuclear
facility, per week in grays at 1 m, for any teletherapy
machine to be encompassed by the licence;
See response above under introduction to clause 3.
3
(o) the anticipated number of hours per week that the
Class II prescribed equipment in the nuclear facility
will be operated for the purpose of treatment,
dosimetry, servicing or research;
See response above under introduction to clause 3.
3
(p) the effects on the environment and the health and
safety of persons that may result from the activity to
be licensed
See response above under introduction to clause 3.
3
(q) the proposed responsibilities of and qualification
requirements and training program for workers during
the operation of the nuclear facility;
See response above under introduction to clause 3.
3
(r) the program to inform persons living in the vicinity of
the site of the general nature and characteristics of the
anticipated effects on the environment and the health
and safety of persons that may result from the nuclear
facility; and
See response above under introduction to clause 3.
3
(s) the proposed plan for the decommissioning of the
nuclear facility
See response above under introduction to clause 3.
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4
An application for a licence to operate a Class II nuclear
facility shall contain the following information in addition
to the information required by section 3 of the General
Nuclear Safety and Control Regulations:
(a) the name and location of the nuclear facility;
Class II nuclear facilities located at CRL are as follows:
• Health Physics Neutron Generator
• GC60 Gamma Irradiator
• Gamma Beam 150C Gamma Irradiator
Relevant material on locations of the Class II nuclear facilities
is provided in the facility Safety Analysis Reports. Reference
to these documents may be found through the Sites and
Facilities Governing Documentation Index document [B-5],
section 4.1.2, and the documents referenced therein.
4
(b) the proposed commissioning plan;
Any required information or plans describing commissioning
of new Class II equipment or sources will be provided to the
CNSC by AECL, under separate cover, on a case-by-case
basis.
4
(c) a description of the results of any commissioning
work;
The commissioning of any upgrades are documented in the
facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5],
section 4.1.2, and the documents referenced therein.
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(d) evidence that the applicant is the owner of the site or
has authority from the owner of the site to operate the
nuclear facility;
Evidence of ownership may be found in the property report
provided with the letter from J.C. Amrouni to B.D. Howden,
CRL Deed, JCA-00-033, 2000 May 02 [B-12].
4
(e) a description of the components, systems and
equipment proposed to be used, including their design
operating conditions;
Relevant material for the Class II nuclear facilities is provided
in the facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5], section
4.1.2, and the documents referenced therein.
4
(f) the proposed measures, policies, methods, and
procedures for operating and maintaining the nuclear
facility;
Relevant material on locations of the Class II nuclear facilities
is provided in the facility Safety Analysis Reports. Reference
to these documents may be found through the Sites and
Facilities Governing Documentation Index document [B-5],
section 4.1.2, and the documents referenced therein.
4
(g) a description of the proposed procedures for handling,
storing, loading, and transporting nuclear substances
and hazardous substances;
Relevant material for nuclear substances and hazardous
substances for the Class II nuclear facilities is provided in the
facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5],
section 4.1.2, and the documents referenced therein.
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4
(h) the proposed quality assurance program;
Consistent with the global trend towards integration of
management systems, AECL is moving from separate
programs such as Quality Assurance to an Integrated
Management System. Hence this requirement is being
addressed by the RTO Management System manual [B-6],
which is compliant with the Canadian Standards Association
N286-05 entitled The Management System Requirements for
Nuclear Power Plants [B-13]. Where required to satisfy
external legislative and customer requirements, lower tiered
Quality Assurance Programs and supporting Manuals continue
to be maintained.
4
(i) the type and energy of radiation produced by any
particle accelerator to be encompassed by the licence;
Relevant material for the Class II nuclear facilities is provided
in the facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5], section
4.1.2, and the documents referenced therein.
4
(j) the proposed measures to ensure that the type of beam
producible by, and the maximum output energy, limits
to the beam orientation and maximum radiation dose
rate of, the Class II prescribed equipment cannot be
inadvertently altered;
Relevant material for the Class II nuclear facilities is provided
in the facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5], section
4.1.2, and the documents referenced therein.
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(k) the proposed method for measuring the effectiveness
of the shielding of the nuclear facility and any results
of those measurements;
Relevant procedures for determining effectiveness of shielding
for the Class II nuclear facilities is provided by Process
508740, Provide Radiation Protection, as described in the
RTO Management System manual [B-6], section B.8.12.
Further information on Process 508740 is presented in the
Management System Governing Documentation Index [B-15],
and documents referenced therein.
4
(l) a description of the proposed portable radiation
detection equipment, including its type, sensitivity,
range, and accuracy and the methods and procedures
for calibrating it;
Relevant material for the Class II nuclear facilities is provided
in the facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5], section
4.1.2, and the documents referenced therein.
4
(m) the proposed methods, procedures and equipment for
conducting the leak tests required by these
Regulations;
Annual leak testing and swipes for the GB 150C and GC-60
irradiators and all sealed sources in the HPNG, GB 150C and
GC-60 facilities are performed according to Leak Testing of
Sealed Sources, [B-20].
4
(n) a description of any proposed area radiation
monitoring system;
Relevant material for the Class II nuclear facilities is provided
in the facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5], section
4.1.2, and the documents referenced therein.
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(o) the anticipated maximum dose of radiation that may be This clause is not relevant to the current application.
received by any person as a result of the
commissioning of the nuclear facility;
4
(p) the expected and maximum radiological workloads,
per week in grays at 1 m, for any teletherapy machine
to be encompassed by the licence;
This clause is not relevant since there are no teletherapy
machines at CRL.
4
(q) the anticipated number of hours per week that the
Class II prescribed equipment in the nuclear facility
will be operated for the purpose of treatment,
dosimetry, servicing or research;
The average weekly operation of the HPNG facility is not
anticipated to exceed 25 h.
The average weekly operation of the GC-60 facility is not
anticipated to exceed 25 h.
Weekly operation of the Gamma Beam 150C ranges from 0 h
to as much as 5 d continuous irradiation (120 h with occasional
staff monitoring); however, routine operations are not expected
to exceed an average of 25 h per week.
4
(r) the proposed methods, procedures and equipment for
conducting radiation surveys, including the frequency
of the surveys and the location of radiation survey
points;
Relevant procedures for radiation surveys within the Class II
nuclear facilities is provided by Process 508740, Provide
Radiation Protection, as described in the RTO Management
System manual [B-6], section B.8.12. Further information on
Process 508740 is presented in the Management System
Governing Documentation Index [B-15], and documents
referenced therein.
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(s) the proposed responsibilities of and qualification
requirements and training program for workers; and
Relevant requirements regarding staff training are addressed
by Process 510200, Train and Develop Employees as
described in the RTO Management System manual [B-6],
section B.10.2.
Specific and generic position descriptions exist within each
facility to define responsibilities and qualification
requirements for operators and other workers. Training plans
are established accordingly based on these defined
requirements.
4
(t) the proposed plan for the decommissioning of the
nuclear facility.
There are currently no permanently shutdown Class II nuclear
facilities at CRL and therefore no current plans for imminent
decommissioning work. AECL will inform the CNSC under
separate cover on a case-by-case basis of the intention to
proceed with permanently shutting down any of the Class II
nuclear facilities.
The most recent decommissioning plan is reference [B-17]. A
revised Comprehensive Preliminary Decommissioning Plan.is
currently in final preparation and will shortly be provided to
CNSC staff.
5
An application for a licence to decommission a Class II
nuclear facility shall contain the following information in
addition to the information required by section 3 of the
General Nuclear Safety and Control Regulations:
This clause is not relevant to the current application for an
operating licence.
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(a) the name and location of the nuclear facility;
See response above under introduction to clause 5.
5
(b) the proposed nature of and schedule for the
decommissioning
See response above under introduction to clause 5.
5
(c) the land, buildings, structures, components, systems,
equipment, nuclear substances, and hazardous
substances that will be affected by the
decommissioning;
See response above under introduction to clause 5.
5
(d) the nature, quantity and activity of any radioactive
nuclear substances at the nuclear facility;
See response above under introduction to clause 5.
5
(e) the nature and extent of any radioactive contamination
at the nuclear facility, including radiation dose rates;
See response above under introduction to clause 5.
5
(f) the proposed measures to control releases of
radioactive nuclear substances and hazardous
substances into the environment;
See response above under introduction to clause 5.
5
(g) the anticipated maximum dose of radiation that may be See response above under introduction to clause 5.
received by any person as a result of the
decommissioning;
5
(h) the maximum quantities and concentrations of nuclear
substances and hazardous substances that may be
released into the environment;
See response above under introduction to clause 5.
5
(i) the effects on the environment and the health and
safety of persons that may result from the
decommissioning, and the measures that will be taken
to prevent or mitigate those effects;
See response above under introduction to clause 5.
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(j) the proposed responsibilities of and qualification
requirements for workers; and
See response above under introduction to clause 5.
5
(k) a description of the planned state of the site upon
completion of the decommissioning.
See response above under introduction to clause 5.
6
An application for a licence in respect of Class II
prescribed equipment, other than a licence to service, shall
contain a copy of or the number of any certificate relating
to the equipment in addition to the information required by
section 3 and, where applicable, section 4 of the General
Nuclear Safety and Control Regulations.
The Health Physics Neutron Generator is Class II prescribed
equipment. This equipment is a prototype that was
commissioned in 1961 and moved to its present location in
1970. There is no related certification. The manufacture,
installation and commissioning of this equipment pre-dates
requirements for certification documentation maintenance.
The Hopewell Designs GC-60 Series Gamma Beam Irradiator
is Class II prescribed equipment, Certificate Number C2-234­
0002-0-2021, issued 2006 February 24 (expiry
2021 January 31).
The Gammabeam 150C is Class II prescribed equipment,
Certificate Number 1-C002.A/2011, issued 2001 December 18
(expiry 2011 December 17).
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An application for a licence to service Class II prescribed
equipment shall contain the following information in
addition to the information required by section 3 of the
General Nuclear Safety and Control Regulations:
(a) the name, model number and characteristics of the
equipment or the number of the certificate relating to
the equipment;
Servicing of the Class II prescribed equipment at CRL is
incorporated into the facility operational practices and
procedures under the operating licence for the site.
The Health Physics Neutron Generator is a Model 9400
Neutron Generator manufactured in the previous century by
Texas Nuclear Corporation. Texas Nuclear Corporation is no
longer in business. There is no related certification. The
manufacture, installation and commissioning of this equipment
pre-dates requirements for certification documentation
maintenance.
The GC-60 gamma irradiator (Model SC2323G, S/N 206-709)
was manufactured by Hopewell Designs, Inc., and was
certified by the CNSC on 2006 February 24 (Certificate
Number C2-234-0002-0-2021).
The Gammabeam 150C gamma irradiator is a dry storage
panoramic irradiator manufactured by Nordion, Kanata, ON,
and was certified by the CNSC on 2001 December 18
(Certificate Number 1-C002.A/2001).
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(b) a description of the nature of the servicing proposed to
be carried on
Servicing and maintenance of the Health Physics Neutron
Generator relates to the following six subsystems: High
Voltage Source, Ion Source, Accelerating System, Target
System, Vacuum System, and Remote Control Console.
Repair and maintenance of these subsystems, and of the Safety
Interlocks controlling access to the irradiation hall, is carried
out as required by facility personnel or CRL maintenance
personnel.
Repair and maintenance of the Gammabeam 150C, and of the
Safety Interlocks controlling access to the irradiation hall, is
carried out as required by CRL maintenance personnel.
Repair and maintenance of the GC-60 irradiator is carried out
by the manufacturer (Hopewell Design, Inc.), under a service
contract. Repairs to the Safety Interlocks controlling access to
the irradiation hall are carried out as required by CRL
maintenance personnel.
7
(c) the proposed methods, procedures and equipment for
carrying on the servicing;
The servicing of the Health Physics Neutron Generator can be
accomplished using standard electrical and vacuum test
equipment, and hand tools. Troubleshooting and maintenance
procedures are provided in the accelerator instruction manual
(Instruction Manual, Model 9400 Neutron Generator Series,
Texas Nuclear Corp., Austin, Texas).
The servicing of the Gammabeam 150C can be accomplished
using standard electrical and mechanical test equipment, and
hand tools. Troubleshooting and maintenance procedures are
provided in the Biological Research Facility procedure [B-21].
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Class II Nuclear Facilities Regulations
Maintenance and servicing of the GC-60 can be accomplished
using standard electrical and mechanical test equipment, and
hand tools. This work is performed by the manufacturer
(Hopewell Design, Inc.) under a service contract.
7
(d) the proposed qualification requirements and training
program for workers; and
Relevant requirements regarding staff training are addressed
by Process 510200, Train and Develop Employees as
described in the RTO Management System manual [B-6],
section B.10.2.
Specific and generic position descriptions exist within each
facility to define responsibilities and qualification
requirements for operators and other workers. Training plans
are established accordingly based on these defined
requirements.
7
(e) the proposed procedures to be followed after
completion of the servicing to confirm that the
equipment is safe to use.
Relevant material for the Class II nuclear facilities is provided
in the facility Safety Analysis Reports. Reference to these
documents may be found through the Sites and Facilities
Governing Documentation Index document [B-5], section
4.1.2, and the documents referenced therein.
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Class II Nuclear Facilities Regulations
10
No person shall use Class II prescribed equipment unless
(a) it is a certified model; or
The Health Physics Neutron Generator is a Model 9400
Neutron Generator manufactured in the previous century by
Texas Nuclear Corporation. Texas Nuclear Corporation is no
longer in business. There is no related certification. The
manufacture, installation and commissioning of this equipment
pre-dates requirements for certification documentation
maintenance.
The GC-60 gamma irradiator (Model SC2323G, S/N 206-709)
was manufactured by Hopewell Designs, Inc., and was
certified by the CNSC on 2006 February 24 (Certificate
Number C2-234-0002-0-2021).
The Gammabeam 150C gamma irradiator is a dry storage
panoramic irradiator manufactured by Nordion, Kanata. ON,
and was certified by the CNSC on 2001 December 18
(Certificate Number 1-C002.A/2001).
10
(b) it is used in accordance with a licence that authorizes
its use for development purposes or for scientific
research that is not conducted on humans.
AECL understands the clause and does not conduct research
on humans.
11
(1) The Commission or a designated officer authorized
under paragraph 37(2)(a) of the Nuclear Safety and
Control Act may certify a model of Class II prescribed
equipment after receiving an application that includes
the following information:
This clause is not relevant to the current application for an
operating licence.
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(a) the applicant’s name and business address;
See response above under introduction to clause 11.
11
(b) the name and business address of the
manufacturer of the equipment;
See response above under introduction to clause 11.
11
(c) the brand name and model number of the
equipment;
See response above under introduction to clause 11.
11
(d) the design of the equipment and its components,
including any standards used in the design;
See response above under introduction to clause 11.
11
(e) the intended use of the equipment;
See response above under introduction to clause 11.
11
(f) the name, quantity in becquerels and form of the
nuclear substance to be incorporated into the
equipment;
See response above under introduction to clause 11.
11
(g) the method of incorporating the nuclear substance
into the equipment;
See response above under introduction to clause 11.
11
See response above under introduction to clause 11.
(h) the expected radiation dose rates around the
equipment in all modes of operation, including the
method, calculations and measurements used to
establish them;
11
(i) the maximum radiation dose rate that the
equipment can deliver;
See response above under introduction to clause 11.
11
(j) instructions for the use, transportation and storage
of the equipment;
See response above under introduction to clause 11.
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(k) instructions for conducting leak tests on the
equipment;
See response above under introduction to clause 11.
11
(l) instructions for dealing with accidents involving
the equipment;
See response above under introduction to clause 11.
11
(m) a description of the labelling of the equipment;
See response above under introduction to clause 11.
11
(n) the quality assurance program that was followed
during the design of the equipment and that will
be followed during the production of the
equipment;
See response above under introduction to clause 11.
11
See response above under introduction to clause 11.
(o) the type of package for and the procedures for
packaging and transporting any equipment that
may contain a nuclear substance, including the
emergency response plan to be followed in case of
a transportation accident involving the equipment;
11
(p) the recommended inspection and servicing
program for the equipment;
11
(q) the type of beam producible by, and the maximum See response above under introduction to clause 11.
output energy and limits to the beam orientation
of, any particle accelerator or radioactive source
teletherapy machine;
11
(r) the estimated maximum photon and neutron
leakage during the use of any teletherapy
machine; and
See response above under introduction to clause 11.
See response above under introduction to clause 11.
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11
(s) the half-lives of activated components of any
particle accelerator and the radiation dose rate at
30 cm from those components.
See response above under introduction to clause 11.
(2) The Commission or the designated officer may request Further information will be provided at the request of the
Commission.
any other information that is necessary to enable the
Commission or the designated officer to determine
whether the equipment model in question poses an
unreasonable risk to the environment, the health and
safety of persons or national security and whether
certification of the equipment model would be in
conformity with measures of control and international
obligations to which Canada has agreed.
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3
3
(1) An application for a licence in respect of a nuclear
substance or a radiation device, other than a licence to
service a radiation device, shall contain the following
information in addition to the information required by
section 3 of the General Nuclear Safety and Control
Regulations:
(a) the methods, procedures and equipment that will
be used to carry on the activity to be licensed;
Requirements at CRL regarding nuclear substances and
radiation devices are addressed accordingly, as per the
information provided under items “a” to “o” below.
Relevant requirements regarding methods, procedures and
equipment are addressed by various processes at CRL,
principally as identified below:
• Process 508510, Manage Nuclear Materials and
Safeguards, as described in the RTO Management System
manual [B-6], section B.8.5.
• Process 508740, Provide Radiation Protection, as
described in the RTO Management System manual [B-6],
section B.8.12.
• Process 509200, Provide Environmental Protection
Program, as described in the RTO Management System
manual [B-6], section B.9.1.
• Process 508520, Manage Transportation of Radioactive
Materials, as described in the RTO Management System
manual [B-6], section B.8.6.
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(b) the methods, procedures and equipment that will
be used while carrying on the activity to be
licensed, or during and following an accident, to
Relevant requirements regarding methods, procedures and
equipment are those referred to above under (a) and also:
• Process 508730, Provide Emergency Preparedness, as
described in the RTO Management System manual [B-6],
section B.8.11.
3(b)
(i) monitor the release of any radioactive
nuclear substance from the site of the activity
to be licensed,
See response above under (b).
3(b)
(ii) detect the presence of and record the
radiation dose rate and quantity in becquerels
of radioactive nuclear substances at the site
of the activity to be licensed,
See response above under (b).
3(b)
(iii) limit the spread of radioactive contamination
within and from the site of the activity to be
licensed, and
See response above under (b).
3(b)
(iv) decontaminate any person, site or equipment
contaminated as a result of the activity to be
licensed;
See response above under (b).
3
(c) a description of the circumstances in which the
decontamination referred to in subparagraph
(b)(iv) of the Nuclear Substances and Radiation
Devices Regulations will be carried out;
Relevant requirements regarding circumstances for
decontamination are addressed by Process 508740, Provide
Radiation Protection, as described in the RTO Management
System manual [B-6], section B.8.12.
3
(d) the proposed location of the activity to be
licensed, including a description of the site;
A general description of the CRL site is presented in the
document CRL Site Characteristics [B-11].
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3
(e) the roles, responsibilities, duties, qualifications,
and experience of workers;
Relevant requirements regarding staff training are addressed
by Process 510200, Train and Develop Employees as
described in the RTO Management System manual [B-6],
section B.10.2.
Specific and generic position descriptions exist within each
laboratory to define responsibilities and qualification
requirements for operators and other workers. Training plans
are established accordingly based on these defined
requirements.
3
(f) the proposed training program for workers;
Relevant requirements regarding staff training are addressed
by Process 510200, Train and Develop Employees as
described in the RTO Management System manual [B-6],
section B.10.2.
Specific and generic position descriptions exist within each
laboratory to define responsibilities and qualification
requirements for operators and other workers. Training plans
are established accordingly based on these defined
requirements.
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(g) the proposed instructions for dealing with
accidents, including fires and spills, in which the
nuclear substance may be involved;
Relevant requirements regarding accidents involving nuclear
substances are addressed by various processes at CRL,
principally as identified below:
• Process 508510, Manage Nuclear Materials and
Safeguards, as described in the RTO Management System
manual [B-6], section B.8.5.
• Process 508740, Provide Radiation Protection, as
described in the RTO Management System manual [B-6],
section B.8.12.
• Process 509200, Provide Environmental Protection
Program, as described in the RTO Management System
manual [B-6], section B.9.1.
• Process 508520, Manage Transportation of Radioactive
Materials, as described in the RTO Management System
manual [B-6], section B.8.6.
• Process 508730, Provide Emergency Preparedness, as
described in the RTO Management System manual [B-6],
section B.8.11.
3
(h) the proposed inspection program for the
equipment and systems that will be used to carry
on the activity to be licensed;
Relevant requirements regarding inspection of the equipment
and systems at the CRL site are addressed by Process 508740,
Provide Radiation Protection, as defined in the RTO
Management System manual [B-6], section B.8.12.
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Nuclear Substance and Radiation Devices Regulation
3
(i) the methods, procedures and equipment that will
be used to calibrate radiation survey meters in
accordance with these Regulations;
Relevant requirements regarding calibration of radiation
survey meters at the CRL site are addressed by
Process 508740, Provide Radiation Protection, as defined in
the RTO Management System manual [B-6], section B.8.12.
3
(j) the methods, procedures and equipment that will
be used to calibrate and verify the calibration of
dosimeters referred to in paragraphs 30(3)(d) and
(e) of the Nuclear Substances and Radiation
Devices Regulations;
Relevant requirements regarding calibration of dosimeters at
the CRL site are addressed by Process 508740, Provide
Radiation Protection, as defined in the RTO Management
System manual [B-6], section B.8.12.
3
(k) the methods, procedures and equipment that will
be used to conduct the leak tests and surveys
required by these Regulations;
Relevant requirements regarding leak testing and surveys at
the CRL site are addressed by Process 508740, Provide
Radiation Protection, as defined in the RTO Management
System manual [B-6], section B.8.12.
3
(l) where the application is in respect of a nuclear
substance that is an unsealed source and that is to
be used in a room, the proposed design of the
room;
Existing rooms that handle unsealed sources are designed in
accordance with the requirements of the Radiation Protection
program (Process 508740).
Relevant requirements regarding laboratory design at the CRL
site are addressed by Process 508740, Provide Radiation
Protection, as defined in the RTO Management System manual
[B-6], section B.8.12.
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AECL Response
Nuclear Substance and Radiation Devices Regulation
3
(m) if the application is in respect of a nuclear
substance that is contained in a radiation device,
the brand name and model number of the
radiation device, and the quantity of the devices;
Relevant requirements regarding nuclear substances and
radiation devices at the CRL site are maintained in a database
of sealed sources and radiation devices which is addressed by
Process 508740, Provide Radiation Protection, as defined in
the RTO Management System manual [B-6], section B.8.12.
This database is permanently available to all radiation
protection staff at the CRL site.
3
(n) where the application is in respect of Category I,
II or III nuclear material, as defined in section 1 of
the Nuclear Security Regulations,
3(n)
(i) the measures that will be taken to prevent
nuclear criticality, and
Relevant requirements regarding nuclear criticality at the CRL
site is addressed by Process 508550, Provide Nuclear
Criticality Safety Control, as defined in the RTO Management
System manual [B-6], section B.8.7.
3(n)
(ii) the information required by section 3 or 4 of
the Nuclear Security Regulations, as
applicable;
See further below under section 3 and 4 of Nuclear Security
Regulations
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AECL Response
Nuclear Substance and Radiation Devices Regulation
3
This clause is not relevant to the use of nuclear substances and
(o) if the applicant will be manufacturing or
radiation devices at CRL.
distributing radiation devices referred to in
paragraph 5(1)(c) of the Nuclear Substances and
Radiation Devices Regulations or section 6 or 7 of
the Nuclear Substances and Radiation Devices
Regulations, or check sources mentioned in
section 8.1 of the Nuclear Substances and
Radiation Devices Regulations, the proposed
procedure for the disposal of each radiation device
or check source or for its return to the
manufacturer.
4
An application for a licence to service a radiation device
shall contain the following information in addition to the
information required by section 3 of the General Nuclear
Safety and Control Regulations:
This section is not relevant to the current licensing application
to renew the CRL operating licence. Any servicing of
radiation devices is conducted under contract by external
suppliers..
4
(a) the brand name and model number of the device or the
number of the certificate relating to the device;
See response above under introduction to clause 4.
4
(b) a description of the nature of the servicing proposed to
be carried on;
See response above under introduction to clause 4.
4
(c) the proposed methods, procedures and equipment for
carrying on the servicing;
See response above under introduction to clause 4.
4
(d) the proposed qualification requirements and training
program for workers; and
See response above under introduction to clause 4.
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AECL Response
Nuclear Substance and Radiation Devices Regulation
4
11
(e) the proposed procedures to be followed after
completion of the servicing to confirm that the device
is safe to use.
(1) No person shall use a radiation device unless
(a) it is a certified model; or
11(1)
(b) it is used in accordance with a licence that
authorizes its use for development purposes.
11
(2) No person shall transfer a radiation device for use
within Canada unless it is a certified model.
(1) The Commission or a designated officer authorized
under paragraph 37(2)(a) of the Nuclear Safety and
Control Act may certify a model of a radiation device
after receiving an application that includes the
following information:
(a) the applicant’s name and business address;
(b) the name and business address of the
manufacturer of the device;
(c) the brand name and model number of the device;
12
12(1)
12(1)
12(1)
See response above under introduction to clause 4.
Relevant requirements regarding radiation devices at the CRL
site are maintained in a database which is addressed by
Process 508740, Provide Radiation Protection, as defined in
the RTO Management System manual [B-6], section B.8.12.
Relevant requirements regarding radiation devices at the CRL
site are maintained in a database which is addressed by
Process 508740, Provide Radiation Protection, as defined in
the RTO Management System manual [B-6], section B.8.12.
AECL understands the clause and no response is required.
AECL understands the clause and application will be made on
a case-by-case basis.
See form Application for Licensing [B-2].
AECL understands the clause and application will be made on
a case-by-case basis.
AECL understands the clause and application will be made on
a case-by-case basis.
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AECL Response
Nuclear Substance and Radiation Devices Regulation
12(1)
(d) the design of the device and its components,
including any standards used in the design;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(e) the intended use of the device;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(f) the name, quantity in becquerels and form of the
nuclear substance to be incorporated into the
device;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(g) the method of incorporating the nuclear substance
into the device;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(h) the expected radiation dose rates around the
device in all modes of operation, including the
method, calculations and measurements used to
establish them;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(i) instructions for the use, transportation and storage
of the device;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(j) instructions for conducting leak tests on the
device;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(k) instructions for dealing with accidents, including
fires and spills, in which the device may be
involved;
AECL understands the clause and application will be made on
a case-by-case basis.
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AECL Response
Nuclear Substance and Radiation Devices Regulation
12(1)
(l) a description of the labelling of the device;
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(m) the quality assurance program that was followed
during the design of the device and that will be
followed during production of the device; and
AECL understands the clause and application will be made on
a case-by-case basis.
12(1)
(n) the recommended inspection and servicing
program for the device.
AECL understands the clause and application will be made on
a case-by-case basis.
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Section
Requirement
AECL Response
Packaging and Transport of Nuclear Substances Regulations
3
An application for a licence to transport Category I, II or
III nuclear material, as defined in section 1 of the Nuclear
Security Regulations, other than a licence to transport
while in transit or a licence to transport under special
arrangement, shall contain, in addition to the information
required by section 3 of the General Nuclear Safety and
Control Regulations, the information required by section 5
of the Nuclear Security Regulations.
This clause is not relevant to the current application for CRL
site operating licence renewal.
4
An application for a licence to transport a nuclear
substance while in transit shall contain the following
information:
This clause is not relevant to the current application for CRL
site operating licence renewal.
4
(a) the name, address and telephone number of the
consignor;
See response above under introduction to clause 4.
4
See response above under introduction to clause 4.
(b) a description of the nuclear substance, including the
name, the chemical and physical form, the activity – or
in the case of fissile material, the mass – of each
nuclear substance in a package and the total quantity
of the activity or mass in the consignment;
4
(c) the country of origin of the nuclear substance;
See response above under introduction to clause 4.
4
(d) the name and address of each consignee;
See response above under introduction to clause 4.
4
(e) the reason for selecting a route through Canada;
See response above under introduction to clause 4.
4
(f) the name of every carrier;
See response above under introduction to clause 4.
4
(g) the route and schedule;
See response above under introduction to clause 4.
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AECL Response
Packaging and Transport of Nuclear Substances Regulations
4
(h) the dates, times and locations of arrival into and
departure from Canada
See response above under introduction to clause 4.
4
(i) the date, time and location of any scheduled stop or
transhipment in Canada;
See response above under introduction to clause 4.
4
(j) where the nuclear substance is required to be
transported in a package of a certified design or in a
package that has been approved as Type B(U)-96,
Type C-96 or H(U)-96 by a foreign competent
authority in accordance with the applicable process
specified in the IAEA Regulations, the number of the
certificate or approval applicable to the package;
See response above under introduction to clause 4.
4
(k) the number of packages that are to be transported;
See response above under introduction to clause 4.
4
(l) the types of conveyance to be used during transit;
See response above under introduction to clause 4.
4
(m) where a vessel is to be used as a conveyance during
transit, the name of the vessel and its flag state:
See response above under introduction to clause 4.
4
4
(m.1) for a special use vessel to be used as a
conveyance during transit, a document issued
by the competent authority of the vessel’s flag
state approving a radiation protection
programme;
(n) where the nuclear substance is to be transported by
sea, the International Maritime Dangerous Goods
Code transport schedule number for the nuclear
substance;
See response above under introduction to clause 4.
See response above under introduction to clause 4.
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AECL Response
Packaging and Transport of Nuclear Substances Regulations
4
(o) the United Nations number for the nuclear substance;
See response above under introduction to clause 4.
4
(p) the identification number of the emergency response
assistance plan approved under section 7 of the
Transportation of Dangerous Goods Act, 1992 or a
reference to the effect that such a plan is not required
by that Act, as the case may be; and
See response above under introduction to clause 4.
4
(q) where the nuclear substance is Category I, II or III
nuclear material, as defined in section 1 of the Nuclear
Security Regulations, the information required by
section 5 of those Regulations.
See response above under introduction to clause 4.
5
An application for a licence to package or transport a
nuclear substance under special arrangement shall contain,
in addition to the information required by section 3 of the
General Nuclear Safety and Control Regulations,
This clause is not relevant to the current application for CRL
site operating licence renewal.
5
(a) the information specified in paragraph 825 of the
IAEA Regulations; and
See response above under introduction to clause 5.
5
(b) where the nuclear substance is Category I, II or III
nuclear material, as defined in section 1 of the Nuclear
Security Regulations, the information required by
section 5 of those Regulations.
See response above under introduction to clause 5.
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Requirement
AECL Response
Packaging and Transport of Nuclear Substances Regulations
7
7(1)
7(1)
7(1)
7(1)
7(1)(d)
7(1)(d)
7(1)
(1) The Commission or a designated officer authorized
under paragraph 37(2)(a) of the Nuclear Safety and
Control Act may certify a package design, a design for
special form radioactive material or a design for low
dispersible radioactive material after receiving an
application that includes the following information:
(a) the information referred to in paragraphs 803,
805(b), 807, 810, and 813 of the IAEA
Regulations, as applicable;
(b) the number of any approval issued by a foreign
competent authority in accordance with the
applicable process specified in the IAEA
Regulations;
(c) Repealed, SOR/2003-405, s. 9
(d) in respect of a package design,
(i) the recommended inspection and servicing
program, and
(ii) instructions for packaging, transport,
receiving, maintenance, and unpackaging; and
(e) at the request of the Commission, any other
information that is necessary to enable the
Commission to determine if the application for
certification meets the requirements of these
Regulations.
This clause is not relevant to the current application for CRL
site operating licence renewal.
See response above under introduction to clause 7.
See response above under introduction to clause 7.
See response above under introduction to clause 7.
See response above under introduction to clause 7.
See response above under introduction to clause 7.
See response above under introduction to clause 7.
See response above under introduction to clause 7.
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AECL Response
Packaging and Transport of Nuclear Substances Regulations
7
(2) An applicant shall give the Commission a reasonable
opportunity to observe any test that the applicant
conducts to demonstrate compliance of a package
design, a design for special form radioactive material
or a design for low dispersible radioactive material
with these Regulations, including reasonable notice of
the date and time of the test.
See response above under introduction to clause 7.
7
(3) The Commission or a designated officer authorized
under paragraph 37(2)(a) of the Nuclear Safety and
Control Act may recertify a design certified under
subsection (1) of the Packaging and Transport of
Nuclear Substances Regulations if its technical
specifications have not changed and the Commission
or designated officer receives an application from the
certificate holder no later than 60 days after the expiry
date of the certificate.
The application shall include the following
information:
See response above under introduction to clause 7.
(a) a statement confirming that the drawings and
procedures previously submitted have not
changed or, if they have changed, a copy of the
revised drawings and procedures and a statement
confirming that the changes are without technical
significance and do not affect the safety of the
design;
See response above under introduction to clause 7.
7(3)
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Packaging and Transport of Nuclear Substances Regulations
7(3)
(b) a statement confirming that each package has
been maintained in compliance with the drawings
and procedures previously submitted;
See response above under introduction to clause 7.
7(3)
(c) in respect of a package design, a statement
confirming that the instructions previously
submitted have not changed;
See response above under introduction to clause 7.
7(3)
(d) unless previously submitted, the model number
and drawings of any capsule containing
radioactive material;
See response above under introduction to clause 7.
7(3)
(e) in respect of a certified package design, other than See response above under introduction to clause 7.
one referred to in paragraph (f) of the Packaging
and Transport of Nuclear Substances Regulations,
a list of the serial numbers of packages
manufactured and maintained in accordance with
the certified package design;
7(3)
(f) in respect of a certified package design that was
certified after approval by a foreign competent
authority, a list of the serial numbers of all
packages currently in use or intended to be used
in Canada;
See response above under introduction to clause 7.
7(3)
(g) a list of the known users of the latest certified
package design;
See response above under introduction to clause 7.
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AECL Response
Packaging and Transport of Nuclear Substances Regulations
7(3)
(h) a summary of the maintenance performed and any
operational or maintenance problems encountered
with the package, including the date, nature of the
maintenance or problem and any action taken;
(i) in respect of a design originating in a foreign
country, a copy of each package design approval
document or low dispersible radioactive material
approval document issued by the foreign
competent authority since the last certification;
See response above under introduction to clause 7.
7(3)
(j) a copy of the documents submitted to the foreign
competent authority in order to obtain a package
design approval document referred to in
paragraph (i) of the Packaging and Transport of
Nuclear Substances Regulations; and
See response above under introduction to clause 7.
7(3)
(k) at the request of the Commission, any other
information that is necessary to enable the
Commission to determine if the application meets
the applicable requirements of these Regulations.
See response above under introduction to clause 7.
7(3)
See response above under introduction to clause 7.
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AECL Response
3
An application for a licence in respect of Category I or II
nuclear material, other than a licence to transport, and an
application for a licence in respect of a nuclear facility
referred to in paragraph 2(b) of the Nuclear Security
Regulations shall contain the following information in
addition to the information required by section 3 of the
Nuclear Substances and Radiation Devices Regulations or
sections 3 to 8 of the Class I Nuclear Facilities Regulations,
as applicable:
Requirements in respect of Category I or II nuclear material at
CRL are addressed by Process 508710, Provide Physical
Security, as described in the RTO Management System manual
[B-6], section B.8.9.
This material is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
Additional aspects of the management of Category I or II
nuclear material at CRL are addressed by Process 508510,
Manage Nuclear Materials and Safeguards, and by Process
508740 Provide Radiation Protection, as described in the RTO
Management System manual [B-6], sections B.8.5 and B.8.12
respectively.
3
(a) a copy of the arrangements referred to in section 35 of
the Nuclear Security Regulations;
See response above under introduction to clause 3.
3
(b) the site plan referred to in section 16 of the Nuclear
Security Regulations;
See response above under introduction to clause 3.
3
(c) a description of the proposed security equipment,
systems and procedures;
See response above under introduction to clause 3.
3
(d) a description of the proposed on-site and off-site
communications equipment, systems and procedures;
See response above under introduction to clause 3.
Nuclear Security Regulations
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AECL Response
Nuclear Security Regulations
3
(e) a description of the proposed structure and
organization of the nuclear security officer service,
including the duties, responsibilities and training of
nuclear security officers;
See response above under introduction to clause 3.
3
(f) the proposed plan and procedures to assess and
respond to breaches of security; and
See response above under introduction to clause 3.
3
(g) the current threat and risk assessment.
See response above under introduction to clause 3.
4
An application for a licence in respect of Category III
nuclear material, other than a licence to transport, shall
contain, in addition to the information required by section
3 of the Nuclear Substances and Radiation Devices
Regulations, a description of the measures to be taken to
ensure compliance with subsection 7(3) and sections 7.1
and 7.2 of the Nuclear Security Regulations.
Requirements in respect of Category III nuclear material at
CRL are addressed by Process 508710, Provide Physical
Security, as described in the RTO Management System manual
[B-6], section B.8.9.
This content is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
Additional aspects of the management of Category III nuclear
material at CRL are addressed by Process 508510, Manage
Nuclear Materials and Safeguards, and by Process 508740
Provide Radiation Protection, as described in the RTO
Management System manual [B-6], sections B.8.5 and B.8.12
respectively.
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AECL Response
5
An application for a licence to transport Category I, II or
III nuclear material shall contain, in addition to any other
information required by sections 3 to 5 of the Packaging
and Transport of Nuclear Substances Regulations, a written
transportation security plan that includes
Requirements in respect of the transportation of Category I, II
or III nuclear material at CRL are addressed by
Process 508710, Provide Physical Security, as described in the
RTO Management System manual [B-6], section B.8.9.
This material is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
Additional aspects of the transportation of Category I, II or III
nuclear material at CRL are addressed by Process 508510,
Manage Nuclear Material and Safeguards and Process
508520, Manage Transportation of Radioactive Materials, as
described in the RTO Management System manual [B-6],
sections B.8.5 and B.8.6 respectively.
5
(a) the name, quantity, radiation level in Gy/h, chemical
and physical characteristics and isotopic composition
of the nuclear material;
See response above under introduction to clause 5.
5
(b) a threat assessment consisting of an evaluation of the
nature, likelihood and consequences of acts or events
that may place prescribed information or nuclear
material at risk;
See response above under introduction to clause 5.
5
(c) a description of the conveyance;
See response above under introduction to clause 5.
5
(d) the proposed security measures;
See response above under introduction to clause 5.
Nuclear Security Regulations
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AECL Response
Nuclear Security Regulations
5
(e) the communication arrangements made among the
licensee, the operator of the land vehicle transporting
the nuclear material, the recipient of the material and
any off-site response force along the route;
See response above under introduction to clause 5.
5
(f) the arrangements made between the licensee and any
off-site response force along the route;
See response above under introduction to clause 5.
5
(g) the planned route; and
See response above under introduction to clause 5.
5
(h) the alternate route to be used in case of an emergency.
See response above under introduction to clause 5.
7(3)
Every licensee shall process, use and store Category III
nuclear material in
Requirements in respect of the storage of Category III nuclear
material at CRL are addressed by Process 508710, Provide
Physical Security, as described in the RTO Management
System manual [B-6], section B.8.9.
This content is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
Additional aspects of the management of Category III nuclear
material at CRL are addressed by Process 508510, Manage
Nuclear Materials and Safeguards, and by Process 508740
Provide Radiation Protection, as described in the RTO
Management System manual [B-6], sections B.8.5 and B.8.12
respectively.
7(3)
(a) a protected area;
See response above under introduction to clause 7(3).
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AECL Response
Nuclear Security Regulations
7(3)
(b) an area that is under the direct visual surveillance of
the licensee; or
See response above under introduction to clause 7(3).
7(3)
(c) an area to which access is controlled by the licensee
and that is designed and constructed to prevent
persons from gaining unauthorized access to the
Category III nuclear material by using hand-held
tools.
See response above under introduction to clause 7(3).
7.1
(1) Subject to subsection (2), if a licensee processes, uses
or stores Category III nuclear material in an area
referred to in paragraph 7(3)(c), the licensee shall
ensure that the area is equipped with devices that
Requirements in respect of Category III nuclear material at
CRL are addressed by Process 508710, Provide Physical
Security, as described in the RTO Management System manual
[B-6], section B.8.9.
This content is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
Additional aspects of the management of Category III nuclear
material at CRL are addressed by Process 508510, Manage
Nuclear Materials and Safeguards, and by Process 508740
Provide Radiation Protection, as described in the RTO
Management System manual [B-6], sections B.8.5 and B.8.12
respectively.
7.1(1)
(a) detect any intrusion into it;
See response above under introduction to clause 7.1.
7.1(1)
(b) detect any unauthorized removal of Category III
nuclear material;
See response above under introduction to clause 7.1.
7.1(1)
(c) detect any tampering that may cause any of the
devices to malfunction or cease to function; and
See response above under introduction to clause 7.1.
M. Leblanc
77
2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Security Regulations
7.1(1)
(d) when an event referred to in paragraph (a), (b) or
(c) is detected, set off a continuous alarm signal
that is both audible and visible to a person in the
service of the licensee or of an alarm monitoring
service under contract to the licensee.
See response above under introduction to clause 7.1.
7.1
(2) A licensee need not comply with subsection (1) if it
takes physical protection measures in respect of the
area that provide the same level of protection as the
devices referred to in that subsection.
See response above under introduction to clause 7.1.
7.2
(1) Every licensee shall make or cause to be made written
arrangements with an off-site response force that is
capable of making an effective intervention at an area
where Category III nuclear material is processed, used
or stored.
Requirements in respect of an off-site response force at CRL
are addressed by Process 508710, Provide Physical Security,
as described in the RTO Management System manual [B-6],
section B.8.9.
This content is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
7.2
(2) The arrangements shall include provisions for
(a) annual familiarization visits by members of the
See response above under introduction to clause 7.2.
off-site response force to the area where the
Category III nuclear material is processed, used or
stored; and
7.2(2)
(b) the joint development of a contingency plan by
the licensee and the off-site response force to
facilitate the force making an effective
intervention.
See response above under introduction to clause 7.2.
M. Leblanc
78
2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Security Regulations
7.2
(3) If a licensee does not have alarm monitoring
See response above under introduction to clause 7.2.
capability, the alarm monitoring service under contract
to the licensee shall notify the licensee and the off-site
response force, immediately on receipt of an alarm
signal from the area where the Category III nuclear
material is processed, used or stored.
16
Every licensee shall maintain a site plan that indicates the
location and includes a description of the following, if
applicable:
16
(a) the perimeter of the lands on which a high-security site See response above under introduction to clause 16.
is located;
16
(b) the barrier enclosing every protected area;
See response above under introduction to clause 16.
16
(c) the protected areas;
See response above under introduction to clause 16.
16
(d) the unobstructed areas that meet the requirements set
out in section 10;
See response above under introduction to clause 16.
16
(e) the structure or barrier enclosing every inner area;
See response above under introduction to clause 16.
16
(f) the inner areas; and
See response above under introduction to clause 16.
16
(g) the vital areas.
See response above under introduction to clause 16.
Requirements in respect of a site plan of CRL are addressed by
Process 508710, Provide Physical Security, as described in the
RTO Management System manual [B-6], section B.8.9.
This content is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
M. Leblanc
79
2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
35
(1) Every licensee shall make or cause to be made written
arrangements with an off-site response force to
provide for the protection of a facility at which it
carries on licensed activities.
Requirements in respect of an off-site response force at CRL
are addressed by Process 508710, Provide Physical Security,
as described in the RTO Management System manual [B-6],
section B.8.9.
This content is considered as prescribed information for the
purposes of the Nuclear Safety and Control Act and no specific
details are provided in this unrestricted document.
35
(2) The arrangements shall include provisions
(a) to ensure that there is capability at all times for
immediate communication among the security
monitoring room, the on-site nuclear response
force and the off-site response force;
Nuclear Security Regulations
See response above under introduction to clause 35.
35
(b) to ensure that the off-site response force can
support the on-site nuclear response force in
making an effective intervention when requested
to do so by the licensee;
See response above under introduction to clause 35.
35
(c) for the installation of a two-way radio referred to
in subparagraph 15(2)(c)(i) and an alarm device
referred to in subparagraph 15(2)(c)(ii);
See response above under introduction to clause 35.
35
(d) for annual familiarization visits to the facility by
members of the off-site response force; and
See response above under introduction to clause 35.
M. Leblanc
80
2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Security Regulations
35
41
(e) for consultation between the licensee and the
off-site response force regarding the
arrangements, the resources and the equipment
available to the licensee and the off-site response
force, and any other matter relating to the security
of the facility.
See response above under introduction to clause 35.
An application for a licence in respect of a nuclear facility See response above under introduction to clause 35.
shall contain, in addition to the information required by
sections 3 to 8 of the Class I Nuclear Facilities Regulations,
a description of the physical protection measures to be
taken to ensure compliance with sections 42 to 48.
M. Leblanc
81
2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Non-Proliferation Import and Export Control Regulations
3
An application for a licence to import or export a
controlled nuclear substance, controlled nuclear equipment
or controlled nuclear information shall contain the
following information:
This section is not relevant to the current licensing application.
Import will be considered on a case-by-case basis and export is
covered by a separate licence.
3
(a) the applicant’s name, address and telephone number;
See response above under introduction to clause 3.
See response above under introduction to clause 3.
(b) a description of the substance, equipment or
information, including its quantity and the number of
the paragraph of the schedule in which it is referred to;
3
(c) the name and address of the supplier;
See response above under introduction to clause 3.
3
(d) the country of origin of the substance, equipment or
information;
See response above under introduction to clause 3.
3
(e) the name, address and, where the application is for a
licence to import, telephone number of each
consignee;
See response above under introduction to clause 3.
3
(f) the intended end-use of the substance, equipment or
information by the final consignee and the intended
end-use location;
See response above under introduction to clause 3.
3
(g) the number of any licence to possess the substance,
equipment or information; and
See response above under introduction to clause 3.
M. Leblanc
82 2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
Attachment B: Background Material for 2011 CRL Licence Renewal
Section
Requirement
AECL Response
Nuclear Non-Proliferation Import and Export Control Regulations
3
(h) where the application is in respect of a controlled
substance that is Category I, II or III nuclear material,
as defined in section 1 of the Nuclear Security
Regulations, the measures that will be taken to
facilitate Canada’s compliance with the Convention
on the Physical Protection of Nuclear Material,
INFCIRC/274/Rev.1.
See response above under introduction to clause 3.
References:
[B-1] E. Drumhiller, Letter to M.A. Leblanc, Chalk River Laboratories (CRL), Application for Operating Licence Renewal – 2011, CRL­
ACNO-10-0048-L, 2010 September 30.
[B-2]
CNSC Form, Application for Licensing, (Rev. 2000 July).
[B-3] Hon. H. Dhaliwal, Letter to Ms. L. Keen, Untitled, 2003 December 11.
[B-4] CNSC, Record of Proceedings, Including Reasons for Decision – Application for the Renewal of the Chalk River Laboratories
Nuclear Research and Test Establishment Operating Licence. Hearing dates: 2006 April 26 and 2006 June 28.
[B-5] Sites and Facilities Governing Documentation Index, 145-514100-GDI-002, Revision 0, 2010 September.
[B-6] Management System, Manual 145-514100-MAN-001, Revision 0, 2010 September.
[B-7] Action Levels for Chalk River Laboratories, CRL-508700-REPT-002, Revision 1, 2009 September.
[B-8] AECL Management Manual, CW-514000-MAN-002, Revision 2, 2010 June.
[B-9] Organization to Support CRL Operations, CRL-514100-ORG-001, Revision 0, 2010 September.
[B-10] Management System Contact and Responsibility List, 145-514100-016-000, Revision 0, 2010 September.
[B-11] CRL Site Characteristics, NSN-RQASD-035, Revision 4, 2004 January.
M. Leblanc
[B-12]
[B-13]
[B-14]
[B-15]
[B-16]
[B-17]
[B-18]
[B-19]
[B-20]
[B-21]
83
2010 September 30
CRL-ACNO-10-0048-L
UNRESTRICTED
J.-C. Amrouni, Letter with enclosure to B.D. Howden, CRL Deed, JCA-00-033, 2000 May 02. The Management System Requirements for Nuclear Power Plants, CSA N286-05. Policy, Employee Health and Safety, 00-009, Revision 3, 2010 June. Management System Governing Documentation Index, 145-514100-GDI-001, Revision 0, 2010 September. Policy, Environment, 00-004, Revision 2, 2010 March. Comprehensive Preliminary Decommissioning Plan for AECL’s Chalk River Laboratories, CPDP-01600-PDP-002, Revision 0, 2005 March.
CRL Annual Safety Review for 2009, CRL-00583-ASR-2009, Revision 0, 2010 April.
Environmental Monitoring in 2009 at Chalk River Laboratories, CRL-509243-ASR-2009, Revision 0, 2010 June.
Leak Testing of Sealed Sources, CW-508740-PRO-207, Revision 0, 2009 November 16.
BRF SOP 6.7 – Gamma Beam 150C Safety Testing and Maintenance, B524-121111-PRO-032, Revision 0, 2009 April 01.
Canadian Nuclear
Safety Commission
1+1
Commission canadienne
de surete nucleaire
Application for Licensing
Demande d'autorisation de permis
Send two copies to:
Envoyer deux exemplaires a:
Canadian Nuclear Safety Commission (CNSC)
Research and Production Facilities Division
P.O. Box 1046, Station B
Ottawa, Ontario
Canada KIP 5S9
Telephone: (613) 992-4634
Fax: (613) 995-5086
Commission canadienne de surete nucleaire (CCSN)
Division des installations de recherche et de production
C.P. 1046, Succursale B
Ottawa (Ontario)
Canada KIP 5S9
Telephone: (613) 992-4634
TeIecopieur: (613) 995-5086
~ Application TypelType de demande
Issuance I
Delivrance
o
o
[2J
o
o
Licence to prepare site / Permis de preparation de l' emplacement
Licence to construct / Permis de construction
Licence to operate / Permis d'exploitation
Licence to decommission / Permis de declassement
Licence to abandon / Permis d'abandon
o
o
Class II I Categorie II
Licence to construct / Permis de construction
Licence to operate / Permis d'exploitation
Licence to decommission / Permis de declassement
Licence to service / Permis d' entretien
o
o
o
o
o
[2J
o
o
~
Amendment I
Modification
Class IA or IB I Categorie IA ou IB
Current Licence or Approval Number (if applicable)
Numero du permis ou de l'approbation actuel (selon Ie cas)
l2..J CNSC File Number
o
o
o
NRTEOL-1.07/2011
(if applicable)
2.14
Numero de dossier de la CCSN (selon les cas)
4
INSTITUTION/ORGANISME
1.
4.1 NamelNom
Atomic Energy of Canada Limited
4.2 Address/Adresse
.:::2.:::25~1-",S'l'P""e""ak,"",m=an=-=D,,-,r,",-iv-,-,e,,--
CityNille Mississauga
_
-,=O~n""ta""n-",'0"--
Province
_
Postal Code/Code postal L5K IB2
4.3 Evidence of current legal status and composition of the Board of Directors included (for new applicants only).
Preuve du statutjuridique courant et composition du Conseil d'administration ci-jointes (pour nouveaux demandeurs
seulement).
~
5.1
Facility/lnstallation (Please check appropriate box.NeuilIez cocher Ie case appropriee.)
0
Particle Accelerator (non-medical) /
Accelerateur de particules (non-medical)
o
Type
_
o
Non Power Reactor/reacteur de faible puissance
o
Nuclear Substance Processing Facility/
Installation de traitement de substances nucleaires
(specify/preciser)
o
o
o
Energy/energie
_
ManufacturerlFabricant andiet
N°. (model/modele):
_
[2J Nuclear Research and Test Establishment!
Irradiator / Irradiateur
o
Etablissement de recherche et d'essais nucleaires
Type
_
o
(specify/preciser)
o
ManufacturerlFabricant andiet
N°. (model/modele):
_
Other (specify)/Autre (preciser):
_
Building or Room NumberlNumero de I'edifice au de la piece
5.2
N/A
Title/Titre Vice-President Operations. Chief Nuclear
5.3 Name of ManagerlNom du chef E. (Hank) Drumhiller
Officer & Site Licence Holder
5.4 Address (if different than 4.2)/Adresse (Autre que dans 4.2) Chalk River Laboratories
Postal Code/Code postal KOJ 110
Province Ontario
CityNille Chalk River
~ Support Technical DocumentslDocuments techniques connexes
Documentation enclosed with application as per Attachments A and B of letter from E. (Hank) Drumhiller to
M. Leblanc. Chalk River Laboratories (CRL) Application for Operating Licence Renewal - 2011.
CRL-ACNO-1O-0048-L. 2010 September 30.
Specify the parts of the Safety Report and/or any other documents supplied with the application. (if applicable)
Preciser les parties du rapport de surete et/ou tout autres documents fournis avec la demande. (selon Ie cas)
~
CNSC ExemptionlExemption de la CCSN
Is any part of this application subject to a request for exemption from the CNSC policy on access to licensing
information?
Dne partie de la presente demande fait-elle l' objet d'une demande d' exemption ala CCSN sur l' acces du public a
I'information relative a la delivrance des permis?
Yes/Oui 0
NolNon
l'2J
If yes, attach details of request for exemption.lDans l' affirmative, veuillez annexer les details de la demandes
d'exemption.
~
Contact Person!Agent de liaison
Person to contact on technical information and licensing matters.
La personne avec qui communiquer a propos du permis au pour obtenir des renseignements techniques.
8.1 NamelNom
Dave Cox
8.2 TitlelTitre Director - Safety Engineering and Licensing
8.3 Address/Adresse
Chalk River Laboratories
(if different than 4.2/ Autre que dans 4.2)
8.4
Province Ontario
CityNille Chalk River
Telephone/Telephone 613-584-8811 extension 45159
8.5
Postal Code/Code postal KOJ 110
FaxlTelecopieur 613-584-8023
~ Signing AuthoritylFonde de pouvoir
The person authorized by the institution, Board of Governors, or other such bodies to sign applications to the CNSC for
licences and authorizations related to the facility./ La personne autorisee par l' organisme, Conseil d' administration, au
autre personne a signer les demandes soumises a la CCSN et autorisations relatives a I'installation.
9.1 NamelNom E. (Hank) Drumhiller
9.2 TitlelTitre Vice-President Operations. Chief Nuclear Officer & Site Licence Holder
9.3 Address/Adresse Chalk River Laboratories
(if different than 4.2/Autre que dans 4.2)
9.4
CityNille Chalk River
Province Ontario
Telephone/Telephone 613-584-8811 extension 46722
9.5
Postal Code/Code postal KOJ 110
FaxITelecopieur 613-584-8227
~ Official LanguagelLangue officielle
In which official language do you wish us to communicate with you?
Dans quelle langue officielle desirez-vous que nous communiquions avec vous?
~ Application submitted bylDemande soumise par
Date
IO/c9/30
f
'I
English!Anglais l'2J
French/Franc;ais 0
J
~
(Signing Authority/Fonde de pouYoir)
Signature
Governing Documentation Index
MANAGEMENT SYSTEM
GOVERNING DOCUMENTATION
INDEX
145-514100-GDI-001
Revision 0
Prepared by
Rédigé par
Beauchamp Stephen - Section
Head, Engineering Programs &
Reviewed by Standards
Vérifié par
Van Drunen Christina - Manager,
Engineering Programs &
Approved by Standards
Approuvé par
Cox David S - Director - Safety
Engineering & Licensing
2010/09/30
2010/09/30
AECL - OFFICIAL
USE ONLY
À L'USAGE EXCLUSIF
D'EACL
Atomic Energy of
Canada Limited
Énergie Atomique du
Canada Limitée
2251 Speakman Drive
Mississauga, Ontario
Canada L5K 1B2
2251 rue Speakman
Mississauga (Ontario)
Canada L5K 1B2
AECL - OFFICIAL USE ONLY
Information Use
Governing Documentation Index
À USAGE EXCLUSIF - EACL
145-514100-GDI-001 Page i
Rev. 0
Always refer to myAECL for latest and OFFICIAL version.
()
Utilisation de
l'information
MANAGEMENT SYSTEM
GOVERNING
DOCUMENTATION INDEX
TABLE
OF CONTENTS
SECTION
SECTION
1.
1.
2.
2.
3.
3.
4.
4.
4.1
4.1.1
4.1
4.1.2
4.1.1
4.1.3
4.1.2
4.2
4.1.3
4.3
4.2
4.3.1
4.3
4.3.2
4.3.1
4.3.3
4.3.2
4.3.3
4.3.4
4.3.5
4.3.4
4.3.5
4.3.6
4.3.7
4.3.6
4.3.8
4.3.7
4.3.8
4.3.9
4.3.10
4.3.9
4.3.11
4.3.10
4.3.12
4.3.11
4.3.13
4.3.12
4.3.14
4.3.13
4.3.14
5.
5.
PAGE
PAGE
SCOPE ................................................................................................................1
SCOPE ................................................................................................................1
PURPOSE............................................................................................................1
PURPOSE............................................................................................................1
DEFINITIONS ....................................................................................................1
DEFINITIONS ....................................................................................................1
INDEX ................................................................................................................1
INDEX
External................................................................................................................1
Documents .............................................................................................2
CNSC
Licences and
Certificates.....................................................................2
External Documents
.............................................................................................2
Other
and Certificates ........................................................3
CNSCPermits,
LicencesLicences
and Certificates.....................................................................2
Codes,
Regulations
and
Standards
..................................................................5
Other Permits, Licences and Certificates
........................................................3
Corporate
and Manuals
...........................................................................7
Codes,Policies
Regulations
and Standards
..................................................................5
Governing
Documents
Corporate Policies
and .........................................................................................7
Manuals ...........................................................................7
Process
501000,
Understand
Markets and Customers .....................................7
Governing Documents
.........................................................................................7
Process
Vision,
Strategy
Corporate
Plan .........................7
Process 502000,
501000, Define
Understand
Markets
andand
Customers
.....................................7
Process
503000,
Develop
and
Design
Products,
Services
or .........................7
Process 502000, Define Vision, Strategy and Corporate Plan
Projects
..........................................................................................................8
Process 503000,
Develop and Design Products, Services or
Process
504000,
Market and Sell Products and Services .................................8
Projects ..........................................................................................................8
Process
Build,
Products,
Process 505000,
504000, Produce,
Market and
Sell Modify
Productsand
andDeliver
Services
.................................8
Services
or
Projects
........................................................................................8
Process 505000, Produce, Build, Modify and Deliver Products,
Process
Provide
After-sales Customer Support..................................9
Services506000,
or Projects
........................................................................................8
Process
507000,
Develop
and Maintain
NuclearSupport..................................9
Technology..........................9
Process 506000, Provide After-sales
Customer
Process
Nuclear
Laboratories,
Process 508000,
507000, Manage
Develop Facilities,
and Maintain
Nuclear
Technology..........................9
Materials
and
associated
Liabilities
..............................................................10
Process 508000, Manage Facilities, Nuclear Laboratories,
Process
Manage Liabilities
Environmental
Protection .....................................17
Materials509000,
and associated
..............................................................10
Process
and Manage Human
Resources.............................17
Process 510000,
509000, Develop
Manage Environmental
Protection
.....................................17
Process
511000,
Manage
Information
and
Associated
Technology ...............19
Process 510000, Develop and Manage Human Resources.............................17
Process
Financial Resources
..............................................20
Process 512000,
511000, Manage
Manage Information
and Associated
Technology ...............19
Process
513000,
Manage
External
Relationships
..........................................21
Process 512000, Manage Financial Resources ..............................................20
Process
Organizational
Performance
and Manage
Process 514000,
513000, Improve
Manage External
Relationships
..........................................21
Change.........................................................................................................21
Process 514000, Improve Organizational Performance and Manage
Change.........................................................................................................21
REFERENCES ..................................................................................................23
REFERENCES ..................................................................................................23
APPENDICES
Prepared by:
R.G.
LavoieA
Appendix
TABLE OF CONTENTS
Date:
Reviewed by:
Date:
Approved by:
Date:
2010/09/30
C. Van
Drunen
2010/09/30 R. Lesco
2010/09/30
Compliance
Matrices
.....................................................................................A-24
A.1
Cross Reference Table to CAN/CSA N286-05 Standard, Management
145-514100-GDI-001 2010/09/30
 Atomic Energy of Canada Limited
system requirements for nuclear power plants ................................................A-24
A.2
Cross Reference Table to ISO-9001:2008 Standard, Quality
management systems – Requirements ............................................................A-27
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page ii
Rev. 0
TABLE OF CONTENTS
SECTION
PAGE
APPENDICES
Appendix A Compliance Matrices .........................................................................................24
A.1
Cross Reference Table to CAN/CSA N286-05 Standard, Management
system requirements for nuclear power plants ....................................................24
A.2
Cross Reference Table to ISO-9001:2008 Standard, Quality
management systems – Requirements ................................................................27
145-514100-GDI-001 2010/09/30
ii
Information Use
AECL - OFFICIAL USE ONLY
Governing Documentation Index
À USAGE EXCLUSIF - EACL
Utilisation de
l'information
145-514100-GDI-001 Page 1
Rev. 0
Always refer to myAECL for latest and OFFICIAL version.
()
TABLE OF CONTENTS
MANAGEMENT SYSTEM GOVERNING DOCUMENTATION INDEX
SECTION
PAGE
1.
SCOPE
1.
1
This document provides an index to governing documents for Research and Technology
Operations (RTO) in support of the Management System [1].
This document consists primarily of external requirements and company policies, manuals and
APPENDICES
procedures issued for general use. They include mostly upper level documents such as Overview
documents,
process/program
Governing Documentation Index (GDI) documents,
No
table of Manuals
contentsand
entries
found.
and some lower level procedures.
For the latest revision of documents listed in the Index section and a more comprehensive list of
governing documents, refer to TRAK or the Procedural Applet on myAECL.
For the contact or subject matter expert of the processes, refer to the Contact and Responsibility
List [2].
Comments or out-of-date documents listed in here should be communicated to the Management
System Specialist, who maintains this document.
2.
PURPOSE
This document ensures that employees in RTO have a list of management system governing
documentation issued for general use.
3.
DEFINITIONS
For terms and abbreviations refer to the individual documents listed in the Index, or the
Acronyms, Abbreviations, and Definitions of Terms web site on myAECL.
(http://sps39/terms_definitions/terms.asp)
4.
INDEX
The section covers:



External documents in Section 4.1;
Corporate policies and manuals in Section 4.2; and
Governing documents issued for general use, grouped under the business processes, in
Section 4.3.
145-514100-GDI-001 2010/09/30
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 2
Rev. 0
4.1
External Documents
4.1.1
CNSC Licences and Certificates
Number
NRTEOL-01.07/2011
20004-17-10.2
Title / Description
Atomic Energy of Canada Limited Nuclear
Research and Testing Establishment
Operating Licence, Chalk River
Laboratories
Nuclear Research and Test Establishment
Decommissioning Licence, Whiteshell
Laboratories
Non-Power Reactor Operating Licence
(Includes MAPLE 1 and MAPLE 2
Reactors, and the New Processing Facility)
Dosimetry Service Licence
EL-01.01/2011
Export Licence, Chalk River Laboratories
2007 Mar
20004-7-11.2
Nuclear Substance and Radiation Devices
Licence, Port Hope
Nuclear Substance and Radiation Devices
Licence, LaPrade
Nuclear Substance and Radiation Devices
Licence, Low Level Waste Management
Office (X-ray Fluorescence Analysis)
Waste Management Facilities Operating
Licence, Douglas Point
Waste Management Facilities Operating
Licence, Gentilly-1
Waste Management Facilities Operating
Licence, Nuclear Power Demonstration
(NPD, Rolphton)
Waste Nuclear Substance Licence, Pine
Street Extension (Port Hope)
Waste Nuclear Substance Licence, Low
Level Waste Management Office (Historic
Waste)
Waste Nuclear Substance Licence, Port
Hope Radioactive Waste Management
Project
Waste Nuclear Substance Licence, Port
Hope Long-Term Low-Level Radioactive
Waste Management Project (Welcome
Waste Management Facility)
Class II Prescribed Equipment Certificate Texas Nuclear Neutron Generator 150-1H
Class II Prescribed Equipment Certificate BRF Irradiator
2007 Nov
NRTEDL-08.01/2018
NPROL-62.03/2011
20004-14-14.2
20004-15.11.0
WFOL-332-4.3
WFOL-331-4.3
WFOL-342-2.6
WNSL-W1-182.1/2011
WNSL-W2-2202.1/2016
WNSL-W1-344-1.4
WNSL-W1-2310.00/2014
C2-041-0001-0-2010
1-C002.A/2011
145-514100-GDI-001 2010/09/30
Rev
7
Date
2010 Jun
Comment
Expiry Date:
2011 Oct 31
1
2010 Apr
Expiry Date:
2018 Dec 31
2010 Mar
Expiry Date:
2011 Oct 31
2010 May
Expiry Date:
2011 May 31
Expiry Date:
2011 July 31
Expiry Date:
2011 Sep 30
Expiry Date:
2014 Oct 31
Expiry Date:
2011 Apr 30
2010 Jul
2006 May
2000 Aug
Amendment No. 3
1999 Oct
Indefinite
1999 Oct
Amendment No. 6
2007 Oct
Expiry Date:
2011 December 31
Expiry Date:
2016 Nov 30
2006 Nov
2007 Oct
Indefinite
2009 Oct
Expiry Date:
2014 Dec 31
2004 Jan
Expiry Date:
2010 Nov 30
Expiry Date:
2011 Dec 17
2001 Dec
2
Information Use
Number
4.1.2
Number
CERT-0046657
CERT-0041274
FHR-PER 10013 to
FHR-PER 10021
TSSA QA.84
TSSA QA.230
TSSA QA.379
TSSA QA.00547
145-514100-GDI-001 2010/09/30
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 3
Rev. 0
Title / Description
Various CNSC certificates for transport
packages used by AECL for shipping
off-site.
(Information include certificate number,
expiry, ownership and manufacturer)
Rev
Date
Comment
List maintained by
the RAM
Transportation
Program in
CW-508520-GDI106
Rev
Date
2010 Jun
Comment
Expires
2013 Jun 24
2009 Nov
Expires
2012 Nov 19
2010 Jul
Expires
2011 Jul 12
2010 Jan
Expires
2013 Feb 19
2009 May
Expires
2012 May 08
2009 Jan
Expires
2011 Dec 21
2010 Jan
Expires
2013 Feb 19
Other Permits, Licences and Certificates
Title / Description
ISO 14001:2004 Environmental
Management System Certification for
AECL Chalk River Laboratories and
Whiteshell Laboratories
ISO 9001:2008 Quality Management
System Certification for AECL Head
Office, Chalk River Laboratories, and
Low-Level Radioactive Waste
Management Office
Environment Canada Permits to charge
fire-extinguishing systems at various
locations at CRL
Manufacture of pressure vessels at CRL
and field sites controlled by CRL in
accordance with ASME Boiler and
Pressure Vessel Code, Section VIII,
Division 1 and CSA Standard B51, Boiler,
Pressure Vessel and Pressure Piping Code
Repair of ASME Section I, IV, & VIII,
Div.1, pressure relief valves using original
equipment manufactures at CRL only in
accordance with CSA Standard B51,
Boiler, Pressure Vessel and Pressure
Piping Code.
Construction of Class 1, 2, 3, Piping
Systems at CRL only in accordance with
CSA Standard N285.0, General
Requirements for Pressure Retaining
Systems and Components in CANDU
Nuclear Power Plants.
Repair and alteration of boilers, pressure
vessels, piping and Category A, B, C, D,
E, F & H type fittings at CRL and for
repairs and alterations at field sites
controlled by CRL in accordance with
CSA Standard B51, Pressure Vessel and
Pressure Piping Code.
3
Information Use
Number
TSSA QA.00548
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 4
Rev. 0
MB-07-018
Title / Description
Fabrication and assembly of power piping
at CRL and fabrication, assembly and
erection of power piping at fiel sites
controlled by CRL in accordance with
CSA Standards B51, Boiler, Pressure
Vessel and Pressure Piping Code and
ASME B31.1 Power Piping
Fabrication and assembly of process piping
at CRL and fabrication, assembly and
erection of process piping at field sites
controlled by CRL in accordance with
CSA Standards B51, Boiler, Pressure
Vessel and Pressure Piping Code and
ASME B31.3 Process Piping.
Fabrication of Class 1, 2, 3 & 4 Welded
and Non-welded Supports; With and
Without design Responsibility: at CRL
Only. In Accordance with CSA standards
N285, General Requirements for Pressure
Retaining Systems and Components in
CANDU Nuclear Power Plants.
Fabrication of Class 1, 2, 3 & 4 Welded
and Non-welded Category A, B, C, D, E, F
& H type Fittings only, with and without
Design Responsibility at CRL only in
accordance with CSA standards N285,
General Requirements for Pressure
Retaining Systems and Components in
CANDU Nuclear Power Plants.
Fabrication of welded and non-welded
Category A, B, C, D, E & H type fittings
only at CRL in accordance with CSA
Standards B51, Boiler, Pressure Vessel and
Pressure Piping Code
Quality Control Certification (for WL)
MB-07-019
Quality Control Certification (for WL)
General 0924787
Association of Professional Engineers of
Ontario Certificate of Authorization
granted to AECL
Canadian Association for Laboratory
Accreditation Inc. (CALA) Certificate of
Accreditation to ISO/IEC 17025:2005 for
AECL, Whiteshell Laboratories.
Ontario Ministry of the Environment,
Provincial Certificate of Approval – Waste
Disposal Site (at CRL)
Certificate of Sewage Works. Issued by the
Ministry of the Environment (for CRL)
TSSA QA.00549
TSSA QA.02107
TSSA QA.02108
TSSA QA.02716
A 2701
A413105
3-0944-77-006
145-514100-GDI-001 2010/09/30
Rev
Date
2010 Jan
Comment
Expires
2013 Feb 19
2010 Jan
Expires
2013 Feb 19
2009 Jan
Expires
2011 Dec 21
2009 Jan
Expires
2011 Dec 21
1987 Aug
Expiry extended to
2010 Nov 30
Expiry extended to
2010 Nov 30
Annual renewal
required.
2009 Sep
Expires
2012 Sep 16
1980 Mar
No expiry date
1977 Dec
No expiry date
4
Information Use
Number
TSSA R-1415
42-10239
0076522978-C
011-689-117
4.1.3
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 5
Rev. 0
Title / Description
Ontario Certificate of Registration of a
Plan, at CRL, Bldg 420
Ontario Ministry of Transportation - Motor
Vehicle Inspection Station Licence
Propane Conversion License.
Rev
Date
2005 Apr
Comment
No Expiry Date
For CRL
For CRL
Ontario Ministry of Transportation Commercial Vehicle Operator Registration
(CVOR) Certificate
Stationary Engineer Certificates for the
Power Plan Chief Engineer, Shift
Engineers and Operators (at CRL)
Licences for Elevators and Lifting Devices
– Issued by TSSA, posted on the
applicable equipment (at CRL)
For CRL
Issued annually
Codes, Regulations and Standards
This section is limited to external documents primarily in licences issued by the CNSC and
includes the main process in place to meet the requirements.
For more references to codes, regulations and standards, refer to the applicable process or
program documents (e.g., Overview document or GDI document).
Title / Description







CAN/CSA-N286.0-92: Overall Quality Assurance Program Requirements
for Nuclear Power Plants (1992)
CAN3-N286.1-00: Procurement Quality Assurance for Nuclear Power
Plants (2000)
CAN3-N286.2-00: Design Quality Assurance for Nuclear Power Plants
(2000)
CAN3-N286.3-99: Construction Quality Assurance for Nuclear Power
Plants (1999)
CAN/CSA-N286.4-M86: Commissioning Quality Assurance for Nuclear
Power Plants (1986)
N286.5-95: Operations Quality Assurance for Nuclear Power Plants (1995)
Business
Process
514200
505210
505220
508120
505240
505250
508200
508300

N286.6-98: Decommissioning Quality Assurance for Nuclear Power Plants
(1998)
N286.7-99 (R2003): Quality Assurance for Analytical, Scientific and
Design Computer Programs for Nuclear Power Plants
Management System Requirements for Nuclear Power Plants, CSA
N286-05 (2005)
Quality Management Systems – Requirements, ISO-9001

Environmental Management System, ISO 14001
509200


145-514100-GDI-001 2010/09/30
Comment
507230
514100
514100
5
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 6
Rev. 0
Title / Description
Business
Process
Various

CSA Z299 Series, Quality Assurance Program, Category 1, 2, 3, and 4.

Nuclear Safety and Control Act and Regulations
 General Nuclear Safety and Control Regulations
 Radiation Protection Regulations
 Class I Nuclear Facilities Regulations
 Class II Nuclear Facilities Regulations
 Nuclear Substances and Radiation Devices Regulations
 Packaging and Transport of Nuclear Substances Regulations
 Nuclear Security Regulations
 Nuclear Non-Proliferation Import and Export Control Regulations
 CNSC Cost Recovery Fees Regulations
Regulatory Document S-99, Reporting Requirements for Operating Nuclear
Power Plants
Radiation Emitting Devices Act and Regulations
508760
508760
508740
508200
508200
508740
508520
508710
508500
508760
508760
508730


GS-R-2, IAEA Preparedness and Response for a Nuclear or Radiological
Emergency, Safety Requirements (2002)
General Requirements for Pressure-Retaining Systems and Components in
CANDU Nuclear Power Plants, CSA Standards N285.0 (2008)
Boiler, Pressure Vessel, and Pressure Piping Code, B51 (2007)
Treaty on the Non Proliferation of Nuclear Weapons / Safeguards

Nuclear Liability Act and Regulations
508760

Series of ANSI/ANS-8.x Standards on Criticality Safety
508550

Standard for Facilities Handling Radioactive Materials, NFPA-801 (2008)
508720

Fire Protection for CANDU Nuclear Power Plants, CAN/CSA-N293 (2007)
508720

508730

Preparedness and Response for a Nuclear or Radiological Emergency,
Safety Requirements, IAEA GS-R-2 (2002)
Canadian Guidelines for Intervention during a Nuclear Emergency, Health
Canada H46-2/03-326E (2003)
International Atomic Energy Agency Safety Standard NS-R-4, Safety of
Nuclear Research Reactors, 2005 June
Nuclear Response Force Standard, S-298

Nuclear Security Officer, Physical and Psychological Fitness, RD-363
508710

National Building Code of Canada (2005)
508720

National Fire Code of Canada (2005)
508720






145-514100-GDI-001 2010/09/30
Comment
508740
508140
508510
508730
514400
508710
6
Information Use
4.2
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 7
Rev. 0
Corporate Policies and Manuals
Number
Policies
Title / Description
Rev
Date
00-001
PEOPLE
0
1999 Apr
00-003
SECURITY
1
2004 Mar
00-004
ENVIRONMENT
2
2010 Jan
00-007
QUALITY
1
2006 Apr
00-008
DISCLOSURE
0
2003 Sep
00-009
EMPLOYEE HEALTH AND SAFETY
2
2009 Jun
00-020
CODE OF ETHICS AND BUSINESS
CONDUCT
0
2004 Mar
CW-514100-MAN-002
AECL MANAGEMENT MANUAL
2
2010 Jun
00-01913-QAM-010
OVERALL QUALITY ASSURANCE
MANUAL
3
2003 Sep
Comment
Manuals
4.3
Governing Documents
Most documents in this section have been assigned the appropriate process number; however,
there are some documents that have not been numbered to the related process, or to the
appropriate process. The number of these documents will be addressed when next revised.
4.3.1
Process 501000, Understand Markets and Customers
For supporting governing documents, contact the Office of the Vice-President, Commercial or
the Marketing and Business Development department in the Commercial Operations division of
AECL.
4.3.2
Process 502000, Define Vision, Strategy and Corporate Plan
For additional supporting governing documents, contact the Financial and Business Services
department.
Number
145-514210-OV-001
145-502300-PLA-072
145-514100-GDI-001 2010/09/30
Title / Description
RESEARCH & TECHNOLOGY
OPERATIONS PLANNING AND
REPORTING
NUCLEAR LABORATORIES
MANAGEMENT PLAN SUMMARY
Rev
1
Date
2009 Aug
0
2010 Jul
Comment
7
Information Use
4.3.3
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 8
Rev. 0
Process 503000, Develop and Design Products, Services or Projects
For supporting governing documents, contact the appropriate department in the Commercial
Operations division of AECL.
For design, engineering and project processes in RTO, refer to Process 508100, Provide
Facilities and Support to Existing Facilities.
4.3.4
Process 504000, Market and Sell Products and Services
For supporting governing documents, contact the Office of the Vice-President, Commercial or
the Marketing and Business Development department in the Commercial Operations division of
AECL.
4.3.5
Process 505000, Produce, Build, Modify and Deliver Products, Services or
Projects
For RTO, this process covers construction, commissioning and procurement activities only.
Project management is covered in process 508110, Provide Project Management, and design
engineering in process 508120, Provide Design and Engineering.
Number
Title / Description
505210 - Perform Procurement and Materials Management
Rev
Date
00-01913-QAM-011
COMPANY-WIDE PROCUREMENT
QUALITY ASSURANCE MANUAL
PROCUREMENT
2
2005 Mar
1
2008 Feb
PROCUREMENT OF GOODS AND
SERVICES FROM EXTERNAL VENDORS
USING ORACLE IPROCUREMENT
PROCUREMENT OF SERVICES
PROVIDED BY A NON-EMPLOYEE.
USING ORACLE IPROCUREMENT
PROCUREMENT OF NUCLEAR
MATERIALS
PROJECT PROCUREMENT PROCESS
0
2009 Nov
0
2009 Oct
1
2009 Feb
2
2008 Jan
CONDUCT OF PROCUREMENT
ENGINEERING
RTO CONTRACT ADMINISTRATION
0
2009 Jul
1
2009 Jun
0
2007 Apr
CW-512000-REQ-103
CW-505210-PRO-612
CW-505210-PRO-611
CW-508510-PRO-188
159-505210-OV-001
145-508120-PRO-007
145-505210-OV-002
Comment
505230 - Manage Fabrication / Manufacturing
CW-505000-QAM-105
145-505240-PRO-001
COMPANY - WIDE CONSTRUCTION
QUALITY ASSURANCE MANUAL
CONSTRUCTION
D1
Under preparation
505250 - Manage Commissioning / Testing
CW-505000-QAM-106
145-514100-GDI-001 2010/09/30
COMPANY WIDE COMMISSIONING
QUALITY ASSURANCE MANUAL
0
2007 Jul
8
Information Use
Number
145-505250-PRO-001
4.3.6
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 9
Rev. 0
Title / Description
COMMISSIONING
Rev
0
Date
2010 Apr
Comment
This procedure
references CW
commissioning
procedures
Process 506000, Provide After-sales Customer Support
For supporting governing documents, contact the Office of the Vice-President, Commercial or
the Marketing and Business Development or Operations department in the Commercial
Operations division of AECL.
4.3.7
Process 507000, Develop and Maintain Nuclear Technology
This business process consists of processes and activities associated with managing the
technology to support our products and services. The process includes evaluating and improving
current technology; identifying, developing and demonstrating new technology; documenting
current learning for future use; managing technical resources, both physical and human; and
managing the technology portfolio.
Number
Title / Description
507100 - Plan Technology Development Activities
Rev
Date
CW-507100-PRO-291
PREPARATION OF TEST PLANS FOR
R&D
CW-507100-PRO-340
PROPOSAL AND CONTRACT REVIEW
FOR R&D
507200 - Develop Technology
0
2008 Sep
0
2007 Apr
CW-507200-QAM-101
0
2009 Jan
0
2007 Apr
0
2007 Feb
1
2007 Mar
0
2005 Apr
0
2007 Mar
CW-507200-PRO-254
CW-507200-PRO-383
COMPANY WIDE RESEARCH AND
DEVELOPMENT QUALITY ASSURANCE
MANUAL
CONTROLLING ITEMS ASSOCIATED
WITH R & D WORK PACKAGES
COMPLETION REVIEW FOR R&D
Comment
507230 - Develop Analytical, Scientific and Design Software
CW-507230-QAM-102
_VOL1
COMPANY WIDE ANALYTICAL,
SCIENTIFIC AND DESIGN COMPUTER
PROGRAMS - REQUIREMENTS
CW-507230-QAM-102 COMPANY WIDE ANALYTICAL,
SCIENTIFIC AND DESIGN COMPUTER
_VOL2
PROGRAMS
507300 - Maintain and Secure Technology
507320 - Manage Intellectual Property
CW-507320-OV-101
145-514100-GDI-001 2010/09/30
INTELLECTUAL PROPERTY
OPERATIONS
9
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 10
Rev. 0
Number
CW-507320-PRO-128
Title / Description
TECHNOLOGY TRANSFER
Rev
0
Date
2007 Apr
CW-507320-PRO-126
TRADE MARKS
0
2006 Jan
CW-507320-PRO-125
PATENTS
0
2006 Jan
4.3.8
Comment
Process 508000, Manage Facilities, Nuclear Laboratories, Materials and
associated Liabilities
Number
145-508000-TOR-002
Title / Description
NUCLEAR PERFORMANCE
ASSURANCE REVIEW BOARD
CRL-514200-COP-001
NUCLEAR PERFORMANCE
ASSURANCE REVIEW
500810 - Provide Facilities and Support to Existing Facilities
Rev
0
Date
2008 Oct
0
2008 Apr
2
2007 Aug
PROJECT MANAGEMENT
DOCUMENTATION INDEX
508120 - Provide Design and Engineering
D1
2010 Sep
CW-503000-QAM-103
COMPANY-WIDE DESIGN QUALITY
ASSURANCE MANUAL
DESIGN AUTHORITY FUNCTION
0
2009 Apr
1
2010 May
RTO ENGINEERING QUALITY
ASSURANCE PLAN
DESIGN DOCUMENTS
2
2009 Jul
1
2010 Mar
0
2009 Jan
0
2009 Jul
145-508120-PRO-001
TECHNICAL OPERABILITY
EVALUATION
CONDUCT OF PROCUREMENT
ENGINEERING
ENGINEERING CHANGE CONTROL
2
2008 Sep
145-508120-PRO-002
FIELD CHANGE CONTROL
2
2010 Feb
145-508120-PRO-003
CONDUCT OF DESIGN ENGINEERING
1
2010 Mar
NUCLEAR FACILITY VENTILATION
SYSTEM DESIGN
145-508120-REQ-001
DESIGN OF TEMPORARY EXHAUST
VENTILATION SYSTEMS
508130 - Configuration Management Tools
0
2010 May
0
2009 Nov
145-508130-PRO-003
0
Comment
Under revision
508110 - Provide Project Management
CW-508110-OV-103
PROJECT MANAGEMENT
145-508110-GDI-001
CW-505220-PRO-600
120-01913-QAP-001
145-508120-PRO-004
145-508120-PRO-006
145-508120-PRO-007
145-508120-REQ-002
145-514100-GDI-001 2010/09/30
DOCUMENT BASELINE CONTROL
In preparation
10
Information Use
Number
145-508130-PRO-001
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 11
Rev. 0
Rev
0
Date
2009 Dec
0
2010 Jan
145-508130-TOR-001
CONFIGURATION MANAGEMENT
OVERSIGHT
508140 - Management of Pressure Boundary System
0
2009 Sep
145-508140-TOR-001
PRESSURE BOUNDARY WORKING
GROUP TERMS OF REFERENCE
CRL-508200-QAM-111
MANUFACTURE, INSTALLATION,
REPAIR, ALTERATION,
REPLACEMENT AND MODIFICATION
OF PRESSURE RETAINING
COMPONENTS TO CSA B51, CSA B52
AND ASME SECTION I, IV, VIII DIV. 1,
B31.1, B31.3 AND B31.5 CODES
CRL-508200-QAM-110
REPAIR/SERVICE OF PRESSURE
RELIEF VALVES TO ASME SECTIONS
I, IV, VIII - DIVISION 1 AND CSA
B51/B52 AT AECL CHALK RIVER
LABORATORIES, CHALK RIVER,
ONTARIO, CANADA, K0J 1J0
CRL-508200-QAM-109
CONSTRUCTION AND
MAINTENANCE OF CLASS 1/2/3
NUCLEAR PIPING SYSTEMS,
NON-STANDARD FITTINGS,
COMPONENTS & NF PIPING
SUPPORTS TO CSA N285.0
STANDARD AT CHALK RIVER
LABORATORIES
RC-2000-029
WL ENGINEERING QUALITY
CONTROL MANUAL - DESIGN AND
CONSTRUCTION OF PRESSURE
RETAINING COMPONENTS AND
SYSTEMS TO CSA STANDARD B51
WLCS-108700-MAN-003 WL Engineering Relief Valve Testing and
Repair Quality Manual
508200 - Operate and Maintain Facilities and Nuclear Laboratories
0
2010 Feb
CW-508200-QAM-112
145-508130-PRO-004
CRL-508200-REQ-104
WL-508200-PRO-212
145-514100-GDI-001 2010/09/30
Title / Description
CONFIGURATION MANAGEMENT
WALKDOWNS
DESIGN BASELINE RECOVERY
NUCLEAR LABORATORIES,
NUCLEAR OPERATIONS QUALITY
ASSURANCE MANUAL
PRIME TENANTS AND BUILDING
CONTACTS
RESPONSIBILITY FOR FACILITIES
AND THE SAFETY OF OPERATIONS
AT THE WHITESHELL
LABORATORIES
Comment
2
0
2009 May
3
2010 Apr
6
2007 Apr
1
2007 May
1
2008 Mar
0
2005 May
5
2010 Jan
Being updated
New number is
WL-508140-QAM
-001
11
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 12
Rev. 0
Number
145-508200-PRO-005
Title / Description
WORK PLAN
Rev
1
Date
2010 Feb
145-508200-PRO-006
SYSTEM WALKDOWNS AND
WALKDOWN REPORTS
SYSTEM HEALTH PROGRAM
0
2010 Apr
0
2010 Apr
0
2009 May
0
2006 Nov
145-508200-PRO-008
TROUBLESHOOTING FACILTY
EQUIPMENT
CLASSIFICATION OF NUCLEAR
FACILITIES AND RADIONUCLIDE
LABORATORIES
READINESS FOR SERVICE
0
2010 Feb
CRL-508200-PRO-255
FOREIGN MATERIAL EXCLUSION
2
2009 Apr
CRL WORK MANAGEMENT PROCESS
OVERVIEW
WORK MANAGEMENT AND
CONTROL GOVERNING DOCUMENT
INDEX
0
2010 Mar
0
2010 Jun
FACILITY MANAGEMENT - OFFICE
SPACE AND FURNITURE
ROOM LABELLING
0
2010 Mar
0
2010 Apr
ORDER TO OPERATE
1
2009 Sep
PREPARATION OF OPERATING
MANUALS
CRL-508220-TOR-111
REACTOR IRRADIATIONS
COMMITTEE
508230 - Provide Maintenance
1
2009 Sep
1
2008 Jul
CRL-508230-OV-116
MAINTENANCE
0
2008 Jun
CRL-508230-REQ-190
MAINTENANCE CONDUCT
1
2009 May
CRL-508230-REQ-177
PREVENTATIVE MAINTENANCE
0
2007 Oct
CRL-508230-PRO-402
CORRECTIVE MAINTENANCE
0
2007 Sep
CRL-508230-PRO-401
MAINTENANCE PLANNING
0
2007 Jul
CRL-508230-PRO-404
CALIBRATION OF SYSTEM
INSTRUMENTATION
0
2007 Jun
145-508200-PRO-007
145-508200-PRO-004
CRL-508200-PRO-334
Comment
508238 - Work Management
187-508238-PRO-009
187-508238-GDI-001
508210 - Operate Sites
CRL-508210-PRO-353
CRL-508210-PRO-592
508220 - Operate Facilities
145-508220-PRO-002
145-508220-PRO-003
145-514100-GDI-001 2010/09/30
12
Information Use
Number
CRL-508230-PRO-403
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 13
Rev. 0
Title / Description
CRL- PREVENTIVE MAINTENANCE
PROGRAM
MAINTENANCE PROCEDURES
Rev
0
Date
2009 Jan
1
2010 Apr
4
2010 May
CRL-508230-PRO-399
CHALK RIVER PREVENTIVE
MAINTENANCE DEFERRAL PROCESS
GENERAL MAINTENANCE
0
2007 Jul
CRL-508230-PRO-405
PERIODIC INSPECTION
0
2008 Jul
CRL-508230-PRO-608
1
2009 Dec
0
2009 Mar
1
2009 Mar
0
2009 Oct
0
2009 Feb
0
2007 Sep
CRL-508230-PRO-406
MATERIAL CONTROL FOR ASME
SECTION III WORK
PREVENTIVE MAINTENANCE TASK
MANAGEMENT
WORK PACKAGE PREPARATION FOR
MAINTENANCE AND
CONSTRUCTION ACTIVITIES
ROUTE SHEET FOR ASME SECTION
III WORK
WORK PLAN AND CHECKLIST FOR
STEEL STRUCTURES
REPLACEMENT ITEM
MANAGEMENT
MEASURING AND TEST EQUIPMENT
0
2007 Jun
CRL-508230-PRO-418
MAINTENANCE PLAN PRODUCTION
0
2007 Jul
CRL-508230-PRO-411
0
2007 Jul
WL-508230-PRO-617
MASTER EQUIPMENT LIST
MANAGEMENT
GENERAL MAINTENANCE
WL-508230-PRO-618
MAINTENANCE PLANNING
0
WL-508230-PRO-619
CORRECTIVE MAINTENANCE
0
WL-508230-REQ-216
PREVENTIVE MAINTENANCE
0
WL-508230-PRO-620
CALIBRATION OF SYSTEM
INSTRUMENTATION
MEASURE & TEST EQUIPMENT
0
CRL-508230-PRO-400
CRL-508230-PRO-232
CRL-508230-PRO-532
CRL-508230-PRO-339
CRL-508230-PRO-609
CRL-508230-PRO-438
CRL-508230-PRO-407
WL-508230-PRO-622
WL-508230-PRO-623
REPLACEMENT ITEM
MANAGEMENT
508240 - Provide Manufacturing and other Support
Comment
0
0
0
508300 - Decommission Sites and Facilities
00-01913-QAM-016
145-514100-GDI-001 2010/09/30
COMPANY-WIDE
DECOMMISSIONING QUALITY
ASSURANCE MANUAL
0
2002 Nov
13
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 14
Rev. 0
Number
Title / Description
508400 - Manage and Maintain Offices and Buildings
Rev
Date
IDENTIFICATION AND
TRACEABILITY AT CONSTRUCTION
AND COMMISSIONING SITES
EXPORT PERMITS AND LICENSES
0
2006 Sep
3
2008 Dec
1
2008 Nov
CW-508500-GL-131
EXPORT PERMITS AND LICENSES USING EPLIS
GREEN PROCUREMENT
0
2007 Oct
CRL-508500-PRO-116
TRANSPORT OFF-SITE - CRL
4
2009 May
CRL-508500-PRO-114
TAG AND STORE - TEMPORARY
STORAGE OF NON-SURPLUS
COMMODITIES
CENTRAL STORES INVENTORY
3
2008 Nov
3
2008 Sep
POST-ORDER EVALUATION OF
CONTRACTORS
RECEIVING
0
2005 May
3
2009 Mar
0
2008 Dec
2
2010 Apr
1
2010 Apr
RADIOACTIVE MATERIAL (RAM)
0
TRANSPORTATION PROGRAM
CW-508520-REQ-203
RADIOACTIVE MATERIAL
1
TRANSPORTATION REQUIREMENTS
CW-508520-GDI-106
RADIOACTIVE MATERIAL
2
TRANSPORTATION
DOCUMENTATION INDEX AND
DEFINITIONS
CW-508520-PRO-614
RADIOACTIVE MATERIAL
0
TRANSPORTATION PROCESS
CW-508520-PRO-616
SHIPMENT OR RECEIPT OF
0
RADIOACTIVE MATERIAL
508530 - Manage non-nuclear materials and 508540 - Manage Services
2009 Oct
Comment
508500 - Manage Materials
CW-508500-REQ-169
CW-508500-PRO-123
CW-508500-PRO-241
CRL-508500-PRO-115
CRL-508500-PRO-122
CRL-508500-PRO-117
508510 - Manage Nuclear Materials and Safeguards
CW-508510-OV-137
NUCLEAR MATERIALS AND
SAFEGUARDS MANAGEMENT
CW-508510-REQ-119
NUCLEAR MATERIALS AND
SAFEGUARDS MANAGEMENT
CW-508510-GDI-107
NUCLEAR MATERIALS AND
SAFEGUARDS MANAGEMENT
GOVERNING DOCUMENTATION
INDEX AND DEFINITIONS
508520 - Manage Transportation of Radioactive Material
CW-508520-OV-138
145-514100-GDI-001 2010/09/30
2010 Apr
2010 Apr
2010 Jun
2010 May
14
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 15
Rev. 0
Number
Title / Description
Rev Date

Refer to Process 505210, Perform Procurement and Materials Management
Comment
508550 - Provide Nuclear Criticality Safety Control
145-508550-OV-001
NUCLEAR CRITICALITY SAFETY
2
2010 Apr
145-508550-REQ-001
NUCLEAR CRITICALITY SAFETY
REQUIREMENTS
NUCLEAR CRITICALITY SAFETY
DOCUMENTATION INDEX AND
DEFINITIONS
0
2009 Aug
5
2010 May
1
2010 Aug
0
2010 Feb
2
2010 Jun
PHYSICAL SECURITY PROGRAM
INDEX AND DEFINITIONS
508720 - Provide Fire Protection
0
2008 Dec
145-508720-OV-001
0
2009 Feb
FIRE PROTECTION PROGRAM INDEX
AND DEFINITIONS
508730 - Provide Emergency Preparedness
0
2009 Mar
CW-508730-OV-143
D1
2010 Feb
EMERGENCY PREPAREDNESS
PROGRAM
CW-508730-REQ-219
EMERGENCY PREPAREDNESS
PROGRAM REQUIREMENTS
508740 - Provide Radiation Protection
0
2010 Feb
D1
2010 Feb
RC-2000-633-0
AECL RESEARCH'S RADIATION
PROTECTION REQUIREMENTS
CW-508740-GDI-103
RADIATION PROTECTION
DOCUMENTATION, DEFINITIONS,
QUANTITIES AND UNITS
508750 - Provide Operating Experience
2
2008 Oct
2
2008 Oct
CW-508750-OV-125
0
2007 Oct
145-508550-GDI-001
508600 - Manage Wastes
CW-508600-OV-129
WASTE MANAGEMENT PROGRAM
OVERVIEW
CW-508600-GDI-108
WASTE MANAGEMENT PROGRAM
DOCUMENTATION INDEX AND
DEFINITIONS
508700 - Manage Operational Risks and Liabilities
508710 - Provide Physical Security
145-508710-OV-001
PHYSICAL SECURITY
145-508710-GDI-001
FIRE PROTECTION PROGRAM
145-508720-GDI-001
EMERGENCY PREPAREDNESS
CW-508730-GDI-109
145-514100-GDI-001 2010/09/30
OPERATING EXPERIENCE (OPEX)
PROGRAM
In preparation
In preparation
15
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 16
Rev. 0
Number
CW-508750-PRO-469
Title / Description
OPERATING EXPERIENCE (OPEX)
Rev
2
Date
2009 Jan
145-508750-PRO-003
PROCESSING OF INTERNAL &
EXTERNAL OPERATING
EXPERIENCE
OBSERVATION AND COACHING
0
2009 Dec
1
2008 Apr
3
2009 Apr
1
2006 Jan
0
2006 Mar
1
2007 Apr
REQUIREMENTS DOCUMENT FOR
1
CNSC INTERACTIONS
145-508760-GL-002-02
GUIDELINE FOR CNSC COMMISSION 0
MEETING/HEARING LOGISTICS
145-508760-GL-002-03
AECL PROTOCOL FOR
0
COMMUNICATING WITH CNSC
STAFF
508770 - Provide Safety Analysis and Operational Safety Assessment
2009 May
CW-508770-PRO-190
1
2007 May
1
2010 Feb
HAZARD AND OPERABILITY
(HAZOP) STUDIES
CRL-508770-PRO-143
OSA FACILITY SAFETY
INSPECTIONS
CRL-508770-PRO-144
SAFETY ASSESSMENT AND CHANGE
CATEGORY VERIFICATION OF
DESIGN AND OPERATIONAL
CHANGES IN NUCLEAR FACILITIES
508790 - Provide Dosimetry Services
0
2006 Jan
1
2006 Feb
0
2006 Jan
DSP-508790-QAM-001
0
2008 Nov
0
2009 Sep
CW-508750-PRO-300
Comment
508760 - Provide Licensing Services
CW-508760-PRO-246
CW-508760-PRO-159
CW-508760-PRO-167
CRL-508760-PRO-343
MANAGING CANADIAN NUCLEAR
SAFETY COMMISSION
CORRESPONDENCE AND
REGULATORY COMMITMENTS
LICENSING OF DECOMMISSIONING
FACILITIES
LICENSING AND SAFETY FOR NEW
AND MODIFIED FACILITIES
REPORTING TO THE CNSC
145-508760-REQ-002
WL-508770-GL-190-01
GRADED HAZARD REVIEW OF
PROCEDURES AND WORK PLANS
JOB SCOPE AND SAFETY ANALYSIS
CW-508770-PRO-236
DSP-508790-GDI-001
DOSIMETRY SERVICES QA MANUAL
DOSIMETRY SERVICES PROGRAM
DOCUMENTATION INDEX
508800 - Manage Physical Liabilities (Radiological and Chemical)
145-514100-GDI-001 2010/09/30
2009 Mar
2009 Mar
16
Information Use
4.3.9
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 17
Rev. 0
Process 509000, Manage Environmental Protection
This business process consists of processes and activities associated with the protection of the
environment for operations at AECL’s Canadian sites as well as for provision of products and
services provided to customers.
Number
Title / Description
Rev
509200 - Provide Environmental Protection Program for Canadian Sites
Date
CW-509200-OV-113
1
2010 Mar
4
2008 Apr
CW-509200-GDI-101
4.3.10
ENVIRONMENTAL MANAGEMENT
SYSTEM FOR AECL SITES IN
CANADA
ENVIRONMENTAL PROTECTION
PROGRAM DOCUMENTATION
Comment
Process 510000, Develop and Manage Human Resources
Number
CW-510000-REQ-166
Title / Description
PRIVACY STATEMENT
Rev
1
Date
2007 Mar
CW-510000-PRO-529
INVESTIGATION OF DISCLOSURES
0
2009 May
CW-510000-PRO-217
DISCLOSURE OF INFORMATION
CONCERNING WRONGDOING
PROTECTION OF PERSONAL
INFORMATION
PROCEDURE FOR APPOINTING
FACILITY AUTHORITIES
PROCEDURE FOR APPOINTING
FACILITY MANAGERS
3
2009 May
1
2007 Mar
2
2010 Jun
2
2010 Jun
EMPLOYMENT EQUITY
COMMITTEES
WORKPLACE ACCOMMODATION
1
2007 Dec
0
2008 Apr
APPOINTMENT OF
ENGINEER/RESEARCHER EMERITUS
CW-510100-PRO-225
ACCOUNTABILITY STATEMENTS
AND POSITION DESCRIPTIONS
145-510100-PRO-001
RESEARCH & TECHNOLOGY
OPERATIONS (RTO) STAFF HIRING
145-510100-OI-001
STAFFING IN THE NUCLEAR
LABORATORIES BUSINESS UNIT
(NLBU)
510200 - Train and Develop Employees
0
2007 May
0
2007 Dec
0
2009 Dec
2
2006 Apr
CW-510000-MAN-001
1
2009 Nov
CW-510000-GL-113
145-510000-PRO-002
145-510000-PRO-003
Comment
510100 - Manage Staffing
CW-510100-TOR-119
CW-510100-PRO-510
CW-510100-PRO-327
145-514100-GDI-001 2010/09/30
AECL SYSTEMATIC APPROACH TO
TRAINING (SAT)
17
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 18
Rev. 0
Number
CRL-510000-MAN-102
Title / Description
CRL APPRENTICESHIP MANUAL
Rev
1
Date
2010 Mar
CRL-510200-PRO-590
NEW EMPLOYEE ORIENTATION
0
2009 Sep
CW-510200-PRO-344
ASSESSMENT AND IDENTIFICATION
OF PERSONNEL QUALIFICATIONS
AND TRAINING NEEDS
EMPLOYEE TRAINING - APPROVING,
ATTENDING AND RECORDING
TUITION REIMBURSEMENT
2
2010 May
1
2010 May
1
1998 Aug
145-510200-PRO-002
PREPARATION OF SYSTEM
TRAINING MANUALS
510300 - Assess and Reward Employee Performance
0
2009 Sep
CW-510300-PRO-335
PERFORMANCE PLANNING AND
REVIEW FORMS FOR UNIONIZED
EMPLOYEES
CW-510300-PRO-213
MATERNITY AND PARENTAL LEAVE
PROCEDURE
510400 - Ensure Employee Safety & Well-being
0
2008 Mar
0
2009 Aug
CW-510400-TOR-118
0
2009 Jan
0
2007 May
0
2010 Jun
CW-510400-REQ-168
AECL HEALTH AND SAFETY POLICY
COMMITTEE
AECL OCCUPATIONAL HEALTH AND
SAFETY PROGRAM MANUAL
OCCUPATIONAL SAFETY AND
HEALTH PROGRAM
SMOKING
0
2006 Oct
CW-510400-REQ-152
DRUG AND ALCOHOL
0
2006 Sep
CW-510400-PRO-610
PROTECTIVE FOOTWEAR
0
2010 Feb
CW-510400-PRO-574
0
2009 Sep
CW-510400-PRO-561
PREVENTING VIOLENCE IN THE
WORKPLACE
WORKING ALONE
0
2009 Mar
CW-510400-PRO-380
FIRST AID PROGRAM
0
2007 May
CW-510400-PRO-379
RETURN TO WORK PROGRAM
1
2009 Sep
CW-510400-PRO-378
WORKER'S COMPENSATION
0
2007 May
CW-510400-PRO-377
WORKPLACE INSPECTIONS
0
2007 May
WL-95000-PRO-484
HOUSEKEEPING ACTIVITIES IN WL
NUCLEAR FACILITIES
1
2009 Mar
CW-510200-PRO-498
00-261_2
CW-510400-MAN-001
CW-510400-GDI-110
145-514100-GDI-001 2010/09/30
Comment
18
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 19
Rev. 0
Number
Title / Description
510600 - Manage Employee Security
Rev
Date
CW-510600-PRO-237
PERSONNEL SECURITY
0
2009 Jul
CW-510600-OV-122
EMPLOYEE SECURITY
0
2007 Jul
CW-510600-PRO-636
PROCESSES ASSOCIATED WITH
EMPLOYEE SECURITY AND
RELATED ACTIVITIES
SECURITY SELF-PROTECTION
GUIDELINE
REPORTING OF SUSPECTED
MATERIAL MATTERS
THREAT AND RISK ASSESSMENT
PROCEDURE
CAMERA USE AT AECL SITES
0
2010 Apr
0
2009 Mar
0
2009 May
0
2007 Jul
0
2007 Mar
CW-510600-GL-120
CW-510600-PRO-530
CW-510600-PRO-422
CW-510600-PRO-349
4.3.11
Comment
Process 511000, Manage Information and Associated Technology
Number
Title / Description
Rev Date
Comment
51110 - Design, Implement and Maintain Systems for Software, Hardware and Network Systems
CW-511100-PRO-211
BACKUP AND RECOVERY OF DATA
0
2009 Jun
CW-511100-REQ-188
USE OF MOBILE WIRELESS DEVICES
1
2010 Mar
USE OF NETWORK AND COMPUTER
SYSTEMS
511200 - Design, Implement and Maintain Information Systems
1
2010 May
CW-511200-MAN-001
0
2005 Dec
CW-511200-PRO-131
myAECL MANUAL AND STYLE
GUIDE FOR USERS AND
ADMINISTRATORS
USE OF ELECTRONIC MESSAGING
1
2010 May
CW-511200-PRO-130
USE OF THE INTERNET
1
2010 May
145-511200-TOR-001
NLBU TRAK STEERING COMMITTEE
0
2007 Nov
0
2003 Jun
CW-511300-REQ-187
AECL DOCUMENT NUMBERING
SYSTEM - GENERAL PRINCIPLES
DOCUMENT CONTROL
0
2009 May
CW-511300-PRO-412
RECORDS MANAGEMENT
1
2010 Mar
CW-511300-REQ-176
REQUIREMENTS FOR RECORDS TO
BE RECOGNIZED AS ORIGINALS
0
2007 Jun
CW-511100-PRO-129
NLBU replaced by
RTO
511300 - Manage Information Assets
CW-511000-MAN-001
145-514100-GDI-001 2010/09/30
19
Information Use
Number
CW-511300-PRO-415
CW-511300-PRO-414
CW-511300-PRO-183
CW-511300-MAN-001
CW-511300-PRO-161
CW-511300-OI-102
CW-511300-PRO-158
CW-511300-OI-148
CW-511300-OI-124
CW-511300-MAN-002
CW-511300-GL-108
CW-511300-GL-102
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 20
Rev. 0
Title / Description
PROCESS FOR NUMBERING
RECORDS
RECORDS RETENTION AND
DISPOSITION
OFF-LINE STORAGE OF ELECTRONIC
DATA
OVERVIEW OF TRAK ELECTRONIC
DOCUMENT MANAGEMENT SYSTEM
PRODUCTION AND CONTROL OF
AECL DOCUMENTS USING TRAK
PRODUCTION AND RELEASE OF
DRAWINGS USING TRAK
DOCUMENT REVIEW AND
COMMENT
MANAGEMENT OF
DOCUMENTATION LIENS
REVIEW OF TEST PROCEDURES AND
REPORTS
HOW TO CREATE FORMAL
DOCUMENTS USING THE AECL
TEMPLATE (WORD 2007)
ACRONYMS, ABBREVIATIONS AND
DEFINITIONS OF TERMS
DATE FORMAT
Rev
2
Date
2008 Oct
0
2009 May
0
2006 Sep
0
2008 Jan
0
2005 Sep
0
2005 Nov
1
2008 Apr
0
2007 Mar
0
2007 Mar
0
2010 Apr
0
2006 Jan
2
2008 Jan
Comment
511400 - Provide Security of IT Infrastructure and of Information Assets
CW-511400-REQ-178
CW-511400-PRO-109
CW-511400-OI-101
4.3.12
ACCESS CONTROL FOR
APPLICATIONS / INFORMATION
COLLECTIONS
PROTECTION OF INFORMATION
1
2009 Aug
3
2007 Dec
CHANGING THE SECURITY
IDENTIFIER ON AECL
DOCUMENTATION
1
2006 Oct
Process 512000, Manage Financial Resources
Number
CW-512000-REQ-106
Title / Description
AUTHORIZATION
Rev
1
Date
2006 Nov
CW-512000-REQ-103
PROCUREMENT
1
2008 Feb
CW-512100-REQ-105
BUDGET TRANSFER
0
2007 May
CW-512000-PRO-604
ACQUISITION OF IT RELATED
PRODUCTS AND SERVICES
TRAVEL
1
2009 Dec
3
2010 Mar
CW-512200-PRO-120
145-514100-GDI-001 2010/09/30
Comment
20
Information Use
Number
CW-512200-REQ-174
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 21
Rev. 0
Rev
2
Date
2010 Mar
0
2006 Jan
CW-512200-PRO-118
Title / Description
TRAVEL - BOARD OF DIRECTORS
AND EXECUTIVES
CORPORATE CHARGE CARD AND
BUSINESS EXPENSES
ORACLE TIME AND LABOUR
0
2006 Feb
CW-512500-REQ-338
INVENTORIES
0
2007 Aug
CW-512500-REQ-100
0
2007 May
CW-512500-PRO-337
RESTRICTED TRANSACTIONS AND
AUTHORIZATION
ACCOUNTS PAYABLE
0
2007 Aug
CW-512500-PRO-223
WARRANTIES AND CONTINGENCIES
0
2006 Jun
CW-512500-PRO-135
PROPERTY, PLANT & EQUIPMENT
AND INTANGIBLE ASSETS
SALE OF MOVEABLE ASSETS
0
2006 Jun
0
2007 May
ACQUISITION OF IT RELATED
PRODUCTS AND SERVICES
REQUEST FOR AUTHORIZATION
(RFA) PROCESS
2
2010 Aug
2
2009 Dec
CW-512200-PRO-119
CW-512500-PRO-132
CW-512000-PRO-604
145-512600-OI-539-01
4.3.13
Comment
Process 513000, Manage External Relationships
For other supporting governing documents, contact the appropriate department in the
Commercial Operations division of AECL, or AECL Corporate.
Number
CRL-513430-REPT-001
208-513000-PRO-001
CW-513730-PRO-566
CW-513730-PRO-565
4.3.14
Title / Description
PUBLIC INFORMATION PROGRAM
FOR AECL CHALK RIVER
LABORATORIES CRL FOR THE
PROPOSED LICENCE PERIOD OF 2006
AUGUST 01 TO 2011 OCTOBER 31
SITE & COMMUNITY AFFAIRS – RTO
COMMUNITY INVESTMENT
PROCEDURE
COMPETITION
Rev
0
Date
2006 Apr
0
2009 Mar
1
2009 Jun
PREVENTING CORRUPTION IN
INTERNATIONAL BUSINESS
1
2009 Jun
Process 514000, Improve Organizational Performance and Manage
Change
Number
Title / Description
514010 and 514020 - Safety Culture and Human Performance
Rev
Date
CW-514020-MAN-001
0
2007 Oct
145-514100-GDI-001 2010/09/30
Comment
SAFETY CULTURE & HUMAN
PERFORMANCE
Comment
21
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 22
Rev. 0
Number
CW-514020-PRO-504
Title / Description
OPERATIONAL DECISION-MAKING
Rev
1
Date
2008 Dec
CW-514020-OV-118
EVENT FREE TOOLS - OVERVIEW
1
2007 Sep
CW-514020-PRO-274
EVENT FREE TOOL - SELF CHECKING
1
2007 Sep
CW-514020-PRO-275
EVENT FREE TOOL - VERIFICATION
1
2007 Sep
CW-514020-PRO-276
EVENT FREE TOOL - CONSERVATIVE
DECISION-MAKING
EVENT FREE TOOLS - PRE-JOB
BRIEFING/POST-JOB REVIEW
EVENT FREE TOOL COMMUNICATION
EVENT FREE TOOL - PROCEDURE
USE AND ADHERENCE
EVENT FREE TOOL - SAFE
PRACTICES
EVENT FREE DAY RESET (EFDR)
1
2007 Sep
3
2009 Dec
2
2007 Dec
3
2008 Apr
1
2007 Sep
1
2010 Feb
RTO IMPROVEMENT PLAN VOYAGEUR PHASE II
514100 - Maintain and Improve Overall Management System
0
2010 Apr
CW-514100-PRO-108
2
2008 Apr
CW-514020-PRO-277
CW-514020-PRO-278
CW-514020-PRO-279
CW-514020-PRO-280
145-514020-PRO-001
145-514020-PLA-001
DELEGATION OF AUTHORITY
CW-514100-PRO-100
PROCEDURAL DOCUMENTS 3
CREATION AND MANAGEMENT
CW-514100-GL-100
PREPARING PROCEDURAL
3
DOCUMENTS
145-514100-PRO-002
ORGANIZATIONAL CHANGE
0
CONTROL PROCESS
514200 - Prescribe Quality Requirements and Improve Business Processes
2010 Jan
CW-514200-PRO-442
CW-514200-PRO-420
CW-514200-PRO-229
CW-514200-OV-110
CW-514200-PRO-178
CRL-514200-COP-001
145-514200-TOR-001
145-514100-GDI-001 2010/09/30
Comment
2008 Aug
2010 Apr
QUALITY ASSURANCE MANUALS
AND PLANS
DIRECTIVE TO STOP WORK
0
2009 Oct
0
2007 Jun
SELECTION OF QUALITY PROGRAM
REQUIREMENTS
COMPANY BUSINESS PROCESSES
3
2009 Sep
1
2007 Mar
DEVELOPING AND MANAGING
COMPANY BUSINESS PROCESSES
NUCLEAR PERFORMANCE
ASSURANCE REVIEW
IMPACT REVIEW BOARD TERMS OF
REFERENCE
0
2006 Jun
0
2008 Apr
0
2010 Apr
22
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 23
Rev. 0
Number
Title / Description
514300 - Ensure Compliance with Requirements
Rev
Date
CW-514300-PRO-392
6
2009 Nov
0
2007 Aug
CW-514300-PRO-506
IMPROVEMENT ACTION (IMPACT)
PROCESS
IMPROVEMENT ACTION (IMPACT)
MANAGEMENT REVIEW MEETING
(MRM) AND MANAGEMENT
SCREENING TEAM (MST) TERMS OF
REFERENCE
PREVENTIVE ACTION
0
2008 May
CW-514300-PRO-427
PROGRAM REVIEWS
1
2009 Jul
156-514300-PRO-001
NUCLEAR OVERSIGHT AUDITS
0
2010 Apr
CW-514300-PRO-228
QUALIFICATION OF QUALITY AND
ENVIRONMENTAL AUDITORS
SUPPLIER QUALITY PROGRAM
AUDITS
SELF ASSESSMENT
2
2009 Feb
0
2009 Sep
0
2010 Jan
ROOT AND APPARENT CAUSE
ASSESSMENT WITHIN RESEARCH
AND TECHNOLOGY OPERATIONS
514400 - Perform Independent Reviews of HSE
0
2010 Jun
CW-514411-TOR-133
0
2010 May
0
2006 Mar
0
2006 Mar
0
2006 Mar
4
1998 Sep
5
1998 Sep
CW-514300-TOR-122
CW-514300-OI-227-02
145-514300-OI-187-01
145-514300-OI-166-01
SAFETY REVIEW COMMITTEE
CW-514400-REQ-129
INDEPENDENT HSE REVIEW OF NEW
FACILITIES
CW-514400-REQ-130
INDEPENDENT HSE REVIEW OF
OPERATING FACILITIES
CW-514400-REQ-131
INDEPENDENT HSE REVIEW OF THE
DECOMMISSIONING OF BUILDINGS,
FACILITIES AND SITES
SRC-R-7
NUCLEAR CRITICALITY SAFETY
PANEL - TERMS OF REFERENCE
SRC-R-5
AECL REQUIREMENTS FOR NUCLEAR
CRITICALITY SAFETY
514500 - Conduct Internal Audits and Report on Findings
5.
[1]
[2]
Comment
Based on
CW-514300-PRO227
Based on
CW-514300-PRO187
Based on
CW-514300-PRO166
REFERENCES
145-514100-MAN-001, Management System Manual.
145-514100-016-000, Management System Contact and Responsibility List.
145-514100-GDI-001 2010/09/30
23
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 24
Rev. 0
Appendix A
Compliance Matrices
The tables in this Appendix identify the sections in the Management System Manual (MSM),
145-514100-MAN-001 [1], where the requirements are addressed. Note that processes are
described in Appendix B of the MSM, and the supporting documents for the processes are listed
in this document.
A.1
Cross Reference Table to CAN/CSA N286-05 Standard, Management
system requirements for nuclear power plants
N286-05
MSM
Section No. and Title
Section No. and Title
2 Management system
9
Governing Documentation
documents
3 Management statement of
2
Management Commitment
commitment
4 Management assessment of 10
Management, Assessment and Improvement
effectiveness
5 Management system - Generic requirements
5.1 The business is defined,
5
Organization Overview
planned and controlled
B.2
Process 502000, Define Vision, Strategy and Corporate
Plan
5.2 The organization is defined 7
Responsibilities and Organization
and understood
B.14.2 Process 514100, Maintain and Improve Overall
Management System
5.3 Personnel are competent at B.10.1 Process 510100, Manage Staffing
the work they do
B.10.2 Process 510200, Train and Develop Employees
5.4 Personnel know what is
B.10.1 Process 510100, Manage Staffing
expected of them
B.10.2 Process 510200, Train and Develop Employees
B.10.4 Process 510700, Manage Employee Communications
B.14.1 Process 514020, Human Performance
5.5 Work is planned
----Various
5.6 Experience is sought,
B.8.13 Process 508750, Provide Operating Experience
shared and used
Process 511000, Manage Information and Associated
5.7 Information is provided in
B.11
time to the people who
Technology
need it
5.8 The performance of work
----Various
is controlled
5.9 The preparation and
B.11.1 Process 511300, Manage Information Assets
distribution of documents
are controlled
145-514100-GDI-001 2010/09/30
24
Information Use
N286-05
Section No. and Title
5.10 Work is verified to confirm
that it is correct
5.11 Problems are identified and
resolved
5.12 Changes are controlled
5.13 Records are maintained
5.14 Assessments are performed
6
6.1
6.2
6.2.1
6.2.2
6.2.3
6.3
6.4
6.5
6.6
6.7
6.8
6.9
6.10
6.11
6.12
6.13
6.14
6.15
6.16
6.17
6.18
6.19
6.20
6.21
6.22
Specific requirements
Design
Safety analysis
General
Safety analysis control
Safety report
Safe operating envelope
Purchasing and material
management
Identification and labelling
of systems and components
Security
Construction and
installation
Commissioning
Turnover
Completion assurance
Operating the plant
Oral communications
Plant status control
Operator surveillance
Surveillance testing
Operating procedures
Emergency procedures
Infrequently preformed
operations
Maintenance
Calibration of measuring
and monitoring devices
Periodic inspection
System health monitoring
145-514100-GDI-001 2010/09/30
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145-514100-GDI-001 Page 25
Rev. 0
MSM
Section No. and Title
----B.8.13
----B.11.1
10.2
B.14.4
B.8.1
B.8.5
B.8.15
Various
Process 508750, Provide Operating Experience (ImpAct
process)
Various
Process 511300, Manage Information Assets
Assessments
Process 514300, Ensure Compliance with Requirements
Process 508120, Provide Design and Engineering
Process 508550, Provide Nuclear Criticality Safety
Control
Process 508770, Provide Safety Analysis and
Operational Safety Assessment
B.8.2
B.8.3
B.8.9
B.5.2
Process 505210, Perform Procurement and Materials
Management
Process 508200, Operate and Maintain Facilities and
Nuclear Laboratories
Process 508710, Provide Physical Security
Process 505240, Manage Construction / Installation
B.5.3
B.5.3
B.5.3
B.8.2
B.10.4
B.14.1
B.8.2
B.8.2
B.8.2
B.8.2
B.8.2
B.8.2
Process 505250, Manage Commissioning/Testing
Process 505250, Manage Commissioning/Testing
Process 505250, Manage Commissioning/Testing
Process 508220, Operate Facilities
Process 510700, Manage Employee Communications
Process 514020, Human Performance
Process 508220, Operate Facilities
Process 508220, Operate Facilities
Process 508220, Operate Facilities
Process 508220, Operate Facilities
Process 508220, Operate Facilities
Process 508220, Operate Facilities
B.8.3
B.8.3
Process 508230, Provide Maintenance
Process 508230, Provide Maintenance
B.8.3
B.8.3
Process 508230, Provide Maintenance
Process 508230, Provide Maintenance
B.5.1
25
Information Use
N286-05
Section No. and Title
6.23 Chemistry control
6.24 Radiation protection
6.25 Fire protection
6.26 Emergency preparedness
6.27 Workplace safety
6.28 Hazardous waste
management
6.29 Effluent control
6.30 Decommissioning
Annexes
Supplementary
A
requirements for design
Supplementary
B
requirements for
purchasing and material
management
Supplementary
C
requirements for
construction and
installation
Supplementary
D
requirements for
commissioning
Supplementary
E
requirements for
decommissioning
Supplementary
F
requirements for
verification of work
145-514100-GDI-001 2010/09/30
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145-514100-GDI-001 Page 26
Rev. 0
B.8.2
B.8.12
B.8.10
B.8.11
B.10.3
B.8.8
MSM
Section No. and Title
Process 508220, Operate Facilities
Process 508740, Provide Radiation Protection
Process 508720, Provide Fire Protection
Process 508730, Provide Emergency Preparedness
Process 510400, Ensure Employee Safety and Well
being
508600, Manage Wastes
B.8.4
Process 509200, Provide Environmental Protection
Program
Process 508300, Decommission Sites and Facilities
B.8.1
Process 508120, Provide Design and Engineering
B.5.1
Process 505210, Perform Procurement and Materials
Management
B.5.2
Process 505240, Manage Construction / Installation
B.5.3
Process 505250 , Manage Commissioning/Testing
B.8.4
Process 508300, Decommission Sites and Facilities
B.8.2
B.8.3
Process 508200, Operate and Maintain Facilities and
Nuclear Laboratories
B.9.1
26
Information Use
A.2
1
1.1
1.2
2
3
4
4.1
4.2
5
5.1
5.2
5.3
5.4
5.5
5.6
6
6.1
6.2
AECL - OFFICIAL USE ONLY
145-514100-GDI-001 Page 27
Rev. 0
Cross Reference Table to ISO-9001:2008 Standard, Quality management
systems – Requirements
ISO-9001:2008
Section No. and Title
Scope
General
Applications
Normative References
Terms and Definitions
Quality Management System
General Requirements
Documentation Requirements
4.2.1 General
4.2.2 Quality manual
4.2.3 Control of Documents
4.2.4 Control of Records
Management Responsibility
Management Commitment
Customer Focus
Quality Policy
Planning
5.4.1 Quality Objectives
5.4.2 Quality Management
System Planning
Responsibility, Authority, and
Communication
5.5.1 Responsibility and
Authority
5.5.2 Management
Representative
5.5.3 Internal
Communications
Management Review
5.6.1 General
5.6.2 Review Input
5.6.3 Review Output
Resource Management
Provision of Resources
Human Resources
6.2.1 General
6.2.2 Competence,
145-514100-GDI-001 2010/09/30
MSM
Section No. and Title
1.1
Scope
1.2
1.3
Purpose
Definitions
1.1
Scope
1.1
B.14.2
Scope
Process 514100, Maintain and Improve Overall
Management System
Process 511300, Manage Information Assets
Process 511300, Manage Information Assets
B.11.1
B.11.1
2
8
B.2
Management Commitment
Business Process - processes 01 to 06
Policy 00-007 Quality
Process 502000, Define Vision, Strategy and Corporate
Plan
B.14.2
Process 514100, Maintain and Improve Overall
Management System
B.10.4
Process 510700, Manage Employee Communications
10
B.14.4
Measurement, Assessment And Improvement
Process 514300, Ensure Compliance with Requirements
B.10
Process 510000, Develop and Manage Human
Resources
27
Information Use
6.3
6.4
7
7.1
7.2
7.3
7.4
7.5
ISO-9001:2008
Section No. and Title
Awareness and
Training
Infrastructure
Work Environment
Product Realization
Planning of Product
Realization
Customer related processes
7.2.1 Determination of
requirements related to
the product
7.2.2. Review of
requirements related to
the product
7.2.3 Customer
communication
Design and development
7.3.1 Design and
Development Planning
7.3.2 Design and
development inputs
7.3.3 Design and
development outputs
7.3.4 Design and
development review
7.3.5 Design and
development
verification
7.3.6 Design and
development
validation
7.3.7 Control of design and
development changes
Purchasing
7.4.1 Purchasing Process
7.4.2 Purchasing
Information
7.4.3 Verification of
Purchased Products
Production and Service
provision
7.5.1 Control of Production
and service provision
7.5.2 Validation of
145-514100-GDI-001 2010/09/30
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145-514100-GDI-001 Page 28
Rev. 0
MSM
Section No. and Title
B.3
Process 503000, Develop and Design Products, Services
or Projects
B.6
Process 506000, Provide After sales Customer Support
B.3
Process 503000, Develop and Design Products, Services
or Projects,
and
B.8.1
Process 508120, Provide Design and Engineering
B.5.1
Process 505210, Perform Procurement and Materials
Management
B.5
Process 505000, Produce, Build, Modify and Deliver
Products, Services or Projects
28
Information Use
7.6
8
8.1
8.2
8.3
8.4
8.5
ISO-9001:2008
Section No. and Title
processes for
Production and
Service Provision
7.5.3 Identification and
Traceability
7.5.4 Customer Property
7.5.5. Preservation of
product
Control of Monitoring and
Measuring Devices
Measurements, Analysis and
Improvement
General
Monitoring and Measurement
8.2.1 Customer Satisfaction
8.2.2 Internal Audits
8.2.3 Monitoring and
Measurement of
Processes
8.2.4 Monitoring and
Measurement of
Products
Control of Nonconforming
Product
Analysis of Data
Improvement
8.5.1 Continual
Improvement
8.5.2 Corrective Action
8.5.3 Preventive Action
145-514100-GDI-001 2010/09/30
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145-514100-GDI-001 Page 29
Rev. 0
MSM
Section No. and Title
B.8.3
Process 508230, Provide Maintenance
B.14
Process 514000, Improve Organizational Performance
and Manage Change
B.8.13
Process 508750, Provide Operating Experience
B.8.13
B.14
Process 508750, Provide Operating Experience
Process 514000, Improve Organizational Performance
and Manage Change
29
Revision History
Liste de révisions
AECL - OFFICIAL USE ONLY
À USAGE EXCLUSIF - EACL
Page 1 of / de 1
CW-511300-FM-168 Rev. 0
Ref. Procedure CW-511300-PRO-161
Document No. / Numéro de document:
145
514100
GDI
001
Doc. Collection ID
ID de la collection de doc.
SI
Répertoire du sujet
Section
Serial No.
o
N de série
Document Details / Détails sur le document
Total no. of pages
Nbre total de pages
Title
Titre
MANAGEMENT SYSTEM GOVERNING DOCUMENTATION INDEX
32
For Release Information, refer to the Document Transmittal Sheet accompanying this document. / Pour des renseignements portant sur la diffusion,
consultez la feuille de transmission de documents ci-jointe.
Revision History / Liste de révisions
Revision / Révision
Date
(yyyy/mm/dd)
Details of Rev. / Détails de la rév.
Prepared/Revised by
Rédigé/Examiné par
Reviewed by
Examiné par
Approved by
Approuvé par
D1
2010/07/30
Issued for “Review and Comment”.
R.G. Lavoie
0
2010/09/30
Issued as “Approved for Use”.
R.G. Lavoie
H. Andersen (for
B. Sanderson)
D. Lemire
J.L. Grenier
T. Arthur
S. Lawton
C. Van Drunen
S. Beauchamp
K. Smith
C. Clavel
C. Van Drunen
R. Lesco
No./N
dsfpdfscs
o
145-514100-GDI-001 2010/09/30
Governing Documentation Index
SITES AND FACILITIES
GOVERNING DOCUMENTATION
INDEX
145-514100-GDI-002
Revision 0
Prepared by
Rédigé par
Lavoie Robert - Management
System Specialist
Reviewed by
Vérifié par
Van Drunen Christina - Manager,
Engineering Programs &
Approved by Standards
Approuvé par
Cox David S - Director - Safety Lesco Randy - GM, ENG. &
Engineering & Licensing
CHIEF NUC. ENGINEER
2010/09/23
2010/09/23
AECL - OFFICIAL
USE ONLY
À L'USAGE EXCLUSIF
D'EACL
Atomic Energy of
Canada Limited
Énergie Atomique du
Canada Limitée
2251 Speakman Drive
Mississauga, Ontario
Canada L5K 1B2
2251 rue Speakman
Mississauga (Ontario)
Canada L5K 1B2
AECL - OFFICIAL USE ONLY
Information Use
Governing Documentation Index
À USAGE EXCLUSIF - EACL
145-514100-GDI-002 Page i
Rev. 0
Always refer to myAECL for latest and OFFICIAL version.
()
Utilisation de
l'information
SITES AND FACILITIES
GOVERNING
DOCUMENTATION INDEX
TABLE
OF CONTENTS
SECTION
SECTION
1.
1.
2.
2.
3.
3.
4.
4.
4.1
4.1.1
4.1
4.1.2
4.1.1
4.1.3
4.1.2
4.1.4
4.1.3
4.1.5
4.1.4
4.1.6
4.1.5
4.2
4.1.6
4.2.1
4.1.7
4.2.2
4.2
4.2.3
4.2.1
4.2.4
4.2.2
4.2.5
4.2.3
4.2.4
5.
4.2.5
PAGE
TABLE OF CONTENTS
PAGE
SCOPE ................................................................................................................1
SCOPE ................................................................................................................1
PURPOSE............................................................................................................1
PURPOSE............................................................................................................1
DEFINITIONS ....................................................................................................1
DEFINITIONS ....................................................................................................1
INDEX ................................................................................................................1
INDEX
................................................................................................................1
Chalk River
Laboratories .....................................................................................2
Class
I
Nuclear
Facilities
................................................................................2
Chalk River Laboratories
.....................................................................................2
Class
NuclearFacilities................................................................................2
Facilities...............................................................................6
Class II
I Nuclear
Class
B
Radioisotope
Laboratories .................................................................7
Class II Nuclear Facilities...............................................................................6
Class
Class C
A Radioisotope
Radioisotope Laboratories
Laboratories ...............................................................10
.................................................................7
Permanently
Shutdown
Facilities..................................................................14
Class B Radioisotope Laboratories .................................................................7
Other
Facilities.............................................................................................15
Class C
Radioisotope Laboratories ...............................................................10
Whiteshell
Laboratories
.....................................................................................15
Permanently Shutdown
Facilities..................................................................14
Nuclear
Facilities
.........................................................................................15
Other Facilities.............................................................................................15
Class BLaboratories
Radioisotope.....................................................................................15
Laboratories ...............................................................17
Whiteshell
Class
C
Radioisotope
Laboratories ...............................................................17
Nuclear Facilities .........................................................................................15
Other
Facilities
and Laboratories
..................................................................18
Class B
Radioisotope
Laboratories
...............................................................17
Permanently
Shutdown
Facilities..................................................................18
Class C Radioisotope Laboratories ...............................................................17
Permanently Shutdown Facilities..................................................................18
REFERENCES
..................................................................................................21
Other Facilities
and Laboratories ..................................................................19
5.
REFERENCES ..................................................................................................21
APPENDICES
No table of contents entries found.
Prepared by:
Date:
Reviewed by:
Date:
Approved by:
Date:
R.G. Lavoie
2010/09/23
C. Van Drunen
2010/09/23
R. Lesco
2010/09/23
145-514100-GDI-002 2010/09/23
 Atomic Energy of Canada Limited
AECL - OFFICIAL USE ONLY
Information Use
Governing Documentation Index
À USAGE EXCLUSIF - EACL
Utilisation de
l'information
145-514100-GDI-002 Page 1
Rev. 0
Always refer to myAECL for latest and OFFICIAL version.
()
TABLE OF CONTENTS
SITES AND FACILITIES GOVERNING DOCUMENTATION INDEX
SECTION
PAGE
1.
SCOPE
1.
SCOPE ................................................................................................................1
This document provides an index to governing documents for sites, facilities and laboratories
managed and operated
by Research and Technology Operations (RTO) in support of the
2.
PURPOSE............................................................................................................1
Management System [1].
3.
....................................................................................................1
This document DEFINITIONS
consists of the main
governing documents for individual facilities and
laboratories at CRL
and................................................................................................................1
WL. Sites and facilities at other locations will be added in a future
4.
INDEX
revision.
4.1
River
Laboratories
For an index toChalk
external
requirements
and.....................................................................................2
company policies, manuals and procedures issued for
4.1.1
Class I Nuclear Facilities ................................................................................2
general use refer to the Management System Governing Documentation Index (GDI) [2].
4.1.2
Class II Nuclear Facilities...............................................................................6
For
the
latest
revision
of B
documents
listedLaboratories
in the Index.................................................................7
section and a more comprehensive list of
4.1.3
Class
Radioisotope
governing
documents,
refer
to
TRAK
or
the
Procedural
Applet on myAECL.
4.1.4
Class C Radioisotope Laboratories ...............................................................10
4.1.5
Permanently
Shutdown
Facilities..................................................................14
For the managers responsible
and/or
contacts
of individual facilities and laboratories, refer to the
4.1.6
Other Facilities.............................................................................................15
Contact and Responsibility
List [2].
4.2
Whiteshell Laboratories .....................................................................................15
Comments or out-of-date documents listed in here should be communicated to the Management
4.2.1
Nuclear Facilities .........................................................................................15
System Specialist, who maintains this document.
4.2.2
Class B Radioisotope Laboratories ...............................................................17
2.
PURPOSE
4.2.3
Class C Radioisotope Laboratories ...............................................................17
4.2.4
Otherthat
Facilities
and Laboratories
This document ensures
management
responsible..................................................................18
for sites, facilities and laboratories in RTO
4.2.5
Permanently
Shutdown
Facilities..................................................................18
have a list of governing documents.
3.
5.
DEFINITIONS
REFERENCES
..................................................................................................21
For terms and abbreviations refer to the individual documents listed in the Index, or the
Acronyms, Abbreviations, and Definitions of Terms web site on myAECL
APPENDICES
(http://sps39/terms_definitions/terms.asp).
4. table of contents
INDEX
No
entries found.
The section covers the index to documents for:


Facilities and laboratories at CRL, in Section 4.1; and
Facilities and laboratories at WL, in Section 4.2.
145-514100-GDI-002 2010/09/23
Information Use
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 2
Rev. 0
4.1
Chalk River Laboratories
4.1.1
Class I Nuclear Facilities
Facility
NRU Reactor
Nuclear Fuel Fabrication
Facility (NFFF), Building
405
Nuclear Fuel Fabrication
Facility (NFFF), Buildings
429A & 429B
145-514100-GDI-002 2010/09/23
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Operations
NRU-00583-FA-001, FACILITY AUTHORIZATION FOR THE
3
2009 Jun
OPERATION OF THE NRU REACTOR AT THE CHALK RIVER
LABORATORIES
NRU-508200-GDI-001, NRU FACILITY GOVERNING
0
2010 Aug
DOCUMENTATION INDEX
The NRU Reactor comprises several buildings; the main one is Building 150, which houses the reactor, rod bays, and experimental
facilities. NRU can be used for a wide variety of irradiations, including: fuels and materials testing, fuel testing under accident
conditions, testing of fusion blanket materials, small-sample irradiations, experiments in neutron scattering, and isotope production.
The reactor operates at power levels up to 130 megawatts thermal and it is heavy water moderated, light water reflected, and heavy
water cooled. The reactor is designed to be fuelled at power. The core consists of an aluminium cylinder approximately 3.7 m in
diameter and 3.5 m high. It is made up of 227 vertical lattice sites arranged in a hexagonal array with a pitch of 19.7 cm. Control
rods and enriched uranium fuel rods occupy about half of the lattice sites; most of the remaining sites are used for low
temperature/low pressure experiments and irradiations. Two-high pressure/high temperature loops supply coolant to three reactor test
sections. A number of beam hole facilities are also available.
Operations
AECL-FA-19, FACILITY AUTHORIZATION FOR THE OPERATION 3
1998 Sep
OF THE NUCLEAR FUEL FABRICATION FACILITY BUILDING
405 AT THE CHALK RIVER LABORATORIES
NFFF-01900-COP-001, NFFF CONDUCT OF OPERATIONS
11
2008 Jun
MANUAL - QUALITY ASSURANCE PLAN
The NFFF, Building 405 produces nuclear fuel products for internal and external customers.
Operations
AECL-FA-02, FACILITY AUTHORIZATION FOR THE OPERATION 3
1998 Sep
OF THE NUCLEAR FUEL FABRICATION BUILDING 429A AND
429B FACILITY AT THE CHALK RIVER LABORATORIES.
NFFF-01900-COP-001, NFFF CONDUCT OF OPERATIONS
11
2008 Jun
MANUAL - QUALITY ASSURANCE PLAN
NFFF Building 429A is used to receive, store, and process low enriched uranium based cores and to manufacture Molybdenum-99
(Mo-99) targets from uranium-aluminum based billets. Building 429B is used to cast uranium-aluminum based billets.
2
Information Use
Facility
Recycle Fuel Fabrication
Laboratories (RFFL)
Heavy Water Upgrading
Plant
ZED-2 Reactor
Universal Cells
145-514100-GDI-002 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 3
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Research &
RFFL-00583-FA-001, FACILITY AUTHORIZATION FOR THE
5
2010 Feb
OPERATION OF THE RECYCLE FUEL FABRICATION
Development
LABORATORIES AT THE CHALK RIVER LABORATORIES
RFFL-01900-COP-001, RECYCLE FUEL FABRICATION
10
2010 Jul
LABORATORIES CONDUCT OF OPERATIONS MANUAL
The RFFL, located in the south end of Building 375, consists of several laboratories. The main fuel fabrication laboratory houses
three interconnected lines of negative-pressure ventilated gloveboxes and fumehoods, to allow the fabrication of sintered pellets of
mixed-oxide fuel, which are then clad and sealed into CANDU type fuel elements.
Operations
AECL-FA-04, FACILITY AUTHORIZATION FOR THE OPERATION 3
1998 Sep
OF THE HEAVY-WATER UPGRADING PLANT AT THE CHALK
RIVER LABORATORIES.
NFO-01900-COP-001 (HWUP-SSS-2)
Upgrading operations in the Heavy Water Upgrading Plant ceased permanently in 1998 August. The facility ceased to be occupied
on a regular basis; it was placed in a Safe Shutdown State. It is being monitored by security and radiation protection personnel, or by
facility supervision on a daily basis. Periodic drum shipments of downgraded heavy water are made from the shipping dock area.
Research &
ZED2-00583-FA-001, FACILITY AUTHORIZATION FOR THE
5
2010 Jan
OPERATION OF THE ZED-2 REACTOR AT THE CHALK RIVER
Development
LABORATORIES
ZED2-01900-COP-001, ZED-2 CONDUCT OF OPERATIONS
10
2010 Jul
The ZED-2 Reactor, located in Building 145, is a versatile, heavy-water moderated, zero energy (less than 200 watts) critical facility
that can be used for a variety of experiments. It is used mainly for reactor physics measurements on various fuel types with several
coolants over a range of lattice pitches. The reactor can also be used for measurements on mockups of reactivity control devices and
fuel channels of both power and research reactors. A heavy-water region in which neutrons are well thermalized can be assembled
and used for neutron detector calibration and thermal neutron cross section measurement.
Operations
AECL-FA-06, FACILITY AUTHORIZATION FOR THE OPERATION 2
1998 Sep
OF THE BUILDING 234 UNIVERSAL CELLS AT THE CHALK
RIVER LABORATORIES.
NFO-01900-COP-001, NUCLEAR FACILITIES OPERATION
5
2009 Dec
CONDUCT OF OPERATIONS MANUAL
The Universal Cells are located in Building 234 and contains three cells. Cell 1 is used for the processing of Co 60 from the NRU
Reactor and the examination of highly radioactive materials. Cells 2 and 3 are used for the examination of irradiated fuel and
metallurgical samples and some approved experiments.
3
Information Use
Facility
Molybdenum-99
Production Facility
Tritium Laboratory
145-514100-GDI-002 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 4
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Operations
MPF-00583-FA-001, FACILITY AUTHORIZATION FOR THE
5
2010 Feb
OPERATION OF THE MOLYBDENUM-99 PRODUCTION
FACILITY AT THE CHALK RIVER LABORATORIES
MPF-508200-GDI-001, MO-99 PRODUCTION FACILITY
1
2010 Jan
GOVERNING DOCUMENTATION INDEX
The Molybdenum-99 (Mo-99) Production Facility (MPF) is comprised of a portion of Buildings 225, 225A, 229, 206 and 203. The
Mo-99 Cell is located in Building 225, and the off-gas delay system components are housed in Building 225A. The Fissile Solution
Storage Tank and associated equipment are located in Building 229. Building 206 is the Mo-99 Cell ventilation fan house and
Building 203 is the 61 m stack.
In the Mo-99 production process, irradiated uranium targets are dissolved in nitric acid and the Mo-99 is recovered from the
fission-product solution. Xenon-133 is recovered as a by-product of this process. The fission-product solution is a waste product that
is transferred to Fissile Solution Storage Tank for storage as liquid waste, or mixed with cement and stored as solid waste in tile holes
in Waste Management Area “B”.
Research &
AECL-FA-15, FACILITY AUTHORIZATION FOR THE OPERATION 1
1999 May
OF THE TRITIUM FACILITY AT THE CHALK RIVER
Development
LABORATORIES
TF-01900-COP-001, TRITIUM FACILITY CONDUCT OF
2
2005 May
OPERATION MANUAL
TF-102300-RLP-001, CLASS A RADIOISOTOPE LABORATORY
1
2009 Jun
PROTOCOL FOR THE TRITIUM FACILITY - BUILDING 250, FIRST
FLOOR ROOM 45, SECOND FLOOR ROOMS 242, 244, 248, 250
AND 250A
The Tritium Laboratory (also referred to as the Tritium Facility) is a Class A Radioisotope Laboratory located in Rooms 242, 244,
245, 248, 250 and 250A in Building 250. The laboratory is used almost exclusively for work with tritium in various chemical forms;
the most common are tritium gas, usually stored as a metal tritide, and tritiated water. A key component of the laboratory is the
inert-atmosphere, positive-pressure glovebox located in Room 245, which is used for handling very large quantities of elemental
tritium.
The Tritium Laboratory serves as the primary facility for conducting research and development activities associated with heavy-water
management and tritium control in CANDU reactors. In addition, tritium is dispensed under contract to Ontario Power Generation
for their customers.
4
Information Use
Facility
Waste Treatment Centre
and Associated Facilities
Fuels and Materials Cells
Waste Management Areas
Combined Electrolysis
Catalytic Exchange
Upgrade and Detritiation
Test Facility
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145-514100-GDI-002 Page 5
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
D&WM
AECL-FA-16, FACILITY AUTHORIZATION FOR THE OPERATION 5
1999 Nov
OF THE WASTE TREATMENT CENTRE AND ASSOCIATED
FACILITIES AT THE CHALK RIVER LABORATORIES.
WMO-01900-COP-001, CONDUCT OF OPERATIONS WASTE
8
2009 Apr
MANAGEMENT OPERATIONS TABLE OF CONTENTS
The Waste Treatment Centre (WTC) is located in Building 570 and receives radioactive liquids and solids from Controlled Area 2 of
CRL. The WTC also manages liquids containing high levels of radioactivity stored in stainless steel tanks.
Operations
AECL-FA-17, FACILITY AUTHORIZATION FOR THE OPERATION 2
1998 Sep
OF THE FUELS AND MATERIALS CELLS AT THE CHALK RIVER
LABORATORIES.
The Fuels & Materials Cells facility, located in Building 375, is used primarily for the destructive examination or thermal mechanical
testing of irradiated fuels and materials. It comprises of numerous cells, remote optical microscopes, an in-cell storage block, a
shielded Scanning Electron Microscope, and several fume hoods. Also included in the facility are a horizontal storage facility for the
temporary storage of irradiated material (particularly fissile) a vertical in-ground storage facility limited to non-fissile material, a
storage block for temporary storage of low-level irradiated non-fissile material, an active waste drainage system, a ventilation system,
a shipping/receiving area, manipulator, and active equipment storage rooms.
D&WM
WMA-01320-FA-001, FACILITY AUTHORIZATION FOR THE
3
2009 Feb
OPERATION OF THE WASTE MANAGEMENT AREAS AT THE
CHALK RIVER LABORATORIES
WMO-01900-COP-001, CONDUCT OF OPERATIONS WASTE
8
2009 Apr
MANAGEMENT OPERATIONS TABLE OF CONTENTS
The Waste Management Areas (WMAs) comprise a number of fenced-in areas used for storage of a variety of solid radioactive
wastes ranging in activity from very low levels up to that of irradiated nuclear fuel. These wastes originate from the operation of
CRL and from off-site, such as isotope manufacturers, hospitals, and universities. Some areas of the WMAs continue to accept wastes
(WMAs “B”, “C”, “D”, and “H”), others are no longer operational (WMAs “A”, “E”, and “F”), and WMA “G” is in the process of
being reactivated.
Research &
AECL-FA-20, FACILITY AUTHORIZATION FOR THE OPERATION 5
2000 Dec
OF THE COMBINED ELECTROLYSIS CATALYTIC EXCHANGE
Development
UPGRADE AND DETRITIATION (CECEUD) TEST FACILITY AT
THE CHALK RIVER LABORATORIES
CECEUD-01900-COP-001, CECEUD FACILITY CONDUCT OF
1
2005 Feb
OPERATIONS MANUAL
5
Information Use
Facility
4.1.2
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
The Combined Electrolysis Catalytic & Exchange Upgrading/Detritiation (CECEUD) Test Facility is located in Building 215. The
facility consists of a process building and a service building, joined by a link building, and includes the combined electrolysis and
catalytic exchange process and associated equipment and services. Some of the original, unused Tritium Extraction Plant equipment
is incorporated into the combined electrolysis and catalytic exchange process. The heavy water upgrading and detritiation processes
involve the electrolytic separation of water into oxygen and the hydrogen isotopes, and the catalytic transfer of hydrogen isotopes
between heavy-water feedstock and the deuterium/tritium gas produced by the electrolytic cell.
Class II Nuclear Facilities
Facility
Health Physics Neutron
Generator
Gamma Beam 150C
Irradiation Facility
Gamma Beam Irradiator
Model GC60
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145-514100-GDI-002 Page 6
Rev. 0
Owner /
Description
Research &
Development
Applicable Document(s)
Number / Title
HPNG-00583-FA-001, FACILITY AUTHORIZATION FOR THE
OPERATION OF THE HEALTH PHYSICS NEUTRON GENERATOR
AT THE CHALK RIVER LABORATORIES
Rev
5
Date
2010 Feb
The Health Physics Neutron Generator is located in Building 513. It is a high voltage accelerator, designed to accelerate 1 mA of
deuterium ions through a maximum potential drop of 150 kV. It produces nominal 14 MeV or 2.7 MeV neutrons, by the 2H(t,n) 4He
or 2H(d,n)3He reactions, when the deuteron beam strikes a target containing either tritium or deuterium. It was put into service in
1961. The designed maximum outputs are about 5 x 1010 14 MeV neutrons and 5 x 108 2.7 MeV neutrons.
Research &
GBF-00583-FA-001, FACILITY AUTHORIZATION FOR THE
2
2009 Aug
OPERATION OF THE GAMMABEAM 150C FACILITY AT THE
Development
CHALK RIVER LABORATORIES
The Gamma Beam 150C (GB 150C), manufactured by Nordion International Inc., is a gamma irradiator used for the irradiating live
biological (animals) specimens and cell cultures for research. GB 150C is located in Room O103 and its controls in Room O102 of
Building 524.
Research &
203-00583-FA-001, FACILITY AUTHORIZATION FOR THE
3
2009 Aug
OPERATION OF THE GC60 GAMMA IRRADIATOR AT THE
Development
CHALK RIVER LABORATORIES
The GC60 is a gamma beam irradiator used for the calibration of gamma survey meters. It is also used for exposure of dosimeters and
irradiating dosimetric material. The GC60 irradiator is located in Room 175 and its controls are in Room 195 of Building 513.
6
Information Use
4.1.3
Class A Radioisotope Laboratories
Laboratory
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Research &
TF-102300-RLP-001, LABORATORY PROTOCOL FOR THE
1
2009 Jun
TRITIUM FACILITY BUILDING 250, FIRST FLOOR ROOM 45,
Development
SECOND FLOOR ROOMS 242, 244, 248, 250 AND 250A
Bldg. 250, Rooms 242, 244, 245, 248, 250, 250A – The laboratories are used for conducting R&D activities associated with heavywater management and tritium control in the CANDU reactor environment. In addition, tritium is dispensed under contract to Ontario
Power Generation for their customers.
Tritium Facility
4.1.4
Class B Radioisotope Laboratories
Laboratory
Molten-Fuel-Moderator-In
teraction Laboratory
Radiation Growth
Laboratory
Control/Loop
Laboratories
Iodine Preparation
Laboratory
145-514100-GDI-002 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 7
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Research &
B137-108460-RLP-001,
1
2004 May
MOLTEN-FUEL-MODERATOR-INTERACTION LABORATORY,
Development
BLD. 137
Bldg. 137, Rooms 117 and 119 – The laboratory is used for experimentation to determine the dominant mechanism of interaction
between ejected molten fuel and the moderator under CANDU accident conditions.
Research &
NRU-108360-RLP-001, THE IRRADIATION CREEP AND GROWTH 0
2009 Jun
Development
LABORATORY, BUILDING 150, ROOM 201-B, 2ND BASEMENT
Bldg. 150, Room 201B – The laboratory is used for assembly and disassembly of irradiation growth holders and open monitors,
examination of creep specimens and creep insert accessories.
Operations
NRU-157901-RLP-001, CLASS B - RLP FOR CONTROL/LOOP
0
2006 May
LABORATORIES, B150, ROOMS 219, 322 & 326.
Bldg. 150, Rooms 219, 322 and 326 – The laboratories are used for assay of samples from NRU and other test loops for routine
analytical chemistry requirements.
Programs &
B226-108344-RLP-002, CLASS B IODINE PREPARATION
0
2009 Mar
Nuclear
LABORATORY, B226, MAIN FLOOR, ROOM 113
Oversight
Bldg. 226, Room 113 – The Iodine Preparation Laboratory is used for receiving and unpacking of radioactive shipments of
Iodine-131, preparing I-131 (as NaI) challenge aerosols which are used to test charcoal filters in-situ, and assembling/disassembling
monitoring sample cartridges.
7
Information Use
Laboratory
TIMS Sample Preparation
Laboratory
Gammacell Laboratory
Active Wet Chemistry
Laboratory
Chromatography
Laboratory
Containment Chemistry
Laboratory
ICP-MS Laboratory
145-514100-GDI-002 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 8
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Research &
RLP-ACB-10, CLASS C RLP FOR THE TIMS SAMPLE
0
1998 Aug
PREPARATION LABORATORY, BUILDING 107, ROOM 56,
Development
FLOOR 1
Bldg. 320, Room 212 – TIMS Sample Preparation Laboratory (Replaces work done in Class C Lab in B107, Rm 56, 62 - Physical &
General Chemistry Laboratory).
Note – B320-108360-RLP-003, Class B Radioisotope Laboratory for TIMS Sample Preparation Laboratory, Building 320, Room 212,
Floor 2, is in review and comment.
Research &
B320-108344-RLP-001, CLASS B RADIOISOTOPE LABORATORY
1
2009 Jan
PROTOCOL FOR THE CONTAINMENT CHEMISTRY
Development
LABORATORY B320 ROOM 333 AND IODINE-131 TRACER
STUDIES IN THE GAMMACELL LABORATORY B320 ROOM 334
Bldg. 320, Room 334 – The laboratory is used for irradiation of solutions and solids to determine the effects of radiation on fission
product behaviour.
Research &
B320-108360-RLP-005, CLASS B FOR ACTIVE WET CHEMISTRY
0
2008 Sep
Development
LABORATORY, BUILDING 320, FLOOR 3, ROOM 324
Bldg. 320, Room 324 – The laboratory is used for handling of radioactive and inactive samples using general wet chemistry
procedures.
Research &
B320-108360-RLP-002, CLASS B RADIOISOTOPE LABORATORY
0
2008 Nov
PROTOCOL FOR THE CHROMATOGRAPHY LABORATORY;
Development
BUILDING 320, FLOOR 3, ROOMS 317, 318/319 AND 320
Bldg. 320, Rooms 317, 318, 319 and 320 – The laboratories are used for analysis of radioactive liquid samples using chromatographic
techniques.
Research &
B320-108344-RLP-001, CLASS B RADIOISOTOPE LABORATORY
1
2009 Jan
PROTOCOL FOR THE CONTAINMENT CHEMISTRY
Development
LABORATORY B320 ROOM 333 AND IODINE-131 TRACER
STUDIES IN THE GAMMACELL LABORATORY B320 ROOM 334
Bldg. 320, Room 333 – The laboratory is used for studies on the behaviour of radioiodines in the reactor environment.
Research &
B330-108360-RLP-005, CLASS B THE ICP-MS LABORATORY;
0
2008 Nov
Development
BUILDING 330, FLOOR 3, ROOMS 316 AND 318
Bldg. 330, Rooms 316 and 318 – The laboratories are used for development of chemical and radiochemical procedures for sample
analysis using the Inductively Coupled Plasma – Mass Spectrometer (ICP-MS).
8
Information Use
Laboratory
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 9
Rev. 0
Neutron Activation
Analysis (NAA) and
Radiochemistry
Laboratory
Applicable Document(s)
Number / Title
Rev
Date
Research &
B330-108360-RLP-002, CLASS B RADIOCHEMICAL ANALYSIS
1
2010 Sept
Development
LABORATORY; BUILDING 330, FLOOR 3, ROOM 325 AND 328
Bldg. 330, Rooms 325 and 328 – The laboratories are used for development of radiochemical procedures for sample preparation and
analysis, and for preparation of Radionuclide Metrology Standard Sources.
Research &
B330-108360-RLP-001, RADIOCHEMICAL ANALYSIS
0
2008 Nov
Development
LABORATORY, BUILDING 330,FLOOR 3, ROOM 326
Bldg. 330, Room 326 – The laboratory is used for development and application of chemical and radiochemical methods and
procedures for sample preparation and analysis.
Research &
B330-108360-RLP-004, CLASS B RADIOISOTOPE LABORATORY
0
2009 Jul
PROTOCOL FOR NAA LABORATORY BUILDING 330, ROOM
Development
321, FLOOR 3
Bldg. 330, Room 321 – The laboratory is used for Routine sample preparation and radiochemical analysis of samples.
Hydrogen and Deuterium
Analysis Laboratories
Research &
Development
Radiochemistry
Laboratories
Radiochemistry
Laboratory
SIMS and Radioactive
Specimen Preparation
Laboratories
Coulometric Titration
Laboratory
Advanced CANDU Fuel
Development Laboratories
145-514100-GDI-002 2010/09/23
Owner /
Description
B330-108360-RLP-006, CLASS B THE HYDROGEN AND
0
2009 May
DEUTERIUM ANALYSIS LABORATORIES; BUILDING 330,
FLOOR 3, ROOM 326A AND 327
Bldg. 330, Rooms 326A and 327 – The laboratories are used for analysis of hydrogen and deuterium in zirconium alloy samples by
Hot Vacuum Extraction Mass Spectrometry.
Research &
B375-108730-RLP-002, CLASS B FOR THE SIMS, SEM AND
1
2008 Sep
RADIOACTIVE SPECIMEN PREPARATION LABORATORIES;
Development
BUILDING 375, FLOOR 1, ROOMS 157, 159 & 161
Bldg. 375, Rooms 153, 157, 157A, 159 and 161 – The laboratories are used for surface and near-surface characterization of solid
materials by Secondary Ion Mass Spectrometry (SIMS).
Research &
B375-108360-RLP-001, CLASS B RADIOISOTOPE LABORATORY
0
2009 Feb
PROTOCOL FOR COULOMETRIC TITRATION LABORATORY,
Development
BUILDING 375, ROOM 257
Bldg. 375, Rooms 253, 257 and 257A – The laboratories are used for coulometric titration of irradiated and non-irradiated UO2
samples.
Research &
B375-124200-RLP-002, CLASS B RADIOISOTOPE LABORATORY
1
2006 Jan
Development
PROTOCOL CERAMICS LABORATORY, BLD. 375, LAB 43
Bldg. 375, Room 43 – The laboratory is used for experimental powder and pellet fuel fabrication.
9
Information Use
Laboratory
Owner /
Description
Research Reactor Fuel
Development Laboratories
Imaging-XPS Laboratory
Advanced CANDU Fuel
Development
Laboratories, B375 Rm
258-262
Waste Processing
Technology Development
Laboratory
4.1.5
Laboratory
H3 Loop
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AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 10
Rev. 0
Applicable Document(s)
Number / Title
Rev
Date
Research &
B375-124200-RLP-003, RADIOISOTOPE LABORATORY
0
2006 Jul
PROTOCOL FOR RESEARCH REACTOR FUEL DEVELOPMENT
Development
LABORATORIES
Bldg. 375, Rooms 38, 40, 50 and 162 – The laboratories are used for powder metallurgy process development.
Research &
Development
B375-108730-RLP-001, CLASS B RADIOISOTOPE LABORATORY
0
2004 Oct
PROTOCOL FOR THE IMAGING-XPS LABORATORY:
BUILDING 375, FLOOR 1, ROOM 160
Bldg. 375, Room 160 – The laboratory is used for surface characterization of solid materials by X-ray photoelectron spectroscopy
(XPS), scanning Auger microscopy (SAM), and scanning electron microscopy (SEM).
Research &
B375-124200-RLP-001, CLASS B RADIOISOTOPE LABORATORY
0
2006 Aug
PROTOCOL - ADVANCED CANDU FUEL DEVELOPMENT
Development
LABORATORIES BLDG. 375, FLOOR 2, ROOMS 258-262
Bldg. 375, Rooms 258 and 262 - The laboratories are used for experimental powder and pellet fuel fabrication.
Research &
B467-108360-RLP-001, WASTE PROCESSING TECHNOLOGY
0
2009 May
Development
DEVELOPMENT LABORATORY, BUILDING 467
Bldg 467, Rooms 101, 102, 106, 106A and 110 – The laboratories are used for development of technologies to remove contaminants
from environmental and waste oil samples.
Class C Radioisotope Laboratories
Owner /
Description
Applicable Document(s)
Number / Title
B250-108332-RLP-001, B250, R111,111A, H3 LOOP
Rev
D1
Date
Research &
Rev. D1 is in review and
Development
comment
Bldg. 250, Rooms 111 and 111A – The laboratories are used for experimentation using radioactive tracers in H3 Loop
10
Information Use
Laboratory
Corrosion and Activity
Transports Tests
Activity Transport Loop
Facility
CAN-DECON
Decontamination Test
Loops
Coupons for Corrosion
Test
Chemical Cleaning
Laboratory
Geochemistry Laboratory
Heat Exchanger
Technology Branch
Laboratory
145-514100-GDI-002 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 11
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Research &
B250-108344-RLP-001, CLASS C RADIOISOTOPE LABORATORY
0
2004 Apr
PROTOCOL FOR BUILDING 250, ROOM 210, FLOOR 2:
Development
CORROSION AND ACTIVITY TRANSPORT
Bldg. 250, Room 210 – The laboratory is used for handling of radioactive samples produced during activity transport and corrosion
experiments. Handling of reactor artifacts.
Research &
B250-108330-RLP-001, CLASS C RADIOISOTOPE LABORATORY
D1
2005 Jun
PROTOCOL FOR HEAT EXCHANGER TECHNOLOGY BRANCH
Development
LABORATORY 112, BUILDING 250, ROOM 112, FLOOR 1
Bldg. 250, Rooms 213 and 215 – The laboratories are used for transport loop testing and analysis of loop samples; Inside surfaces of
loop piping and components; Wire mesh (H5 Loop source CR-233), metal coupons, and reactor artefacts.
Research &
B250-108343-RLP-004, RADIOLOGICAL LABORATORY
0
2009 May
PROTOCOL FOR CLASS C LAB B250 ROOM 221
Development
DECONTAMINATION TEST LOOPS
Bldg. 250, Room 221 – The laboratory is used for preparation of radioactive decontamination reactor-artefact coupons used in
decontamination tests in CAN-DECON Test Loops.
Research &
B250-108330-RLP-004, RADIOLOGICAL LABORATORY
0
2009 May
PROTOCOL FOR CLASS C LAB B250 ROOM 110 CORROSION
Development
COUPONS LAB
Bldg. 250, Room 110 – The laboratory is used for preparation of coupons for use in decontamination experiments.
Research &
B250-108330-RLP-003, RADIOLOGICAL LAB PROTOCOL FOR
0
2009 May
Development
B250 ROOM 415/417 CHEMICAL CLEANING LABORATORY
Bldg. 250, Rooms 415 and 417 – The laboratories are used for analysis of iron-removal cleaning solvents and their effects on corrosion
coupons.
Research &
B250-108360-RLP-001, CLASS C RADIOISOTOPE LABORATORY
0
2009 Aug
PROTOCOL FOR B250 ROOM 116 WASTE PROCESSING
Development
TECHNOLOGY
B250, Room 116 – The laboratory is used for processing, preparation and analysis of environmental samples using gamma
spectroscopy, gas chromatography, reverse osmosis and micro-filtration.
Research &
B250-108330-RLP-001, CLASS C RADIOISOTOPE LABORATORY
D1
2005 Jun
PROTOCOL FOR HEAT EXCHANGER TECHNOLOGY BRANCH
Development
LABORATORY 112, BUILDING 250, ROOM 112, FLOOR 1
11
Information Use
Laboratory
Shipping & Receiving
Room/Laboratory
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 12
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Bldg. 250, Room 112 – The laboratory is used for preparation and analysis of samples from the low temperature fouling loop and the
H-3 loop using wet chemistry techniques.
Research &
RLP-HXP-01,BUILDING 250 RADIOACTIVE MATERIAL
0
1998 Aug
Development
SHIPPING AND RECEIVING ROOM 114
Bldg. 250, Room 114 – The laboratory is used for shipping and receiving of active samples to and from B250.
Fuel Fabrication
Development Laboratory
Laser Laboratory
Solubility Studies
Laboratory
ICP-AES Laboratory
Heat Treatment and
Homogenization
Laboratory
Metallographic Services
Laboratory
145-514100-GDI-002 2010/09/23
Research &
B300-124200-RLP-001, ADVANCED CANDU FUEL
0
2008 Feb
Development
DEVELOPMENT LABORATORY, BUILDING 300 LAB 222
Bldg. 300, Room 222 - The laboratory is used for the development and testing of fabrication processes, and for fabrication and
characterization of prototype fuels in support of Advanced CANDU and other fuel programs.
Research &
B300-03512-RLP-001, RADIOISOTOPE LABORATORY PROTOCOL D1
Rev. D1 in review and
Development
FOR BUILDING 300B
comment
Bldg. 300, Rooms 133 and 134 – The laboratories are used for welding of creep capsules, fuel elements, and other zirconium
components.
Research &
B320-108360-RLP-006, CLASS C RADIOISOTOPE LABORATORY
0
2009 Aug
Development
PROTOCOL, BUILDING 320, FLOOR 3, ROOM 326
Bldg. 320, Room 326 – The laboratory is used for solubility studies of radioactive and inactive samples using general wet chemistry
procedures.
Research &
B320-108360-RLP-001, RADIOISOTOPE LABORATORY
0
2009 May
PROTOCOL FOR ICP-AES LABORATORYBUILDING 320, FLOOR
Development
3 ROOMS 309, 309A AND 312
Bldg. 320, Rooms 309, 309A and 312 – The laboratories are used for analysis of radioactive and inactive samples by Inductively
Coupled Plasma – Atomic Emission Spectrometry (ICP-AES).
153-03210-RWP-002, RADIATION WORK PROCEDURES FOR
0
2004 Dec
Research &
HEAT
TREATMENT
AND
HOMOGENIZATION
LABORATORY
Development
(ROOMS 117, 118A, 118B, AND 120B OF BUILDING 375)
Bldg. 375, Rooms 117, 118A, 118B and 120B – The laboratories are used for heat treatment.
Research &
Development
B375-108370-RLP-002, CLASS C RADIOISOTOPE LABORATORY
PROTOCOL FOR METALLOGRAPHIC SERVICES LABORATORY
BUILDING 375, ROOM 125/127, FLOOR1
D1
2007 Mar
12
Information Use
Laboratory
Surface Science
Laboratory
Fission Product Release
Group Laboratory
Invertebrate testing and
cell tritium effects
Laboratory,
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 13
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Bldg. 375, Rooms 125, 125A, 127 and 127A – The laboratories are used for preparation of metallographic samples for optical
microscopic examination.
Research &
B380-108730-RLP-001, B380, ROOMS 114,116,117 AND 120, THE
0
2004 Oct
Development
SURFACE SCIENCE LABORATORY.
Bldg. 380, Rooms 114, 116, 117 and 120 – The laboratories are used for scanning auger microscopy and scanning electron microscopy
for characterization of corrosion and degradation phenomena of solid materials.
Research &
B469-03512-RLP-001, RADIOLOGICAL LAB PROTOCOL FOR B469 0
2009 Jun
Development
ROOM 105, 125 AND 126B
Bldg. 469, Rooms 105, 125 and 126B – The laboratory is used for assembly and testing of experimental equipment used in hot cell
tests.
Research &
B513-121100-RLP-001, B513, ROOM 25 AND 27- INVERTEBRATE
0
2010 Feb
Development
TESTING AND CELL TRITIUM EFFECTS
Bldg. 513, Rooms 25 and 27 – The laboratories are used for invertebrate testing and cellular testing.
Bioassay Laboratories
Research &
B513-508790-RLP-001, RADIOISOTOPE LABORATORY
0
2009 Dec
Development
PROTOCOL FOR BIOASSAY LABORATORIES - R115,219,263-266
Bldg. 513, Rooms 115, 219, 219A, 263 and 266 – The laboratories are used for chemical analysis of bioassay samples.
Environmental
Technologies Branch
Radiochemistry
Laboratory
Research &
Development
Tritium Monitor/
Technique Development
Laboratory
Biological Research
Facility Laboratory
145-514100-GDI-002 2010/09/23
ETB-RLP-03, CLASS C RADIOISOTOPE LABORATORY FOR THE
ENVIRONMENTAL TECHNOLOGIES BRANCH
RADIOCHEMISTRY LAB, BLDG. 513B, RM 153
0
2000 Oct
Bldg. 513, Room 153 – The laboratory is used for preparation and radioanalysis of environmental samples using wet chemical
operations.
Research &
B513-121130-RLP-001, TRITIUM MONITOR/TECHNIQUE
0
2009 Jun
Development
DEVELOPMENT LAB, BUILDING 513, ROOM 259
Bldg. 513, Room 259 - The laboratory is used primarily for the development and testing of tritium (and other low-energy beta
particle/X-ray monitors such as 14C and 55Fe), development of new measurement techniques, and routine tritium instrument
calibrations.
Research &
B524-121111-RLP-001, RADIOLOGICAL LABORATORY
0
2010 Feb
PROTOCOL FOR CLASS C LAB B524 BIOLOGICAL RESEARCH
Development
FACILITY
13
Information Use
Laboratory
Owner /
Description
Pressure Tube Sampling
Tool (PTST) Facility
Laboratory
4.1.6
NRX Reactor and Fuel
Bays
Plutonium Recovery
Laboratory
Plutonium Tower
145-514100-GDI-002 2010/09/23
Applicable Document(s)
Number / Title
Rev
Date
Bldg. 524, Rooms 101, 173-175, 177 and 179 – The laboratories are used for exposure of animals/animal-derived tissues to
carcinogenic, biohazardous and radioactive materials.
Research &
B610-108360-RLP-001, CLASS C RADIOLOGICAL LABORATORY
0
2010 Feb
PROTOCOL FOR B610 REACTOR TOOLING REFURBISHMENT
Development
AND CALIBRATION
Bldg. 610, Rooms 103, 105 and 121 – The laboratories are used for refurbishment and calibration of radioactive pressure tube
sampling tubing.
Permanently Shutdown Facilities
Facility
Pool Test Reactor
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 14
Rev. 0
Owner /
Description
D&WM
D&WM
D&WM
D&WM
Applicable Document(s)
Number / Title
NRX-06190-PLN-002, NRX Reactor Facility Storage With Surveillance
Plan
3611-01610-PDP-004, Preliminary Decommissioning Plan: NRX
Reactor and Building 100 Decommissioning Plan
RC-2593, Building 204 A/B Fuel Rod Storage Bays, Chalk River
Laboratories: Detailed Decommissioning Plan
PTR-00422-6190-100, Pool Test Reactor Phase 1 Decommissioning
Monitoring, Testing and Surveillance Program
RC-1861, Pool Test Reactor Conceptual Decommissioning Plan
Rev
3
Date
2005 Feb
1
2002 Oct
1
2002 Mar
1998 Jul
0
1996 Jun
B220-06190-PLN-001, Plutonium Recovery Laboratory (Building 220)
Storage With Surveillance Plan
RC-2229, The Plutonium Recovery Laboratory, CRL Building 220,
Preliminary Decommissioning Plan
1
2000 Apr
1
2000 Apr
RC-2392, The Plutonium Tower, CRL Building 223, Preliminary
Decommissioning Plan
0
2002 Apr
14
Information Use
Facility
Waste Water Evaporator
4.1.7
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 15
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
D&WM
RC-2395, The Waste Water Evaporator CRL Building 228: Preliminary
Decommissioning Plan
Rev
Date
0
2000 Apr
Rev
28
Date
2009 May
8
2009 Apr
Other Facilities
Facility
Owner /
Description
MAPLE 1 and 2 Reactors
Applicable Document(s)
Number / Title
Operations
6425-05410-OLC-001, MAPLE Reactors Operations Limits and
Conditions
MAPLE 1 and MAPLE 2 reactors are is an extended shutdown state.
New Processing Facility
Operations
6424-05410-OLC-001, NPF Operational Limits and Conditions
The New Processing Facility (NPF) is in an extended shutdown state.
4.2
Whiteshell Laboratories
4.2.1
Nuclear Facilities
Facility
Concrete Canister Storage
Facility
145-514100-GDI-002 2010/09/23
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
D&WM
AECL-FA-22, FACILITY AUTHORIZATION FOR THE
3
1998 Jul
OPERATION OF THE CONCRETE CANISTER STORAGE
FACILITY AT THE WHITESHELL LABORATORIES
The WL Concrete Canister Storage Facility (CCSF), is adjacent to the WL Waste Management Area and has been used at WL since
1975 to store irradiated fuel.
15
Information Use
Facility
Active-Liquid Waste
Treatment Centre
Shielded Facilities
Waste Management Area
145-514100-GDI-002 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 16
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
D&WM
AECL-FA-25, FACILITY AUTHORIZATION FOR THE
3
1998 Jul
OPERATION OF THE ACTIVE-LIQUID WASTE TREATMENT
CENTRE WHITESHELL LABORATORIES.
The Active Liquid Waste Treatment Centre (ALWTC) at WL is is housed in Building 200 and routinely receives active liquids from
Buildings 100, 300, 411 and occasionally from the Waste Management Area (via tanker truck).
D&WM
AECL-FA-26, FACILITY AUTHORIZATION FOR THE
2
1998 Jul
OPERATION OF THE SHIELDED FACILITIES AT THE
WHITESHELL LABORATORIES
The Shielded Facilities (SF), which includes the Hot Cell Facility (HCF) and the Immobilized Fuel Test Facility (IFTF), is located in
the Research & Development Building (Building 300). The HCF provides facilities for remote handling services for decommissioning
work involving radioactive material. The IFTF is currently being decommissioned.
D&WM
AECL-FA-28, FACILITY AUTHORIZATION FOR THE
3
1998 Jul
OPERATION OF THE WASTE MANAGEMENT AREA
WHITESHELL LABORATORIES
The Waste Management Area (WMA) provides processing and storage facilities for radioactive wastes, including low level wastes
(LLW), medium level waste (MLW), high level liquid waste (HLLW) and small volumes of active liquids and hazardous industrial
chemicals. These wastes originate from the operation of WL experimental facilities. The WMA continues to accept operational and
decommissioning waste.
16
Information Use
4.2.2
Class B Radioisotope Laboratories
Location / Site
Owner /
Description
Inorganic Preparation
Laboratory
Inorganic
Spectrochemistry
Laboratory.
Radiochemistry
Laboratory
4.2.3
Applicable Document(s)
Number / Title
Rev
Date
D&WM
WL-124200-610-000-001/RLP For WL Analytical Science Laboratory
0
2010 Jun
Complex
Bldg. 300, Rooms 2-168 and 2-172 – The laboratory is used for chemical processing of solid and liquid samples: dilution, digestion,
dissolution, filtering, weighing, drying, etc. The physical nature of the material analyzed is quite varied, ranging from aqueous
solutions, to vegetation and soil, to waste tank sludges and concrete.
D&WM
WL-124200-610-000-001/RLP For WL Analytical Science Laboratory
0
2010 Jun
Complex
Bldg. 300, Rooms 2-119 and 2-139 - The laboratory is used for instrumental analysis of liquid samples by Flame Atomic Absorption
(FAA), Inductively Coupled Plasma Atomic Emission Spectroscopy (ICP), Mercury analysis (Hg), and Ion Chromatography (IC) (as
former 2-119/139). The physical nature of materials analyzed is quite varied, ranging from aqueous solutions, through vegetation and
soil, to waste tank sludges and concrete.
D&WM
WL-108360-RLP-001/Radioisotope Laboratory Protocol for Class B
0
2006 Oct
Radiochemistry Laboratory
Bldg. 100, Room 650 - The laboratory is primarily used for radiochemical separations and sample preparation for nuclear
measurement techniques, such as: alpha spectrometry, gamma spectrometry and liquid scintillation counting. The laboratory
receives, handles and performs radiochemical separations and analyses on samples containing low to medium levels of radioactivity.
This includes material originating from decommissioning activities and continuing waste management operations. The laboratory
also handles environmental monitoring samples that contain too high a level of activity to be safely handled by the
WL Environmental Monitoring Section. The physical nature of the material analyzed is quite varied, ranging from aqueous solutions,
to vegetation and soil, to waste tank sludge and concrete.
Class C Radioisotope Laboratories
Laboratory
Inorganic Analysis Lab.
145-514100-GDI-002 2010/09/23
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145-514100-GDI-002 Page 17
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
D&WM
WL-124200-610-000-001/RLP For WL Analytical Science Laboratory
0
2010 Jun
Complex
Bldg. 300, Rooms 2-173 and 2-184 - The laboratory is used for chemical processing of solid and liquid samples: dissolution,
distillation, dilution, digestion, filtering, weighing, drying, etc. The physical nature of the material handled is quite varied, ranging
from aqueous solutions, through vegetation and soil, to sediments and sludges, to samples of unknown composition.
17
Information Use
Laboratory
Owner /
Description
Organic Preparation and
Analysis Lab
Environmental Monitoring
Lab
4.2.4
Facility
WR-1 Reactor
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145-514100-GDI-002 Page 18
Rev. 0
Applicable Document(s)
Number / Title
Rev
Date
D&WM
WL-124200-610-000-001/RLP For WL Analytical Science Laboratory
0
2010 Jun
Complex
Bldg. 300, Rooms 2-169 and 2-170 - The laboratory is used for sample preparation and instrumental analysis of solid, liquid, and
gaseous samples, using chromatographic techniques including GC, GC/MS, etc.). The physical nature of the material analyzed is
quite varied, ranging from aqueous solutions, through soil, to microbiology test broths.
Programs &
RLP-C&RP-EM-01/ CLASS C Radioisotope Laboratory Protocol
3
2004 Apr
Nuclear
Radioisotope Laboratory
Oversight
Bldg. 100, Room 702 - The laboratory is used for receiving, handling and performing radioanalysis of environmental level and
low-level radioactive samples. Environmental samples are primarily in the form of water, fish or animals, vegetation and soil.
Low-level radioactive samples include radioactive standards from stock solutions received from external radionuclide suppliers and
small volumes of low-level radioactive waste samples from nuclear operations at WL. The majority of radioactivity handling
involves the dilution, preparation and radioanalysis of liquid waste samples originating from the low-level liquid waste holding tanks
in the Building 200 Active Liquid Waste Treatment Center. It is the radioactivity of the latter that require the Class C classification.
Permanently Shutdown Facilities
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
D&WM
RC 1291,The Monitoring and Surveillance Plan for the WR-1
1
1996 Mar
Deferment Period
WR-1 Reactor was permanently shutdown in 1985, defuelled, and partially decommissioned. A deferment period was started
following the completion of the Phase 1 Decommissioning in 1995. During the deferment period, the facility is, and will continue to
be, monitored and maintained as defined by the Monitoring and Surveillance Plan for the WR-1 Deferment Period.
18
Information Use
4.2.5
Other Facilities and Laboratories
Facility
B402 Gamma Irradiator
B412 Radiography Room
RD-14M Loop Neutron
Scatterometer
The Environmental
Monitoring/ASB Joint
Radiochemical Counting
Lab 100-658 Radiation
Work Procedure
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145-514100-GDI-002 Page 19
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
Rev
Date
Programs &
DSPWL-508792-PRO-013/TLD Calibrator Procedures
0
2010 Feb
Nuclear
RadP-WL-508740-801-OI-002/Sheperd Model 181 Gamma Calibration
0
2007 Sep
Oversight
Operation
Bldg. 402, Room B-02. Houses a 20 Ci (740 GBq) Cs-137 Shepherd Model 81 Gamma Calibrator that is used to perform gamma
calibrations of TLDs, gamma dose rate meters and personal alarming dosimeters.
D&WM
RC-2000-030/Radiography Operating and Emergency Procedures
1
2005 Nov
WLD-106147-OP-002/100 Curie Cobalt-60 Source Projector Safe
Operating and Emergency Procedure
2
2010 May
Bldg. 412, Room 1-72 - The room is used to perform radiography on components using a 100 Ci (3.7 TBq) Ir-192 exposure device.
Used to store the Ir-192 device when not in use. Also used to store a Sentinel/QSA Global Inc. Model 680B-OP Projector with 100
Ci (3.7 TBq) Cobalt-60 (60Co) source assembly Model Number A424-14 being used for gamma axial density profiling of the
WL-WMA standpipes. Both exposure devices are operated by AECL-WL qualified radiographers.
Research &
RD-14M Heated Channel Neutron Scatterometer system Description and 0
2000 Mar
Development
Operation
Bldg. 300, RD-14M Facility - Measures transient void fraction measurements in an RD-14M heated section under simulated LOCA
conditions.
Programs &
RWP-B100 R658/WL Environmental Monitoriing/Analytical Science
3
2004 Apr
Nuclear
Counting Lab Radiation Work Procedure
Oversight /
D&WM
Bldg. 100, Room 658 - The laboratory is used for receiving, handling and performing radioanalysis of environmental level and
low-level radioactive samples. Environmental samples are primarily in the form of water, fish or animals, vegetation and soil.
Low-level radioactive samples include radioactive standards from stock solutions received from external radionuclide suppliers and
small volumes of low level radioactive waste samples from nuclear operations at WL. Low-level radioactive swipes and samples are
also counting for site RP staff. The Analytical Science Branch receives, handles and performs radioanalysis of radioactive samples in
various forms such as mixed radioactive tank waste, sludges, radioactive tracer test solutions, contaminated soils, sediments, filters
and swipes. The only handling of radioactivity in this laboratory involves loading of samples for radiochemical counting.
19
Information Use
Facility
Radiation and Industrial
Safety Instrumentation
Shop
WL XRD Laboratory
WL Laundry and
Decontamination `
145-514100-GDI-002 2010/09/23
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145-514100-GDI-002 Page 20
Rev. 0
Owner /
Description
Applicable Document(s)
Number / Title
RadP-WL-508740-801-OI-001/Radiation Source Handling
Rev
0
Date
2007 Sep
Programs &
Nuclear
Oversight
Bldg. 100, Room 646 - The shop is used for calibrating and maintaining radiation protection and industrial hygiene survey and
monitoring equipment used in the field by WL radiation and industrial safety staff and authorized WL personnel.
D&WM
EB&AB-00-100/Whiteshell Laboratory X-Ray Diffraction Laboratory
1
2005 Oct
Radiation Safety Manual
Bldg. 300, Room B-184 - A rotaflex RU-200 X-ray Diffraction (XRD) Unit manufactured by Rigaku is operated in the XRD
Laboratory. The XRD Unit is a highly specialized analytical unit that utilizes analytical X-rays to determine chemical composition
and crystal structure of materials. XRD analyses are performed on various materials required by site researchers and commercial
customers.
Programs &
RADP-WL-508740-504-OI-002, DECONTAMINATION CENTRE 1
2007 Apr
Nuclear
DECONTAMINATION SECTION
Oversight
Bldg 411 – This facility is used for performing decontamination of articles in a controlled environment using various techniques.
20
Information Use
5.
AECL - OFFICIAL USE ONLY
145-514100-GDI-002 Page 21
Rev. 0
REFERENCES
[1]
145-514100-MAN-001, Management System Manual.
[2]
[3]
145-514100-GDI-001, Management System Governing Documentation Index.
145-514100-016-000, Management System Contact and Responsibility List.
145-514100-GDI-002 2010/09/23
21
Revision History
Liste de révisions
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À USAGE EXCLUSIF - EACL
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CW-511300-FM-168 Rev. 0
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002
Doc. Collection ID
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SI
Répertoire du sujet
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Serial No.
o
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Title
Titre
SITES AND FACILITIES GOVERNING DOCUMENTATION INDEX
23
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consultez la feuille de transmission de documents ci-jointe.
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Date
(yyyy/mm/dd)
Details of Rev. / Détails de la rév.
Prepared/Revised by
Rédigé/Examiné par
Reviewed by
Examiné par
Approved by
Approuvé par
D1
2010/07/13
Issued for “Review and Comment”.
R.G. Lavoie
0
2010/09/23
Issued as “Approved for Use”.
R.G. Lavoie
H. Andersen (for
B. Sanderson)
D. Lemire
J.L. Grenier
T. Arthur
S. Lawton
C. Van Drunen
S. Beauchamp
K. Smith
C. Clavel
C. Van Drunen
R. Lesco
No./N
dsfpdfscs
o
145-514100-GDI-002 2010/09/23
Manual
MANAGEMENT SYSTEM
145-514100-MAN-001
Revision 0
Prepared by
Rédigé par
Beauchamp Stephen - Section
Head, Engineering Programs &
Reviewed by Standards
Vérifié par
Cox David S - Director - Safety Van Drunen Christina - Manager,
Engineering & Licensing
Engineering Programs &
Approved by
Standards
Approuvé par
Kupferschmidt William C(Bill) ­
Delegated SVP, Research &
Technology Operations
2010/09/23
2010/09/23
AECL - OFFICIAL
USE ONLY
À L'USAGE EXCLUSIF
D'EACL
Atomic Energy of
Canada Limited
Énergie Atomique du
Canada Limitée
2251 Speakman Drive
Mississauga, Ontario
Canada L5K 1B2
2251 rue Speakman
Mississauga (Ontario)
Canada L5K 1B2
Manual
Management System
Research & Technology
Operations
145-514100-MAN-001
Revision 0
145-514100-MAN-001 2010/09/23
2010 September
septembre 2010
AECL - OFFICIAL
USE ONLY
À USAGE
EXCLUSIF - EACL
This document and the
information contained in it is the
property of Atomic Energy of
Canada Limited (AECL). No use,
disclosure, exploitation or transfer
of any information contained
herein is permitted in the
absence of an agreement with
AECL, and the document may
not be released without the
written consent of AECL.
Le présent document et
l’information qu’il contient sont la
propriété d’Énergie atomique du
Canada limitée (EACL). Le
présent document ne peut être
transmis sans l’autorisation écrite
d’EACL et les renseignements
qu’il contient ne peuvent être
utilisés, ni divulgués, ni exploités
ni communiqués sans entente à
cet effet avec EACL.
© Atomic Energy of Canada
Limited
© Énergie atomique du
Canada limitée
Revision History
Liste de révisions
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À USAGE EXCLUSIF - EACL
Page 1 of /de 1
CW-511300-FM-168 Rev. 0
Ref. Procedure CW-511300-PRO-161
Document No. / Numéro de document:
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514100
MAN
001
Doc. Collection ID
ID de la collection de doc.
SI
Répertoire du sujet
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Serial No.
o
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Title
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Management System
64
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Date
(yyyy/mm/dd)
Details of Rev. / Détails de la rév.
Prepared by
Rédigé par
Reviewed by
Examiné par
D1
2010/07/30
Issued for “Review and Comment”.
R.G. Lavoie
0
2010/09/23
Issued as “Approved for Use”.
R.G. Lavoie
H. Andersen (for B.
Sanderson)
D. Lemire
B. Zadarko
J.L. Grenier
T. Arthur
S. Lawton
C. Van Drunen
S. Beauchamp
K. Smith
C. Clavel
C. Van Drunen
R. Lesco
No./N
dsfpdfscs
o
Approved by
Approuvé par
W. Kupferschmidt
145-514100-MAN-001 2010/09/23
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145-514100-MAN-001 Page i
Rev. 0
TABLE OF CONTENTS
SECTION
PAGE
1.
INTRODUCTION ........................................................................................... 1-1
1.1
1.2
1.3
Scope ............................................................................................................... 1-1
Purpose ............................................................................................................ 1-2
Definitions ....................................................................................................... 1-3
2.
MANAGEMENT COMMITMENT ................................................................. 2-1
3.
SAFETY.......................................................................................................... 3-1
3.1
3.1.1
3.2
3.2.1
3.2.2
3.2.3
Safety Culture .................................................................................................. 3-1
Safety Principles ........................................................................................ 3-1
Safety Management.......................................................................................... 3-2
Philosophy ................................................................................................. 3-2
Basis of Safety ........................................................................................... 3-2
Operational Safety...................................................................................... 3-2
4.
MANAGEMENT PRINCIPLES ...................................................................... 4-1
4.1
4.2
4.2.1
4.2.2
4.2.3
4.2.4
4.2.5
4.2.6
4.2.7
4.2.8
4.2.9
4.2.10
4.2.11
4.2.12
4.2.13
4.2.14
Quality Management Principles ....................................................................... 4-1
Management System Principles........................................................................ 4-1
The Business is Defined, Planned, and Controlled ...................................... 4-1
The Organization is Defined and Understood ............................................. 4-1
Personnel are Competent at the Work They Do .......................................... 4-2
Personnel Know What is Expected of Them ............................................... 4-2
Work is Planned ......................................................................................... 4-2
Experience is Sought, Shared and Used ...................................................... 4-2
Information is Provided in Time to the People Who Need It ....................... 4-2
The Performance of Work is Controlled ..................................................... 4-3
The Preparation and Distribution of Documents are Controlled .................. 4-3
Work Is Verified to Confirm that it is Correct............................................. 4-3
Problems are Identified and Resolved......................................................... 4-3
Changes are Controlled .............................................................................. 4-4
Records are Maintained .............................................................................. 4-4
Assessments are Performed ........................................................................ 4-4
5.
ORGANIZATION OVERVIEW...................................................................... 5-1
5.1
5.2
5.3
5.4
5.5
5.6
Description ...................................................................................................... 5-1
Vision and Mission Statement .......................................................................... 5-1
Management Model ......................................................................................... 5-1
Business Planning ............................................................................................ 5-2
Performance Management and Reporting ......................................................... 5-3
Partners, Customers and other Stakeholders ..................................................... 5-3
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TABLE OF CONTENTS
SECTION
5.6.1
5.6.2
5.6.3
5.6.4
5.6.5
PAGE
Research and Development Partners and Customers................................... 5-3
Emergency Preparedness Partners .............................................................. 5-4
World Association of Nuclear Operators (WANO) and Institute of
Nuclear Power Operations (INPO) ............................................................. 5-4
Other Customers ........................................................................................ 5-4
Other Partners and Stakeholders ................................................................. 5-5
6.
NUCLEAR OPERATIONS ............................................................................. 6-1
6.1
6.2
6.3
General ............................................................................................................ 6-1
Class I and Class II Facilities ........................................................................... 6-1
Radioisotope Laboratories................................................................................ 6-1
7.
RESPONSIBILITIES AND ORGANIZATION ............................................... 7-1
7.1
7.2
7.2.1
7.2.2
Organization Structure ..................................................................................... 7-1
Nuclear Leadership Team (NLT) ..................................................................... 7-2
Senior Vice-President................................................................................. 7-2
Vice-President and General Manager, Operations and Chief
Nuclear Officer .......................................................................................... 7-2
General Manager, Isotope Supply Reliability Program.......................... 7-2
Vice-President and General Manager, Decommissioning and Waste Management .................................................................................... 7-2
Vice-President and General Manager, Research & Development ................ 7-3
Principal Scientist....................................................................................... 7-4
Vice-President, Commercial....................................................................... 7-4
General Manager, Finance and Business Services....................................... 7-4
General Manager, Programs and Nuclear Oversight, and Chief
Regulatory Officer ..................................................................................... 7-5
General Manager, Engineering and Chief Nuclear Engineer ....................... 7-5
RTO General Counsel ................................................................................ 7-6
Manager, Human Resources ....................................................................... 7-6
General Responsibilities................................................................................... 7-6
Vice-Presidents and General Managers ...................................................... 7-6
Management............................................................................................... 7-7
Employees.................................................................................................. 7-8
Site Licence Holders .................................................................................. 7-8
Process and Program Management ............................................................. 7-9
Facility Management .................................................................................. 7-9
Senior Quality Representatives and Supporting Staff.................................7-10
Committees.....................................................................................................7-10
Operational Safety Oversight Committee (OSOC).....................................7-11
Performance Oversight Committee (POC).................................................7-11
7.2.2.1
7.2.3
7.2.4
7.2.5
7.2.6
7.2.7
7.2.8
7.2.9
7.2.10
7.2.11
7.3
7.3.1
7.3.2
7.3.3
7.3.4
7.3.5
7.3.6
7.3.7
7.4
7.4.1
7.4.2
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TABLE OF CONTENTS
SECTION
7.4.3
7.4.4
7.4.5
7.4.6
7.4.7
7.4.8
7.4.9
7.4.10
PAGE
Business Operations Strategy (BOS) Committee .......................................7-11
Project Performance Oversight Committee (PPOC)...................................7-11
ImpAct Review Board (IRB).....................................................................7-11
Health, Safety, Security and Environment Business Performance
Council (HSSE BPC) ................................................................................7-11
Environmental Panel (EP) .........................................................................7-12
Site Safety and Health Committees............................................................7-12
Nuclear Performance Assurance Review Board (NPARB) ........................7-12
Safety Review Committee (SRC) ..............................................................7-12
8.
BUSINESS PROCESS..................................................................................... 8-1
8.1
8.2
Graded Approach in Processes ......................................................................... 8-1
Compliance with Requirements........................................................................ 8-2
9.
GOVERNING DOCUMENTATION............................................................... 9-1
9.1
9.2
9.3
9.3.1
9.3.2
9.4
9.5
9.5.1
9.5.2
9.5.3
General ............................................................................................................ 9-1
Level 1, Corporate Plan and Management System Manuals.............................. 9-1
Levels 2, 3 and 4 .............................................................................................. 9-2
Planning Documents .................................................................................. 9-2
Process Documents .................................................................................... 9-2
Records............................................................................................................ 9-3
Local Governing Documentation...................................................................... 9-3
Operating Nuclear Facilities ....................................................................... 9-3
Radioisotope Laboratories .......................................................................... 9-3
Departments ............................................................................................... 9-4
10.
MEASUREMENT, ASSESSMENT AND IMPROVEMENT .........................10-1
10.1
10.1.1
10.1.2
10.2
10.2.1
10.2.2
10.2.3
10.2.4
10.2.5
10.3
Measurements .................................................................................................10-1
Event Free Day Reset ................................................................................10-1
Scorecard Measures...................................................................................10-1
Assessments....................................................................................................10-1
Self-Assessments ......................................................................................10-1
Audits .......................................................................................................10-1
Program and Process Reviews ...................................................................10-2
External Assessments ................................................................................10-2
Other Assessments and Management Oversight.........................................10-2
Improvements .................................................................................................10-2
11.
REFERENCES ...............................................................................................11-1
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145-514100-MAN-001 Page iv
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TABLE OF CONTENTS
SECTION
PAGE
FIGURES
Figure 1-1
Figure 1-2
Figure 5-1
Figure 7-1
Figure 8-1
Figure 9-1
Management System Documentation ............................................................... 1-2
Management System Elements......................................................................... 1-4
Overview of RTO in Management Plan............................................................ 5-2
Organization Structure ..................................................................................... 7-1
Business Process Model ................................................................................... 8-1
Management System Governing Documentation Hierarchy.............................. 9-1
APPENDICES
Appendix A
A.1
A.2
A.3
A.4
A.5
A.6
A.7
A.8
A.9
A.10
Appendix B
B.1
B.2
B.3
B.4
B.5
B.5.1
B.5.2
B.5.3
B.6
B.7
B.8
B.8.1
B.8.2
B.8.3
B.8.4
B.8.5
145-514100-MAN-001 2010/09/23
Principles .........................................................................................................A-1
Safety Principles ..............................................................................................A-1
Quality Management Principles .......................................................................A-2
Customer Focus..........................................................................................A-2
Leadership..................................................................................................A-2
Involvement of People................................................................................A-3
Process Approach.......................................................................................A-3
System Approach to Management ..............................................................A-3
Continual Improvement..............................................................................A-4
Factual Approach to Decision Making........................................................A-4
Mutually Beneficial Supplier Relationships ................................................A-4
Business Processes...........................................................................................B-1
Process 501000, Understand Markets and Customers .......................................B-1
Process 502000, Define Vision, Strategy and Corporate Plan ...........................B-1
Process 503000, Develop and Design Products, Services or Projects ................B-2
Process 504000, Market and Sell Products and Services...................................B-2
Process 505000, Produce, Build, Modify and Deliver Products,
Services or Projects..........................................................................................B-2
Process 505210, Perform Procurement and Materials Management ............B-3
Process 505240, Manage Construction and Installation ..............................B-3
Process 505250, Manage Commissioning and Testing................................B-3
Process 506000, Provide After-Sales Customer Support...................................B-3
Process 507000, Develop and Maintain Nuclear Technology ...........................B-4
Process 508000, Manage Facilities, Nuclear Laboratories, Materials
and associated Liabilities..................................................................................B-4
Process 508120, Provide Design and Engineering ......................................B-5
Process 508220, Operate Facilities .............................................................B-5
Process 508230, Provide Maintenance........................................................B-5
Process 508300, Decommission Sites and Facilities ...................................B-5
Process 508510, Manage Nuclear Materials and Safeguards .......................B-6
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TABLE OF CONTENTS
SECTION
B.8.6
B.8.7
B.8.8
B.8.9
B.8.10
B.8.11
B.8.12
B.8.13
B.8.14
B.8.15
B.9
B.9.1
B.10
B.10.1
B.10.2
B.10.3
B.10.4
B.11
B.11.1
B.12
B.13
B.13.1
B.13.2
B.14
B.14.1
B.14.2
B.14.3
B.14.4
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Process 508520, Manage Transportation of Radioactive Materials..............B-6
Process 508550, Provide Nuclear Criticality Safety Control .......................B-6
Process 508600, Manage Wastes ................................................................B-6
Process 508710, Provide Physical Security.................................................B-6
Process 508720, Provide Fire Protection.....................................................B-7
Process 508730, Provide Emergency Preparedness.....................................B-7
Process 508740, Provide Radiation Protection............................................B-7
Process 508750, Provide Operating Experience ..........................................B-7
Process 508760, Provide Licensing Services ..............................................B-7
Process 508770, Provide Safety Analysis and Operational Safety
Assessment ................................................................................................B-8
Process 509000, Manage Environmental Protection .........................................B-8
Process 509200, Provide Environmental Protection Program......................B-8
Process 510000, Develop and Manage Human Resources ................................B-8
Process 510100, Manage Staffing...............................................................B-9
Process 510200, Train and Develop Employees..........................................B-9
Process 510400, Ensure Employee Safety and Well-being..........................B-9
Process 510700, Manage Employee Communications ................................B-9
Process 511000, Manage Information and Associated Technology...................B-9
Process 511300, Manage Information Assets............................................ B-10
Process 512000, Manage Financial Resources................................................ B-10
Process 513000, Manage External Relationships ............................................ B-10
Process 513300, Manage Community Relationships................................. B-11
Process 513400, Manage External Communications................................. B-11
Process 514000, Improve Organizational Performance and Manage
Change........................................................................................................... B-11
Process 514010, Safety Culture, and Process 514020, Human
Performance ............................................................................................. B-12
Process 514100, Maintain and Improve Overall Management
System ..................................................................................................... B-12
Process 514200, Prescribe Quality Requirements and Improve
Business Processes ................................................................................... B-12
Process 514300, Ensure Compliance with Requirements .......................... B-12
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1.
INTRODUCTION
1.1
Scope
This document describes the management system in place for the Research and Technology
Operations (RTO) division of Atomic Energy of Canada Limited (AECL). The management
system governs the activities carried out in support of business, scientific, engineering, technical,
operational, liability and compliance management, and applies at all locations managed by the
organization.
The document includes the following:









Management commitment, described in Section 2;
Safety culture and safety management, described in Section 3;
Management principles, described in Section 4;
Organization overview, described in Section 5;
Nuclear operations, described in Section 6;
Responsibilities and organization, described in Section 7;
Business process and supporting programs, described in Section 8;
Governing documentation structure, described in Section 9; and
Measurement, assessment and improvement activities, described in Section 10.
The document supplements the AECL Management Manual (AMM) [1], which describes AECL,
its overall management system, policies and associated responsibilities, primarily at the
executive level. This document includes information from the AMM where deemed necessary to
describe the management system for RTO. NOTE:
When the Commercial Operations division of AECL is separated from the Nuclear
Laboratories (RTO) division, the AMM and this document will be consolidated and
updated as required.
This document has the following supporting documents:
 A Governing Documents Index (GDI) document listing external requirements, company
policies and manuals, and governing documents to support business processes issued for
general use within the organization [2];
 A GDI document listing the main governing documents for sites and facilities managed and
operated by RTO [3]; and
 A Contact and Responsibility List listing the names of individuals responsible for the
departments, facilities, laboratories and supporting processes and programs [4].
Figure 1-1 provides the relationship between this document and the four documents referenced
above.
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AECL Management
Manual [1]
Describe
Management
System
RTO Management
System Manual
GDI-002 [3]
External and Internal
Governing Documents
Sites, Facilities and
Laboratories Governing
Documents
Contact and
Responsibility List
[4]
Licenses, permits
standards, regulations,
process & program documents,
planning documents
Site, facility and
laboratory specific
governing
documents
Senior management and
contacts for committees, process
& programs, facilities,
laboratories, projects
GDI-001 [2]
Supporting
Documents
Figure 1-1 Management System Documentation
If there are conflicts or inconsistencies between this document and its supporting GDIs and
provisions in the AMM [1], or any of the QA Manuals previously issued to support CAN/CSA
N286 series of standards (N286.0 through N286.6), seek clarification from the General Manager,
Engineering or his/her designate on management system matters.
1.2
Purpose
The primary objective of the management system is to manage the set of interrelated or
interacting system elements for establishing policies and objectives and enabling the objectives
to be achieved in an efficient and effective way. The management system integrates all elements
of the organization into one coherent system to enable all of the organization’s objectives to be
achieved. These elements include the structure, resources and processes.
The management system integrates safety, health, environmental, security, quality, economic and
other elements required to ensure the protection of people, the environment, and company assets.
It is also to manage and improve business processes used to integrate common requirements, and
to satisfy the requirements of stakeholders and applicable regulations and management system
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standards, including CAN/CSA-ISO 9001:08 (ISO 9001:2008) Quality management systems –
Requirements [5] and ISO 9000:2005, Quality management systems – Fundamentals and
vocabulary.
Progression towards implementation of an Integrated Management System (IMS) is needed to
support AECL’s application to the Canadian Nuclear Safety Commission (CNSC) for a licence
renewal for the Chalk River Laboratories (CRL) in November 2011. Hence, the management
system defined herein is also designed to meet the requirements of CSA N286-05, Management
system requirements for nuclear power plants [6], which replaces CSA N286.0 and the
associated CSA Standards N286.1 through N286.6, and will further evolve to an IMS.
Reference [2] includes appendices with cross-reference tables showing the processes in place to
meet requirements of N286-05 and other applicable management system standards.
The Senior Vice-President is responsible for the overall implementation and continuous
improvement of the management system, while:
 The site licence holders are responsible for the implementation of the management system at
their respective site, as described in Section 7.3.4; and
 The General Manager, Engineering is responsible for the development and maintenance of
the management system documentation.
Figure 1-2 provides an overall view of the management system elements described herein. It
includes references to sections in the AMM, sections in this manual, and sections in the GDI
document.
1.3
Definitions
Except where otherwise defined, this document relies on word meanings as found in common
dictionaries. For terms and abbreviations refer to the individual documents listed in the GDIs
(References [3] and [4]) or the Acronyms, Abbreviations, and Definitions of Terms web site on
myAECL (http://sps39/terms_definitions/terms.asp).
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Our Mandate - Customer & Stakeholders
[AMM Section 2.2 and 2.5]
Our Safety Culture and Safety Management
MSM Section 3
Our Management Principles
MSM Section 4
Our Policies
AMM Section 2.4
Our Vision &
Mission Statement
Where We Work
AMM Section 2.7
MSM Section 5.2
Our Three Core Missions
Isotope Production
Environmental
Management
Research Development & Innovation
MSM Section 5.3
Nuclear Operations
MSM Section 6
What We
Comply With
How We Are
Organized
MSM Section 8.2 &
GDI Section 4.1
AMM Section 3
MSM Section 7
What We Do
MSM Section 5
How We Work - Our Business Processes
MSM Section 8 & GDI Sections 4.2 and 4.3
Our Documentation Framework
MSM Section 9
How We Improve - Measurements and Assessments
MSM Section 10
Legend:
AMM = AECL Management Manual (CW-514000-MAN-002 Rev. 2)
MSM = Management System Manual (145-514100-MAN-001 Rev. 0)
GDI = Governing Documentation Index document (145-514100-GDI-001 Rev. 0)
Figure 1-2 Management System Elements
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2.
MANAGEMENTCO~TMENT
As the leadership team for RTO we are committed to the development, implementation and
continuous improvement of the management system described in this manual; and will seek the
same commitment of our staff. We comply with the organization's policies while continuously
improving the underlying processes to support our operation. We also accept our respective
responsibilities listed herein.
2010 S "'(J1-2~
Earnest (Hank) Drumhiller
Vice-President & General Manager,
Operations and Chief Nuclear Officer
I
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"7""/ (12-,<:
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,····Joan Miller
Vice-President & General Manager,
Waste Management and
Decommissioning
Richard Didsbury (Actin )
Vice-President & General Manager,
Research and Development
Date
2)0/0
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Andrew White
General Manager, Programs and
Nuclear Oversight and Chief
Regulatory Officer
lt y-
Date
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Steven Halpenny
General Manager, Finance and
Business Services
General Manager, En . eering and
Chief Nuclear' I eer
Richard Cote
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Vice-President, 06mmercial
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$:pl;( if
Date
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Date
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Date
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Manager, Human Resources
~~~~~~~~_ 2~/J ~43 ____~l~~~--__Stephen Bushby
General Manager, Isoto e
Reliability Program
Date
Doug McImyre
RTO General Cou
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Date
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3.
SAFETY
3.1
Safety Culture
RTO is committed to building a strong safety culture and working towards an “event free” work
environment.
A human performance program (See Process 514020, Human Performance, described in
Appendix B, Section B.14.1) has been developed to provide tools and best practices to reduce
human error and thereby reduce events. The ultimate goal is to reduce the likelihood of error and
to create defences that will prevent the remaining errors from causing events.
The successful implementation of this program will increase situational awareness throughout
the organization and decrease human error. This will result in positive control of work and
enhanced safety for employees, the general public, the work site, and the environment.
The human performance program activities are integrated with, and support, other safety-related
programs to ensure safety risk is controlled to as low as reasonably achievable. Externally, the
experience with the program is shared with our nuclear partners to further improve human
performance best practices across the industry.
3.1.1
Safety Principles
RTO has adopted the safety principles defined by WANO GL 2006-02, Principles for a Strong
Nuclear Safety Culture [7]. The principles describe the essential attributes of a healthy safety
culture, with the goal of creating a framework for open discussion and continuing evolution of
safety culture throughout the nuclear industry. These principles influence the assumptions,
experiences, behaviours, beliefs, and norms used by the organization in defining the work to be
done at a specific facility and how it is to be done.
Managers and staff are expected to compare these principles with their day-to-day activities and
practices and to use any differences as a basis for improvement.
The eight principles, listed below, are explained in Appendix A, Section A.1, while their
attributes are covered in [7].
1.
2.
3.
4.
5.
6.
7.
8.
Everyone is personally responsible for nuclear safety.
Leaders demonstrate commitment to safety.
Trust permeates the organization.
Decision-making reflects safety first.
Nuclear technology is recognized as special and unique.
A questioning attitude is cultivated.
Organizational learning is embraced.
Nuclear safety undergoes constant examination.
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3.2
Safety Management
3.2.1
Philosophy
RTO is a complex organization that undertakes a wide variety of work. In carrying out this work,
safety is put as the highest priority. In establishing this priority, it is recognized that “safety” in the
organization covers a broad range of areas where the health and well-being of workers or visitors
as well as that of the wider general public and/or the environment could be threatened.
The general approach taken is to ensure that RTO sites and facilities are “safe” by design and that
they are “safe” during all stages of operation – it is important to recognize, that any aspect of site
operation can have consequences in other areas of the site that must be understood and effectively
managed; this is especially the case for critical elements of site infra-structure.
3.2.2
Basis of Safety
In the context of the development, production and use of nuclear energy and the production,
possession and use of nuclear substances, prescribed equipment, and prescribed information,
“safe” means the prevention of unreasonable risk to the environment and to the health and safety
of persons, associated with that development, production, possession, or use.
3.2.3
Operational Safety
Safe operation is achieved by following a number of key programs and processes each with a focus
on a specific safety area.
They include the following processes1:












1
508510, Manage Nuclear Materials and Safeguards, described in Section B.8.5;
508520, Manage Transportation of Radioactive Materials, described in Section B.8.6;
508550, Provide Nuclear Criticality Safety Control, described in Section B.8.7;
508600, Manage Waste, described in Section B.8.8;
508710, Provide Physical Security, described in Section B.8.9;
508720, Provide Fire Protection, described in Section B.8.10;
508730, Provide Emergency Preparedness, described in Section B.8.11;
508740, Provide Radiation Protection, described in Section B.8.12;
508750, Provide Operating Experience, described in Section B.8.13;
508770, Provide Safety Analysis and Operational Safety Assessment, described in Section
B.8.15;
509000, Manage Environmental Protection, described in Section B.9; and
510400, Ensure Employee Safety and Well-being, described in Section B.10.3.
Business process is described in Section 8, and process overview descriptions are covered in Appendix B.
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Other supporting processes such as maintenance and work planning are carried out within the
overall safe operating envelope at the sites.
In addition to program-specific measures, monitoring of safety performance in the operational
area is achieved through the concept of “events” and the associated record of “Event Free Days”,
described in Section 10.1.1, Event Free Day Reset.
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4.
MANAGEMENT PRINCIPLES
4.1
Quality Management Principles
Quality management principles are those defined under ISO 9000 Quality Systems standard, and cover the following:
 Customer Focus;
 Leadership;
 Involvement of People;
 Process Approach;
 System Approach to Management;
 Continual Improvement;
 Factual Approach to Decision Making; and
 Mutually Beneficial Supplier Relationships.
These principles are further described in Appendix A, Section A.2.
4.2
Management System Principles
Management system principles are those defined under CSA N286-05 [6]. These principles
together with the required supporting actions, and the documentation that describes them support
the management system.
4.2.1
The Business is Defined, Planned, and Controlled
This principle applies to all aspects of the business and is fundamental to the achievement of
required results at the planning level. It covers the company’s core missions (defined in
Section 5.3) and associated financial objectives, customers, strategic actions and enablers.
This principle is primarily addressed by Process 502000, Define Vision, Strategy and Corporate
Plan, described in Appendix B, Section B.2.
4.2.2
The Organization is Defined and Understood
This principle is covered as part of the management system. The Management System Manual
(this document) and the AMM [1] define the organizational roles and responsibilities at
executive and senior management levels. Other governing documents, including facility
authorization documents, overview documents and plans cover detailed responsibilities and
interfaces.
This principle is primarily addressed by Process 514100, Maintain and Improve Overall
Management System, described in Appendix B, Section B.14.2.
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4.2.3
Personnel are Competent at the Work They Do
This principle applies to all employees and is addressed through a defined hiring process, clear
definition of responsibilities and accountabilities, and training programs. Where required, the
training uses a systematic approach and is developed by those who understand the work.
This principle is primarily addressed by Processes 510100, Manage Staffing, and 510200 Train
and Develop Employees, described in Appendix B, Sections B.10.1 and B.10.2 respectively.
4.2.4
Personnel Know What is Expected of Them
Individuals know what is expected of them and how well they performed against expectation via
a number of channels, including job descriptions, internal communication, procedures, training,
pre-job and post-job briefings, and performance reviews.
This principle is addressed by numerous business processes, including Processes 510100,
Manage Staffing; 510200, Train and Develop Employees; 510700, Manage Employee
Communications; and 514020 Human Performance, described in Appendix B, Sections B.10.1,
B.10.2, B.10.4 and B.14.1 respectively.
4.2.5
Work is Planned
This principle applies to all work. Its application varies with the risks associated with the work
and is achieved through various planning methodologies from long term activities to shop floor
work executions defined in work requests.
This principle is addressed by most business processes, activities and systems such as: corporate
and operational planning, work requests and authorization, work packages and work
management. The main process covering this principle is Process 508238, Work Management.
4.2.6
Experience is Sought, Shared and Used
This principle covers all processes and is addressed from operating experience within AECL and
from the industry. An event reporting system called ImpAct (Improvement Action) is used to
capture issues, unplanned events, internal and external lessons learned and supporting actions.
Management at all levels are involved in reviewing captured information and ensuring staff are
informed. Other means of sharing information include discussions at staff meetings and
myAECL (the company’s Intranet).
This principle is primarily addressed by Process 508750, Provide Operating Experience,
described in Appendix B, Section B.8.13.
4.2.7
Information is Provided in Time to the People Who Need It
Information is needed and used for every process and exists in visible and audible forms.
Ensuring that people who need information get it is accomplished through various means,
including procedures and work instructions; signage such as warnings; drawings; plans; and
various information systems accessed through computers.
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The information for defined activities is usually defined in governing documents such as
procedures and work plans and is also discussed in pre-job briefings.
This principle is addressed by all business processes, in particular their supporting procedural
documents. The primary one that ensures information is managed is Process 511000, Manage
Information and Associated Technology, described in Appendix B, Section B.11.
4.2.8
The Performance of Work is Controlled
Work control is addressed through procedures and plans covering the various stages of controls:
initiation, planning and scheduling, execution and close out.
The performance of work is controlled when the person doing the work has been authorized to
do so, is competent in the work being performed, trained and uses the right procedure and
methodology. Performance is also assured by implementing third-party review and monitoring,
in areas such as radiation protection via radiation surveyors, and in quality via quality control
inspectors.
This principle is addressed by most processes.
4.2.9
The Preparation and Distribution of Documents are Controlled
This principle covers documents to support most processes where unique identification of
documents is required, format is defined, and control is needed for formal review, approval and
distribution. A document management system called TRAK is in place to provide a framework
for managing the required controls for documentation.
This principle is primarily addressed by Process 511300, Manage Information Assets, described
in Appendix B, Section B.11.1
4.2.10
Work Is Verified to Confirm that it is Correct
This principle is applied to prevent errors going undetected by confirming that work meets
requirement. The level of verification and the independence of the verifier depend on the
complexity of the work and its potential risks (e.g., impact on safety, budget and schedule). It
includes verification of documents, verification of design, verification of planned instructions for
activities to be performed, and verification of records demonstrating the acceptability of results.
Verification includes self-checking, co-worker verification, or subject matter expert verification,
a conformity test or an inspection performed by an independent internal or external group
(e.g., quality surveillance or quality control inspector).
This principle is addressed by many processes.
4.2.11
Problems are Identified and Resolved
This principle applies to all work. Staff are encouraged and expected to identify problems,
regardless of significance. Problems are captured through the ImpAct system. The process
includes the use of cause analysis methodologies and capturing and monitoring of actions,
including corrective action with effectiveness reviews.
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This principle is primarily addressed by Process 508750, Provide Operating Experience,
described in Appendix B, Section B.8.13.
4.2.12
Changes are Controlled
This principle applies to numerous processes, in particular where there is a need to limit risks
and costs. Change requests get reviewed and those of more complex or high risk go through a
formal process that includes justification, review, approval and confirmation of effectiveness.
Change control processes cover changes to operational plans, business processes, organization,
engineering (design or physical systems), projects, plant status, documentation, radiation
protection measures and computer codes to name a few.
This principle is addressed by many processes.
4.2.13
Records are Maintained
This principle applies to numerous processes where there is a requirement to demonstrate work
completed, record unplanned events, record discussions and decisions, and record how
requirements have been met. Various storage media are used where retrievability is assured.
The retention time varies, with some records kept permanently, in particular those records
needed to support decommissioning of nuclear facilities. The process in place includes the use
of a record management system called TRAK and other information management systems
housed on computer servers, subject to business recovery plans. Procedures are used to define
the information to be kept as records, including the responsibility for filing the record with the
document control group.
This principle is primarily addressed by Process 511300, Manage Information Assets, described
in Appendix B, Section B.11.1.
4.2.14
Assessments are Performed
This principle applies to all processes. It includes management reviews, self-assessments,
independent assessments and third-party inspections, assessments and audits. Assessments cover
compliance and/or performance.
This principle is addressed by numerous business processes, including Process 514300, Ensure
Compliance with Requirements; Process 514400, Perform Independent Reviews of HSE; and
Process 514500, Conduct Internal Audits and Report on Findings, described in Appendix B,
Section B.14.
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5.
ORGANIZATION OVERVIEW2
5.1
Description
RTO is a science and technology (S&T) organization that operates as part of AECL, a federal
Crown corporation. The principle RTO site is Chalk River Laboratories (CRL), Canada’s largest
federal lab. The integrated laboratory site at Chalk River is home to the unique Canadian
infrastructure that supports the company’s core missions.
The organization employs approximately 3,0003 people including 700 scientists and engineers.
Four hundred staff are based at five other locations in Canada including Whiteshell Laboratory
(WL) in Manitoba, and in the Port Hope offices.
CRL has two operating research reactors and four other reactors in a variety of shutdown
conditions. In addition, the site includes facilities for handling radioactive material, supporting
scientific activities across the range of physics, chemistry, biology and engineering disciplines,
and also includes unique storage facilities for radioactive materials and waste.
The WL site is currently being decommissioned. It does have some operating facilities,
shutdown facilities, facilities at various stages of decommissioning and also still maintains some
R&D programs.
To enable the S&T activities there is a substantial base of people, processes, programs and
infrastructure that ensures safety, security and environmental protection are maintained at
consistently high levels.
5.2
Vision and Mission Statement
The vision for RTO is to be a global partner in nuclear innovation.
The mission statement for RTO is to employ our strengths in people and facilities to advance
nuclear science and technology for the benefit of Canada.
5.3
Management Model
The model used to develop the management plan is shown in Figure 5.1. The plan provides
strategic direction for the organization. There are three core missions for delivering social,
environmental and economic benefits to Canadians. These missions are: Research Development
and Innovation; Isotope Production; and Environmental Management. They are carried out by
staff across the organization, many of whom support more than one mission in the course of their
daily work. In addition, the organization needs to operate efficiently and effectively.
The success of RTO is dependent on the success of the three core missions and of laboratory
operations as follows:
2
3
Information in this section is derived from the Nuclear Laboratories Management Plan, 145-502300-PLA-072
[8].
Number of employees at the time the document was prepared.
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1. Research Development and Innovation: RTO has unique capabilities in people and nuclear
facilities that allow discovery research which is strongly oriented towards the
commercialization of ideas that will benefit Canadian industry.
2. Isotope Production: RTO has unique capabilities for the production of a range of isotopes
used for medical and industrial purposes. Isotopes are the raw materials that sustain two
Canadian companies (MDS Medical and Best Medical International).
3. Environmental Management: RTO has a key national role in the management of legacy
issues in Canada that involve radioactive material, as well as managing the environmental
impact associated with operations.
4. Operations: RTO must operate efficiently, effectively and safely.
The core missions are not organizational groups within RTO (as defined in Section 7). While the
leadership of the missions is provided by the Research & Development, Commercial and
Decommissioning & Waste Management organizational groups, the core missions rely on the
successful integration of all the groups within RTO for their success.
Figure 5-1 Overview of RTO in Management Plan
5.4
Business Planning
The management plan, reference [8], was prepared in support of the corporate plan and includes
strategy maps developed for the following:
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


The three core missions: Research Development & Innovation, Isotope Production and
Environmental Management;
Operations; and
The support groups: Programs and Nuclear Oversight (PNO), Engineering, and business
support from Finance and Business Services (FBS) and Human Resources (HR).
The management plan captures the interdependencies of the core missions, operations and
support groups. It identifies the strategic actions each part of the organization needs to take, the
enabling factors required for success as well as responsible leads for those enablers.
5.5
Performance Management and Reporting
Performance management and reporting is carried out to gather information about the company’s
progress to date versus planned targets and to facilitate management decision-making throughout
the year.
In addition to internal reports, Board of Directors Report and Minister’s Report for NRCan are
also prepared.
5.6
Partners, Customers and other Stakeholders
5.6.1
Research and Development Partners and Customers
There are a number of partners and customers supporting the Research, Development and
Innovation mission. They include the following:
 CANDU Owners Group (COG). The partnership includes participation in joint projects and
programs of common interest to COG members, and supplier of R&D services to COG.
 University Network of Excellence in Nuclear Engineering (UNENE). The partnership
includes supporting educational programs in nuclear science and engineering and funding
and guiding collaborative research projects and funding industrial chairs at various
universities jointly with other UNENE partners.
 Generation IV International Forum (GIF). The partnership includes carrying out R&D
funded by NRCan in support of Canada’s obligation to GIF, leveraging the internal R&D
with NRCan-funded program, representing Canada on GIF committees and working groups,
and providing in-kind support to universities participating in programs funded by
NRCan/NSERC (Natural Sciences and Engineering Research Council of Canada).
 Various universities. The partnership includes funding and supporting collaborative research
and providing funding and in-kind support for the sponsored chairs and research projects.
Partners include Ecole Polytechnique, University of Western Ontario, University of Ontario
Institute of Technology, University of Toronto, University of Waterloo, University of Alberta
and Carleton University.
 International Research Organizations and Universities. The partnership includes
collaborative research, information exchange and in some cases, funding for use of facilities.
Partners include Chinese universities, Korea Atomic Research Institute, US Department of
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Energy, International Nuclear Energy Research Initiative and the International Atomic
Energy Agency.
 Department of National Defence. The partnership includes carrying out R&D funded under
the Chemical, Biological, Radiological-Nuclear Explosive (CNBE) Research and
Technology Initiative (CRTI) aimed at mitigating terrorist attacks.
5.6.2
Emergency Preparedness Partners
Partners supporting emergency preparedness efforts include the following:
 Federal, provincial, and municipal nuclear emergency organizations; and
 Local and regional response agencies.
Emergency preparedness staff collaborates with off-site agencies through the following:
 Participating in nuclear emergency planning committees;
 Maintaining human and material resources to operate off-site emergency centres;
 Maintaining off-site communications with local and regional response agencies;
 Participating in the chemical, biological, radiological, nuclear emergency planning and
exercise meetings; and
 Participating in local emergency worker training.
5.6.3
World Association of Nuclear Operators (WANO) and Institute of Nuclear
Power Operations (INPO)
AECL is currently on a trial membership with WANO, which provides the following:




Access to industry standards, expertise and technical support;
Training, seminars and workshops;
Web site information, guidelines, and operating experience information; and
Networking with industry peers.
AECL also has a trial membership in the INPO International Participants Program.
5.6.4
Other Customers
Customers of the organization’s products and services include:
 MDS Nordion for isotopes produced at NRU;
 Waste generators, such as hospitals and universities, whose radioactive waste is sent to CRL
for disposal;
 Nuclear Waste Management Organization (NWMO) for research associated with long-term
management of Canada's used nuclear fuel;
 SLOWPOKE Research Reactor community; and
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 CANDU power utilities (including Ontario Power Generator, Bruce Power and Point
Lepreau Nuclear Generating Station) and non-CANDU power utilities via AECL’s
Commercial Operations division.
5.6.5
Other Partners and Stakeholders
Other partners include the following:
 The International Nuclear Information System (INIS), a branch of IAEA. The CRL Library
has been the INIS Centre for Canada since 1971, a role designated by the Government of
Canada.
 Port Hope Area Initiative (PHAI) in Port Hope, Ontario. The Government of Canada has
assumed responsibility for the cleanup and long-term safe management of historic low-level
radioactive waste in Port Hope. A project office, with AECL as project proponent, has been
established for the community-initiated environmental remediation project. The project goal
is the cleanup and safe local long-term management of the waste that resulted from radium
and uranium refining done in Port Hope from the 1930s to the 1960s.
 National Research Council (NRC). The partnership with NRC involves providing access to
neutron beam from the NRU reactor for neutron scattering experiments performed by NRC
and the universities for material characterization. NRC experimental facilities are an
important resource for AECL’s R&D for materials investigations.
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6.
NUCLEAR OPERATIONS
6.1
General
RTO is engaged in a broad range of nuclear-related activities at its various sites and operates
facilities that include nuclear reactors, nuclear fuel fabrication facilities, radioactive waste
storage facilities as well as specialized radioisotope laboratories.
The performance and effectiveness of nuclear facilities and the implementation of supporting
processes/programs is assessed by the Nuclear Performance Assurance Review Board, described
in Section 7.4.9.
6.2
Class I and Class II Facilities
All Class I and Class II facilities are listed in site licences and are operated in accordance with
formal documentation, including a safety analysis report and a Facility Authorization document.
The operating limits and conditions within which a facility must be operated are presented in the
individual Facility Authorization. Facility staff are required to operate the facility in accordance
with the approved Facility Authorization, and to meet the requirements of safety set out in any
listed safety analysis report. Company and site governing documents, supplemented by
facility-specific documentation, describe the processes used to achieve safety objectives.
Safe and reliable performance objectives in nuclear facility operations exist from the time of the
conceptual design, through to construction and operation. Assurance is required that components,
systems and subsystems in facilities are capable of performing their required functions in a reliable
manner. The rigour of the various testing programs is dependent on the potential consequences of
failure of the components, systems and subsystems. For example, the testing program for many
facilities is included in standard operating procedures. However, in other facilities, such as reactors,
a separate intensive program of trip-and-alarm and equipment tests is in place. Results of these tests
are closely monitored and are subject to external (to the facility) review.
All testing is carried out according to approved procedures. Test frequencies are selected to
satisfy regulatory and internal requirements.
Annual safety reviews for each facility, are carried out and compiled into a report, as one of the
requirements of the site operating licence, and to assist the SRC in its annual review of nuclear
facilities operations. Events, faults, and modifications significant to facility operation are
reported, as are radiation doses to personnel and any radioactive and hazardous substance
releases to the environment.
6.3
Radioisotope Laboratories
All uses of unsealed radioactive materials that occur outside the nuclear facilities listed in the site
licences are conducted in radioisotope laboratories that are classified as basic, intermediate and
high. These laboratories are classified on the International Atomic Energy Agency
hazard-graded scale of A, B and C that take into account the nature of the operations performed
and the relative toxicity of the radionuclides handled in the laboratories. Individual Radioisotope
Laboratory Protocols for each laboratory document the design elements of the physical
characteristics of the laboratories against regulatory guidelines. In addition, the individual
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radioisotope laboratory protocol specifies the laboratory operating limits and identifies the basis
for maintaining safe operations within each laboratory.
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7.
RESPONSIBILITIES AND ORGANIZATION
This section covers the following:
 The organization structure, outlined in Section 7.1;
 The Nuclear Leadership Team and the specific responsibilities of its members, described in
Section 7.2;
 The general responsibilities of senior management, management and employees, including
responsibilities of some key roles, described in Section 7.3; and
 The committees within the organization, described in Section 7.4.
Additional and specific responsibilities are covered in governing documentation, including
policies, manuals, procedural documents, plans, as well as position descriptions and accountability statements.
Changes to the structure and to responsibilities are subject to an organizational change control
process.
7.1
Organization Structure
The organizational structure of RTO is shown in Figure 7-1.
Senior Vice-President
RTO General Counsel
Principal Scientist
Vice-President and General
Manager Research &
Development
Vice-President and General
Manager Decommissioning &
Waste Management
Vice-President and General
Manager Operations and Chief
Nuclear Officer
Vice-President Commercial
General Manager Programs and
Nuclear Oversight and Chief
Regulatory Officer
General Manager Engineering
and Chief Nuclear Engineer
Manager Human Resources
General Manager Finance &
Business Services
Figure 7-1 Organization Structure
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7.2
Nuclear Leadership Team (NLT)
The NLT provides oversight of operations including activities conducted in support of isotope
productions, research and decommissioning. Members of the team are listed below with their
responsibilities. Section 7.3.1 describes the general responsibilities common to these positions.
7.2.1
Senior Vice-President
The Senior Vice-President leads RTO with responsibility for nuclear technology and obligations,
reactor design technology, advanced technology development as well as overall business
operation and the supporting management system.
7.2.2
Vice-President and General Manager, Operations and Chief Nuclear
Officer
The Vice-President and General Manager, Operations and Chief Nuclear Officer (CNO), is
responsible for the following:
 The safe conduct of licensed activities at CRL including the safe and effective operation of
the Class I nuclear facilities (National Research Universal (NRU) reactor, Dedicated Isotope
Facilities, Molybdenum-99 Production Facility, Nuclear Fuel Fabrication Facility (Buildings
429A/B and 405), Universal Cells, Fuels and Materials Cells and Heavy Water Upgrading
Plant) and non-nuclear facilities under his control;
 Operational and maintenance processes and performance, including work management and
control;


Developing, implementing, and maintaining a sustainable staffing strategy for the
facilities/isotope production stream; and
Isotope supply and the Isotope Supply Reliability Program.
The CNO is designated site licence holder for CRL, and in addition to the responsibility of the
site licence holder in Section 7.3.4, is responsible for the following:
 Authorizing, where required, changes to programs and processes that support the site licences
where such changes affect safe or compliant operation at more than one site; and
 Representing AECL at CNSC meetings on matters relating to organization-wide licensing
matters.
7.2.2.1
General Manager, Isotope Supply Reliability Program
The General Manager, Isotope Supply Reliability Program resides in Operations and is
responsible for the execution of several projects and initiatives focussed on maintaining a
reliable supply of isotopes using existing facilities and processes.
7.2.3
Vice-President and General Manager, Decommissioning and Waste
Management
The Vice-President and General Manager, Decommissioning & Waste Management (D&WM) is
responsible for the following:
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 The safe conduct of licensed activities associated with the facilities at CRL, WL and other
locations within D&WM, including nuclear facilities related to facilities decommissioning,
waste management, and environmental remediation within the organizational unit. These
include the Waste Management Areas and the Waste Treatment Center at CRL;
 Developing and managing the decommissioning and waste management programs;
 Managing waste management facilities and related projects at company sites;
 Nuclear Legacy Liabilities Program, funded by the Government of Canada, to address legacy
responsibilities associated with the Government of Canada and AECL’s operations;
 Low-Level Radioactive Waste Management Office, funded by the Government of Canada, to
address historic wastes at specific sites in Canada;
 Port Hope Area Initiative Management Office, the federal agency declared by the
Government of Canada to implement the Legal Agreement of the Port Hope Area Initiative
on its behalf; and
 Commercial waste management and decommissioning undertakings.
In addition, the Vice-President and General Manager, D&WM is
 The site licence holder for WL with responsibility defined in Section 7.3.4; and
 The licence holder for the Douglas Point, Gentilly-1 and Nuclear Power Demonstration
reactor waste management facilities as well as the Port Hope Project, which includes the
Welcome Waste Management Facility in Port Hope, Ontario.
7.2.4
Vice-President and General Manager, Research & Development
The Vice-President and General Manager, Research & Development (R&D) is responsible for
the following:
 The safe conduct of licensed activities associated with the operation of the radioisotope
laboratories and nuclear facilities within R&D, including the following Class I and II nuclear
facilities: Zero Energy Deuterium (ZED)-2 reactor, Recycle Fuel Fabrication Laboratories,
Health Physics Neutron Generator, CECEUD, Tritium Lab, GC 60, and GB 150C;
 Ensuring the quality and the effective, efficient and economical delivery of the products and
services developed and delivered by R&D;
 Developing and implementing the company-wide R&D programs;
 Overseeing the development and management of the following technological areas: fuel
channels; reactor chemistry and systems; hydrogen and heavy-water technology; safety
technology; fuel and fuel cycles; environmental emissions; health physics; software
performance reactor core technology; and CANDU;
 Administering contracts between AECL and CANDU Owners’ Group (COG), including the
COG budget, business planning for COG programs, and related policy issues; and
 Developing qualified software programs.
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7.2.5
Principal Scientist
The Principal Scientist is responsible for the following:
 Assisting and advising senior management and corporate executives on technical directions,
strategic initiatives, and R&D focus;
 Supporting innovation efforts for advanced technology development, including new designs,
applications and development needs;
 Challenging and reviewing advanced concepts, including technical safety, design, and
performance and risk aspects;
 Providing analysis of, and support to the definition of forward nuclear issues and policies;
 Building partnerships and progressing national and international co-operations, and
supporting business development activities; and
 Building professional leadership and technical credibility.
7.2.6
Vice-President, Commercial
The Vice-President, Commercial is responsible for commercial activities, which include the
following:
 Overseeing and managing the isotope business;
 Working with NRCan and the related industry organizations; and
 Representing AECL on the Association of Imaging Producers and Equipment Suppliers
(AIPES) and on the NEA High Level Group, which work globally on strategies and protocols
to ensure reliability and sustainability of isotope supply to Canada and the global markets.
7.2.7
General Manager, Finance and Business Services
The General Manager, Finance and Business Services is responsible for:
 The financial integrity and strategy of the business;
 Advising senior management on overall long- and short-term strategic issues including
matters related to financial management, performance management strategies,
revenue/market growth strategies, and organization structures;
 Interacting with corporate Finance and Information Technology, and providing support for
corporate-led activities and initiatives;
 Providing financial review, reporting, business-decision support, business advice/strategies,
financial modelling, negotiation support, billing, and routine project/product accounting
activities for RTO;
 The development and execution of supply chain strategies, plans, and programs;
 Ensuring the provision of information assets services, and the development of processes and
procedures to protect, manage, and safeguard records and information assets;
 Ensuring the effective and efficient provision of Information Technology services;
 Establishing an effective strategic business planning process;
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 Overseeing the development and execution of a Business Continuity Program; and
 Establishing and maintaining effective working relationships with community stakeholders in
order to build awareness, understanding, and support for company activities and operations.
7.2.8
General Manager, Programs and Nuclear Oversight, and Chief Regulatory
Officer
The General Manager, Programs and Nuclear Oversight (PNO), is responsible for the following:
 The effective implementation and continued improvement of the programs and processes
required to operate in accordance with regulatory requirements and best practices, including
operating experience, human performance, nuclear criticality safety, radioactive materials
transportation, nuclear materials and safeguards management, emergency preparedness,
environmental protection, radiation protection, dosimetry services, security and fire
protection;
 Independent assessments; and
 Ensuring that performance improvements and organizational learning drive toward
operational excellence.
The Chief Regulatory Officer is responsible for the following:
 Maintaining effective relationships between the organization and regulatory bodies in
AECL’s role as a licensee; and
 Bringing significant regulatory issues to the attention of appropriate senior management and
executive in a timely manner, and advising on strategies to address such issues.
7.2.9
General Manager, Engineering and Chief Nuclear Engineer
The General Manager, Engineering and Chief Nuclear Engineer is responsible for the following:
 Developing, maintaining and providing oversight of the integrated management system, the
pressure boundary program and well as the engineering, safety analysis and licensing
processes;
 Establishing and maintaining quality programs where needed;
 Providing design engineering, safety analyses and licensing services; and
 Establishing and maintaining the project management processes and oversight for projects.
The Chief Nuclear Engineer is responsible for the following:
 Executing Design Authority function for the organization’s facilities, design and licensing
basis and engineering; and
 Conducting technical review and oversight of engineering activities to ensure compliance
with a complete set of design requirements, codes, standards, regulatory requirements,
quality standards and engineering practices.
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7.2.10
RTO General Counsel
The RTO General Counsel is responsible for the following:




Providing legal support and advice to RTO;
Overseeing all engagements with outside legal counsel;
Managing intellectual property resources; and
Providing support for compliance with laws and regulations, including operational elements
of Access to Information and Privacy.
7.2.11
Manager, Human Resources
The Manager, Human Resources, is responsible for the following:
 Providing support in developing and implementing activities to address both immediate and
long-term staffing issues;
 Ensuring effective interaction with human resource staff, management, union, and employee
communities;
 Providing administrative support for items such as pension and benefits provisions,
staffing/recruitment and terminations, and salary administration;
 Supporting recruitment activities in accordance with regulatory requirements, collective
agreements, and company policies, procedures and practices;
 Supporting line management activities through the recruitment process; and
 Supporting staffing initiatives related to succession planning/capability maintenance and
resource forecasting.
NOTE: The Manager, Human Resources reports to the Senior Vice-President, Human
Resources in the corporate office, and indirectly reports to the RTO Senior
Vice-President.
7.3
General Responsibilities
7.3.1
Vice-Presidents and General Managers
Each Vice-President and/or General Manager is responsible for, and leads, an organizational unit
or area of responsibility. In this capacity, they are responsible for the following:
 Demonstrating personal commitment to health and safety and improving safety culture, by
example and leadership, so that safe behaviours and working conditions become part of the
work environment and a condition of employment;
 Ensuring the safety of their staff;
 Evaluating and managing business risks associated with their area of responsibility;
 Developing and monitoring their respective operational business plan;
 Contributing to business unit and corporate business planning, and performance monitoring;
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 Providing for strategic direction, leadership, and support to unit and divisional/department
staff;
 Providing support and direction in developing unit goals and objectives focused on providing
services and/or products for process unit customers/stakeholders;
 Ensuring effective implementation of the management system, including adherence to
supporting program and process requirements in a consistent manner across their unit;
 Reviewing and approving business cases for staff hiring, equipment, and facilities;
 Contributing to maximum operating efficiency through effective financial planning and
monitoring, and the resolution of departmental and divisional issues to ensure fiscal
stewardship;



Executing responsibilities of process owner for processes assigned to them as described in
Appendix B;
Managing the assets and human resources within their respective organizational units; and
Supporting the vision, mission and strategic actions as described in the management plan [8].
7.3.2
Management
Management include Senior Directors, Directors and Managers. They are responsible for the
following:
 Demonstrating personal commitment to health and safety and improving safety culture, by
example and leadership, so that safe behaviours and working conditions become part of the
work environment and a condition of employment;
 Establishing and maintaining a safe and healthy workplace, and ensuring the safety of their
staff;
 Ensuring that their employees, contractors, students and attached staff understand their
responsibility under the Code of Ethics and Business Conduct;
 Managing the performance of their employees by:
- Providing training and development including succession planning; and
- Providing specific feedback and assess employee performance against expectation to
develop and sustain performance;







Performing periodic monitoring (e.g., performing self-assessments) and taking action as
needed to address issues and correct non-compliances;
Providing direction, strategy and alignment to the organization’s vision;
Preparing and managing business plans and supporting scorecards and metrics;
Supporting the accomplishment of work and removing unnecessary obstacles;
Providing communication and reinforcing expectations for high standards of performance;
Ensuring effective implementation of the management system, including adherence to
supporting program and process requirements in a consistent manner across their unit; and
Actively promoting and supporting process improvement initiatives.
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7.3.3
Employees
All employees, including management, are responsible for:


Performing their duties safely and in accordance with instructions and training provided;
Adhering to company policies, process requirements and procedures, including safety
protocols;
 Being sufficiently familiar with the company to understand their specific role and how it
aligns with the overall mandate, and to know from whom they can get help, as well as to
whom they can offer help, identify concerns, and obtain approvals and acceptance of work;
 Understanding how their performance will be measured and expecting and soliciting
feedback;

Actively participating or leading the effort to develop and improve their skills and
performance;
 Carrying out their duties ethically and with integrity;
 Safeguarding the public, the environment, company property, material, and equipment;
 Ensuring commercial integrity when dealing with vendors;
 Using established processes and adhering to procedures in all activities;
 Reporting events, including identifying problems and deficiencies;
 Identifying ways to improve; for example, from “lessons learned” resulting from reviews and
assessments and benchmarking; and
 Demonstrating a questioning attitude.
7.3.4
Site Licence Holders
Site licence holders are responsible and have authority for the safe conduct of licensed activities
at their respective site, including the operation, maintenance and use of the nuclear facilities in
compliance with all applicable codes, standards, laws, regulations and site licence conditions.
Specifically they are responsible for:
 Shutting down for safety reasons facility operations;
 Ensuring the implementation of the management system at their respective site as it relates to
safe operation and compliance with licence requirements;
 Taking site safety, quality, licensing, and technical issues to the Senior Executive level for
resolution where these cannot be resolved at the site;
 Representing AECL at CNSC meetings on matters relating to their respective site;
 Ensuring that conditions and requirements of CNSC licences are communicated to site and
facility management;
 Ensuring that adequate arrangements for responses to all kinds of anticipated operational
occurrences and accident conditions have been made, and that appropriate actions have been
taken to provide for the protection of site personnel, the public, and the environment;
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 Ensuring that arrangements are in place to manage the situations that fall outside normal
operating procedures at their respective site. These arrangements shall ensure that
appropriate controls are maintained and due consideration is given to the safety implications
of the situation; and
 Designating Senior Emergency Officers for managing the response to a site emergency.
7.3.5
Process and Program Management
Managers and senior staff assigned to manage a process or a program (e.g., Process Owners,
Program Authorities and Program Managers) are responsible for:
 Developing and maintaining the business process (or program);
 Ensuring the process or program addresses requirements of applicable codes and standards,
reflects AECL practices and is maintained effectively to meet company business needs;
 Providing interpretations of external requirements and establishing internal processes and
practices necessary to address these;
 Defining internal process or program requirements and supporting procedures and
performance measures;
 Coaching, guiding and facilitating implementation of process requirements, including
providing training and development to support implementation;
 Ensuring process activities interfaces effectively with other processes;
 Reviewing program or process effectiveness, and benchmarking practices and performance
with similar process or programs in other organizations;
 Mediating with external bodies (interpreting and overseeing requirements);
 Maintaining knowledge (awareness of industry practice); and
 Monitoring ongoing performance of the process or program and periodically reporting to the
responsible vice-president and/or general manager on performance and any major
non-compliances and issues.
7.3.6
Facility Management
Managers and senior staff assigned to manage a nuclear facility (e.g., Facility Authorities and
Facility Managers) are responsible for:

Ensuring the overall safe conduct of licensed activities including the operation, maintenance,
and use of the facility;
 Contacting regulatory authorities and the SRC in matters related to facility operations;
 Staffing to facilitate safe and compliant facility operations;
 Ensuring facility operations staff training and development;
 Reporting of unplanned events involving the facility, and implementing applicable corrective
actions;
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 Implementing the operational processes within the facility including preparation, review,
revision, and authorization of the facility-specific procedures;
 Identifying assessment and audit requirements for the facility, facilitating the conduct of the
required assessments and audits, and implementing corrective actions arising from findings;
 Monitoring and periodically reviewing the function and effectiveness of operational
processes, and that of supporting processes (e.g., OSH, RP, Information Management) in the
facility;
 Reviewing and verifying the safe operating envelope and program functions; and
 Ensuring actions from management and staff outside the facility do not impact safety within
the facility.
7.3.7
Senior Quality Representatives and Supporting Staff
Senior Quality Representatives and their supporting staff (e.g., quality assurance specialists,
quality control inspectors, quality surveyors, process and/or program specialists) support the
organization by meeting management system and quality-related requirements. They are
responsible for:
 Assisting with management system and quality-related training, implementation and
improvements, including verifications, audits, program reviews, and self-assessment
activities;
 Assisting with the preparation of governing documentation that support the management
system;
 Establishing and maintaining required quality programs;
 Reviewing quality and quality assurance manuals of external participating organizations,
consultants and contractors, to assess suitability as a supplier;
 Advising on quality and quality assurance codes and standards;




Identifying conditions adverse to quality and reporting these to the appropriate level of line
management, up to the General Manager, Engineering as required;
Providing leadership in continuous improvement initiatives;
Monitoring performance against stated quality objectives and measures; and
Benchmarking industry best practices and evaluating their applicability.
7.4
Committees
A number of committees comprised of executives, senior managers, managers and technical
experts are established to deal with management oversight, planning and issues covering
processes integration, use of information technology, quality and safety.
Terms of reference documents are in place to document the committees’ mandates, memberships
and organizational structures, specific responsibilities, and meeting and reporting requirements.
Refer to reference [2] and/or the Procedure Applet for applicable documents.
In addition to the committees below, there are process and/or working level committees in place.
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7.4.1
Operational Safety Oversight Committee (OSOC)
OSOC provides oversight and monitoring of operational safety and regulatory performance
within the organization ensuring prompt corrective action is taken when the need for
performance improvements are identified. Topics on a standing agenda are program reports on
environmental safety, radiation protection, occupational health and safety, fire safety, OPEX,
criticality safety and business line operational safety reports.
7.4.2
Performance Oversight Committee (POC)
POC provides oversight and monitoring of overall business performance ensuring prompt
management action is taken to correct performance deficiencies and that actions are effective.
Topics on a standing agenda include the RTO scorecard, financial performance and forecast,
human resource report, and business line scorecards (including explanation and recovery actions
to address off-target items and business highlights).
7.4.3
Business Operations Strategy (BOS) Committee
The BOS committee provides a forum for discussion of business issues, strategy discussions,
talent pooling, succession planning, leadership development and other items central to the
long-term sustainable operation of the organization. Items of significance with regard to the
NLT and the Corporate updates are also brought to this forum.
7.4.4
Project Performance Oversight Committee (PPOC)
PPOC provides oversight of projects and monitors the delivery of scope against cost, schedule,
and quality requirements. The committee ensures prompt management action is taken to address
deficiencies in project delivery and to address RTO process deficiencies that affect project
delivery. Topics on a standing agenda include the following: summary of large project cost and
schedule performance; discussion of deficiencies on an exception basis; new and emerging
projects; and generic issues affecting project delivery.
7.4.5
ImpAct Review Board (IRB)
IRB provides oversight of corrective action plans for Significant Level (SL) 1 and 2 issues
arising from the ImpAct process; improvement plans addressing internal audits to ensure the
appropriateness and effectiveness of the corrective actions taken, and responses to CNSC Type 1
Inspections.
7.4.6
Health, Safety, Security and Environment Business Performance Council
(HSSE BPC)
The HSSE BPC provides a forum for AECL’s executives, HSSE senior leaders, subject matter
experts, HSSE committees, line units and HSSE compliance programs to expeditiously identify
HSSE priorities, opportunities, or issues and develop strategies to effectively address them.
NOTE:
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7.4.7
Environmental Panel (EP)
EP is responsible for the overall environmental strategic planning, the management of progress
against the strategic and operational plans, and the monitoring of the environmental aspects of
AECL’s nuclear laboratories and other Canadian sites, consistent with AECL’s policy on the
protection of the Environment. The panel reports to the HSSE-BPC.
7.4.8
Site Safety and Health Committees
Safety and health committees at the various sites are dedicated to the promotion and
improvement of the safety and health of employees and is the principal forum for joint
employee/management consultation and development of solutions on safety and health concerns
in the workplace.
7.4.9
Nuclear Performance Assurance Review Board (NPARB)
The NPARB reviews the performance and effectiveness of nuclear facilities and the
implementation of supporting processes/programs required to achieve operational excellence.
The board monitors the interfaces between facilities and the processes/programs and resolves any
obstacles to effective implementation of identified actions.
7.4.10
Safety Review Committee (SRC)
The SRC is an internal body, independent of line management, which acts on behalf of the Board
of Directors and the President and Chief Executive Officer, through the HSSE-BPC, in matters
of Health, Safety, Security and Environment. The SRC is responsible for providing a high level
of independent oversight and confirming that all HSSE controls are in place, including
independent review of facilities and of products and services developed by RTO.
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BUSINESS PROCESS
8.
The business process model as defined in the AMM [1] includes:
 Processes central to AECL’s operations and mandate that are aimed at meeting external
customers’ needs; business processes 01 to 06; and
 Processes that support the above processes and those that are required to sustain the business;
business processes 07 to 14.
The model, shown in Figure 8-1, is based on the Process Classification Framework developed by
the APQC4 International Benchmarking Clearinghouse.
01
Define vision,
strategy and
corporate
plan
02
Design and
develop
products,
services and
03 projects
Market and
sell products
and services
04
07
Develop and maintain nuclear technology
08
Manage facilities, nuclear laboratories, materials and associated liabilities
09
Manage environmental protection
10
Develop and manage human resources
11
Manage information and associated technology
12
Manage financial resources
13
Manage external relationships
14
Improve organizational performance and manage change
Produce and
deliver
products,
services and
05 projects
Provide
after-sales
customer
support
06
Customer Satisfaction
Customer Needs
Understand
markets and
customers
Figure 8-1 Business Process Model
Appendix B lists and describes the business processes.
8.1
Graded Approach in Processes
Once it is determined that a process applies, the application of process requirements is graded so
as to deploy appropriate resources on the basis of the consideration of the following:
 The significance and complexity of the activity or product;
 The hazard and the magnitude of the potential impacts or risks associate with the safety,
health, environment, security, quality and economic element of the activity or product; and
 The possible consequences if the activity is carried out incorrectly or the product fails.
4
APQC is American Productivity and Quality Centre.
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For example, those activities significant to nuclear safety need more stringent controls and verification than activities with lesser significance.
The grading is guided through a series of questions to enable the determination of the
consequences of inadequate performance or inadequate control of an item, service, or process.
The following are examples of aspects of processes where grading is to be applied:








Type and content of training;
Amount of detail and degree of review and approval of instructions;
Need for and detail of inspections plans;
Degree of in-process reviews and controls;
Requirements for material traceability;
Type and level of detail in procurement documents;
Frequency and types of assessments; and
Records to be generated and retained.
Grading is to be applied to all business processes and their supporting procedures. The selected grading needs to be consistent with the applicable company requirements, codes and standards,
and licence and regulatory requirements.
8.2
Compliance with Requirements
AECL adheres to external requirements in the form of laws, regulations, codes, standards and
contracts and agreements. In addition, some legislation establishes legal regimes AECL may
choose to pursue (e.g., to protect intellectual property by patent or trademark registration), or
standards to which AECL may choose to voluntarily conform, as a matter of policy
(e.g., provincial environmental laws).
Compliance management is performed through business processes, which translate these external
requirements and related internal requirements into operational requirements appropriate for
AECL. Managers responsible for compliance with the various external requirements ensure that
other managers have established proper work procedures and practices and have identified
adequate training so that the work performed complies with applicable requirements.
In some cases, a formal program is established to ensure that AECL meets a specific set of
requirements (e.g., Pressure Boundary, Dosimetry). These programs would normally span more
than one business process.
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9.
GOVERNING DOCUMENTATION
9.1
General
The documentation supporting the management system comprises a set of governing documents
with varying levels of approval authority, scope of application and detail. The governing
documentation hierarchy is shown in Figure 9-1.
Corporate
Plan
Level 1
(Mandate)
Management
System Manuals
(AMM, MS Man, Policies)
Process
Documents
Overview
Documents
(includes QA and
Program Manuals with
references to licences,
regulations and
standards)
Management
Plan
Level 2
(Missions, Goals and
Challenges)
Company and Site
Requirements,
Procedures, and
Instructions
Operational Plans
Local Procedures
Local Plans
(covering: Facility, Projects,
Programs, Processes, Department,
Sites
Planning
Documents
(Resources and Budget)
(covering: Projects Execution, Work,
Production, Improvements, Training,
Workforce, Emergency,
Assessments)
Level 3
Level 4
Reports on Progress, Assessments and Measurements
Records and Evidence
Records
(Demonstrate compliance with plans and requirements)
Figure 9-1 Management System Governing Documentation Hierarchy
9.2
Level 1, Corporate Plan and Management System Manuals
The corporate plan is a strategic document developed in compliance with the Financial
Administration Act (FAA) and the Crown Corporation Corporate Plan, Budget and Summaries
Regulations. It serves as a high level plan directing the activities of the organization, and results
from an in-depth analysis of the company and its environment by the corporation’s senior
management and its board of directors. It commits the corporation to a planned strategic
direction over the planning period of five years. The contents of the corporate plan include an
executive summary, mandate, corporate profile, strategic issues for the planning period,
objectives, strategies and performance measures, and financial statements. The plan also
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includes sections on specific approvals, notification of restricted transactions and land-use plans
and support for Government policies.
The scope and purpose of the management system documents is covered in Sections 1.1 and 1.2,
respectively.
9.3
Levels 2, 3 and 4
The document structure, at Levels 2 to 4, consists of two multi-tiered sets of documents, namely
planning documents, and process documents. Collectively, these documents define all the
requirements, standards, expectations, behaviours, processes, and methodologies that have been
established for the management of all activities in the organization.
9.3.1
Planning Documents
With the mandate defined in the corporate plan, the planning documents starts with the
management plan (Level 2) and further detailed in operational plans (Level 3).
The management plan is used to develop strategies and to define key measures of success at a
high level. It is intended for the board of directors, executives and their direct reports. It includes
governing assumptions, the mission statement and vision, a strategy map, goals and measures
and key challenges and initiatives.
Operational plans are developed for each of the organization’s business lines. The operational
plans establish deliverables, measures and targets. It outlines the actions, resources and budgets
required to execute against the corporate plan and management plan objectives.
Day-to-day work is covered in various planning documents (Level 4) and includes work
requests, improvement plans, training plans, work activities plans, work packages, and project
execution plans (PEP) for major projects. The latter is used to describe the project objectives,
identify the project client and major stakeholders, and delineate the “plan of attack” for
achieving the project objective. It defines the scope, cost, schedule, quality, and other relevant
parameters of the project that will satisfy the requirements as agreed to with the client.
9.3.2
Process Documents
Process documents cover business processes and programs. Overview documents and QA
manuals (Level 2) are supported by procedural documents issued for general use (Level 3), and,
where required, procedural documents issued for local use (Level 4).
Business processes or programs are described in Overview (OV) documents. These documents
cover process/program scope and objectives, external and internal requirements, process owner
and support personnel, pre-requisites (training, facilities and equipment), inputs and outputs, the
main activities and interfaces.
Process supporting documents include the following:
 Requirements (REQ) documents which covers high-level requirements (the WHAT) and
responsibilities;
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 Procedures (PRO) which cover requirements, responsibilities and process (the HOW)
outlining the steps or activities to meet the requirements;
 Governing Documentation Index (GDI) documents which provides an index to supporting
external and internal governing documents; related definitions, acronyms and abbreviations;
training documents and courses; and other related documents and records; and
 Terms of Reference (TOR) documents which cover the mandate of committees or other
groups along with the process that is followed.
Local documents consist of various document types to provide the specific instructions to
follow, the guidance needed to perform the work, and the tools, such as forms and checklists
used by employees, to ensure procedural adherence and to provide the record of work
performed. These include guideline documents, forms, operating instructions, operation
procedures, maintenance procedures and emergency procedures.
9.4
Records
The document structure includes the various documentation and records, which are defined in
individual processes, and support our management activities.
9.5
Local Governing Documentation
9.5.1
Operating Nuclear Facilities
Facility Authorization (FA) documents are in place for Class I and II nuclear facilities to identify
the limits of safe operation (the safe operating envelope) for the facility, which are subject to
acceptance by the SRC and the CNSC under the site licence.
A facility GDI is used to provide a list of governing documents for each nuclear facility. The
GDI ensures that staff working at the facility and those that support the facility have the list of
governing licensing documents and a complete and current list of authorized procedures, which
describe the organization, responsibilities, processes and controls used at the facility. These
procedural documents satisfy various program and licensing requirements including quality
assurance, health, safety, security and environmental programs. At the facility level, operating
instructions are used to append and/or grade company-wide procedures.
Some facilities will have a separate GDI document covering the working level procedures
including operating procedures and manuals, maintenance procedures, orders to operate, valve
slips, instructions to staff, etc.
Existing facility Conduct of Operations (COP) procedures are consolidated with other applicable
procedures, operating instructions and licensing documents in the GDI.
9.5.2
Radioisotope Laboratories
Radioisotope Laboratory Protocol (RLP) documents are used to accomplish the following:
 Ensure the safe operation of a radioisotope laboratory and control of radiation exposures due
to operation of the laboratory;
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 Describe the radiological hazards of the authorized activities and document the requirements,
processes, practices, procedures, and radiation protection expectations of laboratory users for
a particular laboratory;
 Define the operating limits and conditions for activities involving radioactive material in an
individual laboratory; and
 Provide generic good practices for radioisotope laboratories.
RLP documents also cover requirements of other safety areas, including emergency
preparedness, environmental protection, physical security, nuclear safety, criticality safety and
occupational safety and health.
9.5.3
Departments
Departments are defined in Organizational documents (ORG). These documents, which are
issued at the organizational level, or at the Division/Branch level, describe the management
structure and specific roles, responsibilities and objectives. They may include a list of
departmental requirements and procedures and/or governing documents where appropriate.
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10.
MEASUREMENT, ASSESSMENT AND IMPROVEMENT
10.1
Measurements
10.1.1
Event Free Day Reset
The Event Free Day Reset (EFDR) is the primary metric used to identify, track and trend
significant human performance events and communicate the results quickly through all levels of
the organization. This indicator reflects the effectiveness of management in reducing errors,
improving organizational processes and activities to reduce the significance and frequency of
human performance events.
The declaration of an EFDR is made when an event occurs as a result of significant human
performance error and when specific criteria are met. The criteria are aligned to the nuclear
industry standards and applied consistently across RTO to allow performance comparisons and
benchmarking. Event groups include nuclear safety, personal and industrial safety, radiological
safety and environment, facility operation and regulatory action.
EFDR is covered by Process 514020, Human Performance described in Appendix B,
Section B.14.1.
10.1.2
Scorecard Measures
A measure definition document is prepared that includes each measure listed on business line
scorecards and is completed once the measures are identified during the operational plan process.
Each measure is assigned a lead organization. Measures are subject to regular monthly
performance reporting against targets. Changes to measures are subject to a change control
process and approval prior to implementation.
10.2
Assessments
10.2.1
Self-Assessments
Self-assessments are used to confirm that work activities meet the requirements of the
management system and to identify areas for improvement to ensure business goals are met.
They are also used to confirm compliance with requirements, assess the effectiveness of the
process/program and its implementation, assist in identifying strengths and concerns, and assist
in measuring the overall performance of activities and operations under the manager’s
responsibility.
Managers are responsible for establishing the frequency and nature of self-assessments for
activities under their responsibility through consultation with program and business process
managers.
10.2.2
Audits
Audits verify compliance to applicable standards/codes and typically also assess effectiveness
through performance-based assessment. The purpose of audits is the following:
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


To evaluate compliance with the requirements of the management system and applicable
regulatory codes and standards;
To assess the status of implementation and effectiveness of performance; and
To identify improvement opportunities.
In addition, reactive audits/assessments are performed as required to address immediate safety
issues or business needs. These assessments are usually reactive in nature and require an
expeditious deliverable.
10.2.3
Program and Process Reviews
Program reviews are performed to assess the program for its suitability, adequacy and
effectiveness to meet current and future business needs. It assesses strengths and weaknesses of
the program for the specified time interval and makes recommendations for improvement. In
addition to program reviews a number of business process reviews are conducted. These have a
broader management system focus, and integrate quality, environmental, financial and other
inputs.
10.2.4
External Assessments
AECL is also subject to external assessments and audits, such as those conducted by the Auditor
General of Canada, the Special Examiner, the CNSC, the International Atomic Energy Agency
(IAEA), Technical Standards and Safety Authority (TSSA), International Organization for
Standardization (ISO) Registrars as well as external customers.
10.2.5
Other Assessments and Management Oversight
Standing committees are established to perform assessments and management oversight. Refer
to Section 7.4 on Committees.
10.3
Improvements
Improvement opportunities are identified through audits, root and apparent cause analysis
results, review of operating experience (internal and external), lessons-learned bulletins, and
adverse trends identified through the ImpAct process. In accordance with the ImpAct process,
each item is reviewed through line management and corrective actions are assigned to address
the issues. This includes opportunities to improve the management system implementation at the
department level.
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11.
REFERENCES
NOTE: Unless otherwise indicated, the references below are for the latest released revision of
the document.
[1]
[2]
[3]
[4]
[5]
[6]
[7]
[8]
CW-514000-MAN-002, AECL Management Manual, Revision 2.
145-514100-GDI-001, Management System Governing Documentation Index.
145-514100-GDI-002, Sites and Facilities Governing Documentation Index.
145-514100-016-000, Management System Contact and Responsibility List.
CAN/CSA ISO 9001:08 (ISO 9001:2008) Quality management systems –
Requirements.
CSA N286-05, Management system requirements for nuclear power plants.
WANO GL 2006-02, Principles for a Strong Nuclear Safety Culture.
145-502300-PLA-072, Nuclear Laboratories Management Plan Summary.
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Appendix A
Principles
This appendix covers safety principles in Section A.1 and quality management principles in
Section A.2.
A.1
Safety Principles
The wording describing the principles in this section is exactly as found in WANO GL 2006-02,
Principles for a Strong Nuclear Safety Culture [7]. The following interpretations are utilized:
the Canadian spelling is used; Nuclear safety is to mean safety in general; and Station is to mean
facility.
Also, Section A.5 applies to NRU. For other nuclear facilities, the three critical safety functions
are radiation protection, contamination control and criticality control.
Attributes for the principles are covered in [7].
1)
Everyone is Personally Responsible for Nuclear Safety
Responsibility and authority for nuclear safety are well defined and clearly understood.
Reporting relationships, positional authority, staffing, and financial resources support nuclear
safety responsibilities. Corporate policies emphasize the overriding importance of nuclear
safety.
2)
Leaders Demonstrate Commitment to Safety
Executive and senior managers are the leading advocates of nuclear safety and demonstrate their
commitment both in word and action. The nuclear safety message is communicated frequently
and consistently, occasionally as a stand-alone theme. Leaders throughout the nuclear
organization set an example for safety.
3)
Trust permeates the Organization
A high level of trust is established in the organization, fostered, in part, through timely and
accurate communication. There is a free flow of information in which issues are raised and
addressed. Employees are informed of steps taken in response to their concerns.
4)
Decision-Making Reflects Safety First
Personnel are systematic and rigorous in making decisions that support safe, reliable plant
operation. Operators are vested with the authority and understand the expectation, when faced
with unexpected or uncertain conditions, to place the plant in a safe condition. Senior leaders
support and reinforce conservative decisions.
5)
Nuclear Technology is Recognised as Special and Unique
The special characteristics of nuclear technology are taken into account in all decisions and
actions. Reactivity control, continuity of core cooling, and integrity of fission-product barriers
are valued as essential, distinguishing attributes of the nuclear station work environment.
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6)
A Questioning Attitude is Cultivated
Individuals demonstrate a questioning attitude by challenging assumptions, investigating
anomalies, and considering potential adverse consequences of planned actions. This attitude is
shaped by an understanding that accidents often result from a series of decisions and actions that
reflect flaws in the shared assumptions, values, and beliefs of the organization. All employees
are watchful for conditions or activities that can have an undesirable effect on plant safety.
7)
Organizational Learning is Embraced
Operating experience is highly valued, and the capacity to learn from experience is well
developed. Training, self-assessments, corrective actions, and benchmarking are used to
stimulate learning and improve performance.
8)
Nuclear Safety Undergoes Constant Examination
Oversight is used to strengthen safety and improve performance. Nuclear safety is kept under
constant scrutiny through a variety of monitoring techniques, some of which provide an
independent “fresh look”.
A.2
Quality Management Principles
A.3
Customer Focus
This principle is expressed as follows:
Organizations depend on their customers and therefore should understand current and future
customer needs, should meet customer requirements and strive to exceed customer
expectations.
Benefits from this principle include the following: increased revenue and market share obtained
through flexible and fast responses to market opportunities; increased effectiveness in the use of
the organization’s resources to enhance customer satisfaction; and improved customer loyalty
leading to repeat business.
This principle means that the organization needs to be customer-focused. Customer focus is also
about satisfying needs rather than wants.
This principle is primarily addressed by Processes 501000, Understand Markets and Customer;
503000, Develop and Design Products, Services or Projects; 504000, Market and Sell Products
and Services; 505000, Produce, Build, Modify and Deliver Products, Services or Projects; and
506000, Provide After-sales Customer Support, described in Appendix B, Sections B.1, B.3, B.4,
B.5 and B.6 respectively.
A.4
Leadership
This principle is expressed as follows:
Leaders establish unity of purpose and direction of the organization. They should create and
maintain the internal environment in which people can become fully involved in achieving
the organization’s objectives.
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Benefits from this principle include the following: people will understand and be motivated
towards the organization’s goals and objectives; activities are evaluated, aligned and
implemented in a unified way; and miscommunication between levels of an organization will be
minimized.
This principle is primarily addressed by Processes 510100, Manage Staffing; and 510200, Train
and Develop Employees, described in Appendix B, Sections B.10.1 and B.10.2 respectively.
A.5
Involvement of People
This principle is expressed as follows:
People at all levels are the essence of an organization and their full involvement enables
their abilities to be used for the organization’s benefit.
Benefits from this principle include the following: motivated, committed and involved people
within the organization; innovation and creativity in furthering the organization’s objectives;
people being accountable for their own performance; and people eager to participate in and
contribute to continual improvement.
This principle is addressed by most business processes.
A.6
Process Approach
This principle is expressed as follows:
A desired result is achieved more efficiently when activities and related resources are
managed as a process.
Benefits from this principle include the following: lower costs and shorter cycle times through
effective use of resources; improved, consistent and predictable results; and focused and
prioritized improvement opportunities.
This principle is primarily addressed by Process 514200, Prescribe Quality Requirements and
Improve Business Processes, described in Appendix B, Section B.14.2.
A.7
System Approach to Management
This principle is expressed as follows:
Identifying, understanding and managing interrelated processes as a system contributes to
the organization’s effectiveness and efficiency in achieving its objectives.
Benefits from this principle include the following: integration and alignment of the processes
that will best achieve the desired results; ability to focus effort on the key processes; and
providing confidence to interested parties as to the consistency, effectiveness and efficiency of
the organization.
This principle is primarily addressed by Process 514100, Maintain and Improve Overall
Management System, described in Appendix B, Section B.14.2.
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A.8
Continual Improvement
This principle is expressed as follows:
Continual improvement of the organization’s overall performance should be a permanent
objective of the organization.
Benefits from this principle include the following: performance advantage through improved
organizational capabilities; alignment of improvement activities at all levels to an organization’s
strategic intent; and flexibility to react quickly to opportunities.
This principle is primarily addressed by Process 514000, Improve Organizational Performance
and Manage Change, described in Appendix B, Section B.14.
A.9
Factual Approach to Decision Making
This principle is expressed as follows:
Effective decisions are based on the analysis of data and information.
Benefits from this principle include the following: informed decisions; an increased ability to
demonstrate the effectiveness of past decisions through reference to factual records; and
increased ability to review, challenge and change opinions and decisions.
This principle is addressed by most business processes.
A.10
Mutually Beneficial Supplier Relationships
This principle is expressed as follows:
An organization and its suppliers are interdependent and a mutually beneficial relationship
enhances the ability of both to create value.
Benefits from this principle include the following: increased ability to create value for both
parties; flexibility and speed of joint responses to changing market or customer needs and
expectations; and optimization of costs and resources.
This principle is primarily addressed by Process 505210, Perform Procurement and Materials
Management, described in Appendix B, Section B.5.1.
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Appendix B
Business Processes
This appendix provides an overview of Tier 1 business processes, lists lower tier processes and
includes a brief description of processes, in particular, those that support the requirements of
CSA N286-05, and licences issued by the CNSC. Descriptions of other lower tier processes will
be added in future revisions.
The organization unit listed is responsible for the process, or is the contact for the process where
the process responsibility is with AECL Corporate office or with the Commercial Operations
division.
For process supporting governing documents refer to document 145-514100-GDI-001,
Management System Governing Document Index [2].
B.1
Process 501000, Understand Markets and Customers
This business process consists of processes and activities associated with understanding the
markets and customers. It includes determining customer needs and wants; measuring customer
satisfaction; monitoring changes in market or customer expectations; and understanding
competition market intelligence.
ASI
#
Process Name
501000
501100
501200
501300
501400
01
Understand Markets and Customers
01.1
01.2
01.3
01.4
Determine Customer Needs and Wants
Manage and Maintain Marketing Information
Identify and Qualify Potential Customers
Measure Customer Satisfaction
B.2
Process Owner
Commercial
Process 502000, Define Vision, Strategy and Corporate Plan
This business process consists of processes and activities associated with developing a vision, a
strategy, and a corporate plan. It includes monitoring the external environment; defining the
business concept and AECL’s strategy; developing the business plan, and managing business
intelligence.
ASI
#
Process Name
Process Owner
502000
502100
502200
502300
02
02.1
02.2
02.3
Define Vision, Strategy and Corporate Plan
Define Vision, Objectives and Strategy
Define Corporate Plan
Manage Planning Process
Finance and Business Services
502400
502500
02.4
02.5
Monitor and Report Corporate Performance
Ensure Business Continuity
 Office Business Recovery
 Plant Business Recovery
Provide Executive Crisis Management
502600
02.6
145-514100-MAN-001 2010/09/23
Finance and Business Services
Programs and Nuclear Oversight
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-2
Rev. 0
Process 503000, Develop and Design Products, Services or Projects
B.3
This business process consists of processes and activities in support of New Build Projects, and
in support of Products and Services provided to external customers.
For design, engineering and project processes for RTO, refer to Process 508100, Provide
Facilities and Support to Existing Facilities.
ASI
#
Process Name
503000
03
Design and Develop Products, Services and Projects
503100
03.1
503200
03.2
New Build Projects - Develop Reactor Concept
and Product, Risk assessment, Environmental
Assessment, Safety and License Basis and Plan
Products/Services - Develop and Design
Products and Services
B.4
Process Owner
Engineering
Process 504000, Market and Sell Products and Services
This business process consists of processes and activities associated with marketing and selling
products and services. It includes marketing products or services to relevant customer segments;
marketing communication materials; assessing business risks; establishing alliances with other
parties; preparing proposals; negotiating contracts and processing customer orders.
ASI
#
Process Name
504000
504100
504200
504300
504400
504500
504600
04
04.1
04.2
04.3
04.4
04.5
04.6
Market and Sell Products and Services
Marketing Products and Services
Generate Sales Opportunities
Establish Alliances
Prepare Proposals
Assess Sales Risks
Negotiate Sales Contracts (include project
financing)
B.5
Process Owner
Commercial
Process 505000, Produce, Build, Modify and Deliver Products, Services or
Projects
This business process consists of processes and activities associated with producing and
delivering products and services. For RTO, this process covers construction, commissioning and
procurement activities. Note that project management is covered in business process 508110,
Provide Project Management.
ASI
#
Process Name
505000
05
05.1
05.2
05.2.1
Produce and Deliver Products, Services and Projects
505100
505200
505210
145-514100-MAN-001 2010/09/23
Plan and Manage Projects (Project Management)
Build Products or Services and Execute Projects
Perform Procurement and Materials
Management
Process Owner
Refer to Process 508110
Engineering
Finance and Business Services
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-3
Rev. 0
ASI
#
Process Name
Process Owner
505220
05.2.2
05.2.3
05.2.4
Manage Detailed Design Engineering
Manage Fabrication / Manufacturing
Manage Construction / Installation
Manage Commissioning / Testing
Manage Operations
Handover Plant or Deliver Product / Service to
Customer
Refer to Process 508120
Refer to Process 508240
Operations
Operations
Refer to Process 508220
505230
505240
505250
505260
505300
05.2.5
05.2.6
05.3
B.5.1
Various
Process 505210, Perform Procurement and Materials Management
This process covers procurement activities, including approval of suppliers; generating
tender/request for quotation documents; administering the bidding process; commercial, quality
assurance and engineering evaluations; negotiating terms, conditions and pricing of purchase
orders; awarding purchase orders; ensuring execution of the contract; and making customs and
shipping arrangements.
B.5.2
Process 505240, Manage Construction and Installation
This process covers construction activities from the receipt of components and material on the
construction site to their installation in systems and/or structures, as required by drawings of
other formal engineering information. It also covers support activities and equipment, and
applies to all stages at the construction site up to and including the installation and testing of
components or systems and turnover to Commissioning.
B.5.3
Process 505250, Manage Commissioning and Testing
This process covers commissioning activities to ensure thorough testing that each component,
subsystem, system or structure in a facility will be capable of fulfilling its design requirements
throughout its design life. The process execution will demonstrate that all the functional, control
and performance criteria for the system are met, as specified in the design and will prepare the
facility to operate within the safety parameters as described in the design specifications. The
process covers the turnover to Operations.
B.6
Process 506000, Provide After-Sales Customer Support
This business process consists of processes and activities associated with post-order customer
support. The process includes billing the customer, providing after-sales service, responding to
customer inquiries, and post-order customer feedback.
ASI
#
Process Name
506000
06
Provide After-Sales Customer Support
506100
506200
06.1
06.2
06.3
Bill the Customer
Provide After Sales Services
Respond to Customer Inquiries
506300
145-514100-MAN-001 2010/09/23
Process Owner
Commercial
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-4
Rev. 0
Process 507000, Develop and Maintain Nuclear Technology
B.7
This business process consists of processes and activities associated with managing the
technology to support our products and services. The process includes evaluating and improving
current technology; identifying, developing and demonstrating new technology; documenting
current learning for future use; managing technical resources, both physical and human; and
managing the technology portfolio.
ASI
#
Process Name
Process Owner
507000
507100
507200
507230
07
07.1
07.2
07.2.3
Research & Development
507300
507320
07.3
07.3.2
Develop and Maintain Nuclear Technology
Plan Technology Development Activities
Develop Technology
Develop Analytical, Scientific and Design
Software
Maintain and Secure Technology
Manage Intellectual Property
B.8
RTO General Counsel
Process 508000, Manage Facilities, Nuclear Laboratories, Materials and
associated Liabilities
This business process consists of processes and activities associated with managing facilities,
nuclear laboratories, materials and associated liabilities. The process includes managing licensed
nuclear sites; managing material and services; managing non-nuclear sites and offices; managing
physical risk and loss prevention.
ASI
#
Process Name
508000
508100
08
08.1
508110
508120
508130
508110
508200
08.1.1
08.1.2
08.1.3
08.1.4
08.2
508210
508220
508230
08.2.1
08.2.2
08.2.3
508240
08.2.4
508300
508400
508500
508510
508520
08.3
08.4
08.5
08.5.1
08.5.2
Manage Facilities, Nuclear Laboratories, Materials and Liabilities
Provide Facilities and Support to Existing
Facilities
Provide Project Management Office Services
Engineering
Provide Design and Engineering
Engineering
Configuration Management
Engineering
Management of Pressure Boundary System
Engineering
Operate and Maintain Facilities and Nuclear
Operations
Laboratories
Operate Sites
Operations
Operate Facilities
Operations
Provide Maintenance (for site and facility
Operations
operations)
Provide Manufacturing and other Support
Operations
(for site and facility operations)
Decommission Sites and Facilities
Decommissioning & Waste Mgmt
Manage and Maintain Offices and Buildings
Operations
Manage Materials
Finance and Business Services
Manage Nuclear Materials and Safeguards
Programs and Nuclear Oversight
Manage Transportation of Radioactive Materials
145-514100-MAN-001 2010/09/23
Process Owner
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-5
Rev. 0
ASI
#
Process Name
508530
508540
508550
508600
508700
508710
508720
508730
508740
508750
508760
08.5.3
08.5.4
08.5.5
08.6
08.7
08.7.1
08.7.2
08.7.3
08.7.4
08.7.5
08.7.6
Manage non-nuclear materials
Manage Services
Provide Nuclear Criticality Safety Control
Manage Wastes
Manage Operational Risks and Liabilities
Provide Physical Security
Provide Fire Protection
Provide Emergency Preparedness
Provide Radiation Protection
Provide Operating Experience
Provide Licensing Services
508770
08.7.7
508790
508800
08.7.9
08.8
508810
508810
08.8.1
08.8.2
Provide Safety Analysis and Operational
Safety Assessment
Provide Dosimetry Services
Manage Physical Liabilities (Radiological
and Chemical)
Manage Legacy Liabilities (AECL sites)
Manage Historic Liabilities (non-AECL
sites)
B.8.1
Process Owner
Finance and Business Services
Programs and Nuclear Oversight
Decommissioning & Waste Mgmt
Decommissioning & Waste Mgmt
Programs and Nuclear Oversight
Programs and Nuclear Oversight
Programs and Nuclear Oversight
Programs and Nuclear Oversight
Programs and Nuclear Oversight
Programs and Nuclear Oversight and
Engineering
Engineering
Programs and Nuclear Oversight
Decommissioning & Waste Mgmt
Process 508120, Provide Design and Engineering
This process covers all aspects of the design work including conceptual studies, preliminary and
detailed design, and design support work required for licensing, procurement, fabrication,
construction, installation, testing, commissioning, operation, maintenance, and decommissioning
of nuclear safety and safety-related systems. It also includes change control process.
B.8.2
Process 508220, Operate Facilities
This process covers activities to safely operate facilities. Activities include: verification of
work; identification and labelling of systems and components; plant status control; operator
surveillance and surveillance testing; preparation of operating procedures and manuals; and,
infrequently preformed operations.
B.8.3
Process 508230, Provide Maintenance
This process covers maintenance activities needed for the safe operation of all structures,
systems and components on site. The process supports safe, uniform, effective and efficient
maintenance activities, and is designed to ensure all facilities can be operated within framework
that meets all regulatory, codes and licence requirements.
B.8.4
Process 508300, Decommission Sites and Facilities
This process ensures that decommissioning activities for facilities including sites, associated
structures and systems, are funded, planned, prepared, executed and completed, in accordance
145-514100-MAN-001 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-6
Rev. 0
with appropriate specification, throughout the life cycle of the facility, until the final end-state
objectives are met and requirements satisfied.
B.8.5
Process 508510, Manage Nuclear Materials and Safeguards
This process covers nuclear materials and safeguards management activities. It ensure that
activities involving the procurement and receipt of radioisotopes and radiation sources, and the
procurement, receipt, disposition, transfer, accounting, safeguards management, storage and
inventory management of nuclear materials are performed in a manner that protects the workers,
the public and the environment; and ensure compliance with applicable regulatory and license
requirements.
B.8.6
Process 508520, Manage Transportation of Radioactive Materials
This process covers the off-site transport of radioactive material activities and practices. It
ensures the protection of persons, property and the environment from the effects of radiation
during the transport of radioactive material by establishing and maintaining requirements and
processes necessary to facilitate the safe transport of radioactive material to and from AECL sites
in accordance with regulatory requirements.
B.8.7
Process 508550, Provide Nuclear Criticality Safety Control
This process integrates the necessary nuclear criticality safety principles and practices into
activities that could affect the use, process, movement, storage and disposal of fissionable
materials or the consequences of failures in the use, process, movement and storage of
fissionable material. Process activities ensure compliance with applicable site licence
requirements, the proper handling of fissionable material to reduce or eliminate the potential of a
nuclear criticality accident, that the use, handling, movement and storage of fissionable materials
are controlled; and that adequate provisions are made to protect all persons, property and
environment from the effects of a nuclear criticality accident.
B.8.8
Process 508600, Manage Wastes
This process ensures that activities involving planning for, handling, processing, transporting,
storage and disposal of radioactive and non-radioactive wastes are performed in a manner that
protects the workers, the public, and the environment, and are in compliance with applicable
regulatory and licence requirements.
B.8.9
Process 508710, Provide Physical Security
This process ensures the physical protection of assets, safeguarding of the public and personnel.
The process activities provide a safe work environment for employees; an on-site security force,
physical security of nuclear facilities and non-nuclear sites, and site access control where
required. It includes protection of Category I, II and III nuclear materials and ensures security
systems integrity, operability and reliability.
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145-514100-MAN-001 Page B-7
Rev. 0
B.8.10
Process 508720, Provide Fire Protection
This process covers fire protection activities. These activities protect life, prevent fire losses and
degradation of fire protection coverage, provide responsible fire protection and change control
that enhances fire protection, demonstrate compliance to applicable fire protection codes and
standards, and provide reliable facilities from a fire protection perspective. It includes risk
management, fire suppression, fire protection screening process and fire hazard analysis.
B.8.11
Process 508730, Provide Emergency Preparedness
This process consists of activities to ensure a state of readiness to mitigate the effects of an
emergency/abnormal situation in order to protect the health and safety of workers, the public,
and the environment; prepare employees for emergency responses through training,
documentation, exercises and drills, establish liaison and coordination with federal, provincial
and municipal officials, and establish emergency plans and procedures for the mitigation of
harmful effects of emergencies.
For CRL and WL, site specific emergency preparedness documentation specifies how major
emergencies will be managed, including a definition of emergency conditions, designation of a
Site Emergency Officer (SEO) to manage emergency response, and appropriate response
procedures. During a defined site emergency, normal lines of responsibility and authority for
personnel and resources are temporarily suspended and the SEO has all the requisite authority to
manage the emergency effectively. SEOs are assigned and authorized by the most senior site
authority management position.
B.8.12
Process 508740, Provide Radiation Protection
This process ensures the protection of workers and the members of the public from harmful
effects of radiation exposure. Activities are in place to control occupational and public exposure
by keeping individual doses below regulatory limits, avoiding unplanned exposures, keeping
individual risk from lifetime radiation exposure to an acceptable level, and keeping collective
doses As Low As Reasonably Achievable (ALARA), social and economic factors taken into
account. It also includes preventing the uncontrolled release of contamination or radioactive
materials from the nuclear sites through the movement of employees and materials.
B.8.13
Process 508750, Provide Operating Experience
This process utilizes information both from within AECL and from external sources to improve
the safety of operations, improve operational performance, and reduce the significance and the
occurrence of unplanned events at AECL Canadian sites. It includes the identification and
investigation of unplanned events, determination of corrective actions, internal notification of
stakeholders, trending and information sharing, both internally and with the nuclear industry in
general.
B.8.14
Process 508760, Provide Licensing Services
This process consist of the following licensing services: producing licensing documents,
supporting the licence applications and approval requests to CNSC staff and the Commission,
145-514100-MAN-001 2010/09/23
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145-514100-MAN-001 Page B-8
Rev. 0
preparing licence renewal and amendment and new licence applications, and providing licensing
advice to management and staff.
B.8.15
Process 508770, Provide Safety Analysis and Operational Safety
Assessment
This process ensures that sites and facilities are safe-by-design, both the initial design and
subsequent changes, and that the sites and facilities remain safe to operate. The main activities
include safety design engineering, operational safety assurance, safety analysis, and site safety
management.
B.9
Process 509000, Manage Environmental Protection
This business process consists of processes and activities associated with the protection of the
environment for operations at AECL’s Canadian sites as well as for provision of products and
services provided to customers.
ASI
#
Process Name
509000
09
Manage Environmental Protection
509100
09.1
509200
09.2
509300
09.3
Provide Corporate Environmental
Management Strategy
Provide Environmental Protection Program
for AECL Operations
Provide Environmental Protection Program
for Products and Services
B.9.1
Process Owner
Programs and Nuclear Oversight
Process 509200, Provide Environmental Protection Program
This process implements the environment policy and ensures compliance with legal and other
environmental requirements. The activities are aimed at preventing environmental protection
degradation (includes pollution prevention) and at providing responsible environmental
management. Activities include reporting on environmental performance and environmental
issues, identifying environmental aspects of activities, products and services and ensuring that
those that have or can have significant impacts on the environment are carried out under
specified condition by establishing, implementing, maintaining procedures to control
environmental risks.
B.10
Process 510000, Develop and Manage Human Resources
This business process consists of processes and activities associated with developing and
managing our human resources. The process includes creating human resources strategy;
recruiting employees; educating and training employees; assessing employee performance and
rewarding employees; ensuring employee safety, well-being and morale; and managing
employee relations.
145-514100-MAN-001 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-9
Rev. 0
ASI
#
Process Name
510000
10
Develop and Manage Human Resources
510100
510200
10.1
10.2
10.3
10.4
10.5
10.6
10.7
Manage Staffing
Train and Develop Employees
Assess and Reward Employee Performance
Ensure Employee Safety & Well-being
Manage Relations with Employees
Manage Employee Security
Manage Employee Communications
510300
510400
510500
510600
510700
B.10.1
Process Owner
AECL HR (Manager, HR Services CRL &
WL)
Programs and Nuclear Oversight
Finance and Business Services
Process 510100, Manage Staffing
This process covers activities to support staff hiring, employment equity, workplace
accommodation, work transfer, and the preparation of accountability statements and position
descriptions.
B.10.2
Process 510200, Train and Develop Employees
The process covers activities to support a systematic approach to training used to train personnel
to perform duties and execute responsibilities in a safe and competent manner. The main
activities comprise training-needs analysis, training design and development, conducting
training, evaluating training, validating training, preparation of training plans, qualification of
trainers, training records and controlling changes to training.
B.10.3
Process 510400, Ensure Employee Safety and Well-being
This process covers activities to protect the safety and health of employees, contractors and
visitors. It includes analyzing safety and health risks associated with operations, workplace
inspections, incident and injury investigations, industrial hygiene support, provision of health
services, and ensuring compliance to applicable codes and standards.
B.10.4
Process 510700, Manage Employee Communications
This process ensures employees are informed. Activities include managing content on the
company’s internal website “myAECL”, preparing and issuing monthly internal staff
newsletters, providing support on mission-based communications, facilitating executive quarterly
all-staff communications, facilitating tours and events at the site, managing general
communication of performance objectives, and support other groups in meeting their
communications objectives.
B.11
Process 511000, Manage Information and Associated Technology
This business process consists of processes and activities associated with managing information
and supporting technology. Managing information consists of those activities that directly
handle the information, and managing the technology consisting of providing the computing
services and developing and managing the application systems.
145-514100-MAN-001 2010/09/23
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-10
Rev. 0
ASI
#
Process Name
511000
11
Manage Information and Associated Technology
511100
11.1
511200
11.2
511300
511400
11.3
11.4
511500
11.5
Design, Implement and Maintain Systems for
Software, Hardware and Network Systems
Design, Implement and Maintain Information
Systems
Manage Information Assets
Provide Security of IT Infrastructure and of
Information Assets
Provide Desktop Support Services
B.11.1
Process Owner
Finance and Business Services
Process 511300, Manage Information Assets
This process covers activities that ensure the integrity of information. Activities include records
management including process for numbering records, records retention and disposition and
off-line storage of electronic data; document control including production and control of
documents and drawings using TRAK; document review and comment; management of
documentation liens; and acronyms, abbreviations and definitions of terms.
B.12
Process 512000, Manage Financial Resources
This business process consists of processes and activities associated with managing our financial
resources. The process includes managing financial resources; processing finance and
accounting transactions; reporting financial data; managing the tax function; and managing
financial risks.
ASI
#
Process Name
512000
12
Manage Financial Resources
512100
512200
512300
512400
512500
12.1
12.2
12.3
12.4
12.5
512600
12.6
Prepare Annual Budget
Process Financial and Accounting Transactions
Report Financial Information
Manage Tax Functions
Manage Financial Assets (to include both cash
and capital assets)
Manage Non-Sales Risks
B.13
Process Owner
Finance and Business Services
Process 513000, Manage External Relationships
This business process consists of processes and activities associated with managing external
relationships. The process includes communicating with the shareholder; managing government
and regulatory relationships; managing partner relations; developing public relations program;
interfacing with the Board of Directors; developing community relations; managing legal issues;
and managing international relationships.
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145-514100-MAN-001 Page B-11
Rev. 0
ASI
#
Process Name
513000
13
Manage External Relationships
513100
513200
13.1
13.2
513300
513400
13.3
13.4
513500
13.5
513600
513700
13.6
13.7
Manage Relationships with Governments
Manage Relationships with Nuclear and
Other Related Industry Stakeholders
Manage Community Relationships
Manage External Communications, including
media relations
Manage Interactions with Educational
Institutions
Interface with the Board of Directors
Manage Legal Issues
B.13.1
Process Owner
Finance and Business Services
RTO General Counsel
Process 513300, Manage Community Relationships
This process is aimed at providing community stakeholders with timely and meaningful
information on company activities and their impacts to the community. Activities include active
communication with local officials and elected representatives, regular meetings with municipal
officials to share information on operations and status of various projects, publication of a
quarterly community newsletter mailed to more than 40,000 residents of Renfrew and Pontiac
Counties, communication with the local business community and school boards, participation in
local fairs and trade show, and ensuring communication links are maintained during emergencies
as part of the company emergency preparedness program.
B.13.2
Process 513400, Manage External Communications
This process covers wider public communication, both nationally and international. Activities
include media relations, managing the company’s web site (www.aecl.ca) in both official
languages, developing and managing “specific” web site of key areas of interest, and facilitating
the company’s presence at national and international events.
B.14
Process 514000, Improve Organizational Performance and Manage
Change
This business process consists of processes and activities associated with managing our
operational performance, improvement and change. The process includes managing
organizational performance; implementing quality management principles; conducting
compliance assessments and internal audits; benchmarking performance; making management
system and business process improvements; managing changes; and reporting on performance
and assessments.
ASI
#
Process Name
514000
14
Improve Organizational Performance and Manage Change
514010
514020
14.01
14.02
Safety Culture
Human Performance
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Process Owner
Programs and Nuclear Oversight
AECL - OFFICIAL USE ONLY
145-514100-MAN-001 Page B-12
Rev. 0
ASI
#
Process Name
Process Owner
514030
514100
14.03
14.1
Research & Development
514200
14.2
514300
14.3
Knowledge Management
Maintain and Improve Overall Management
System
Prescribe Quality Requirements and Improve
Business Processes
Ensure Compliance and Performance
514400
14.4
Perform Independent Reviews of HSE
AECL - SRC Chair
514500
14.5
Conduct Internal Audits and Report on
Findings
AECL – Internal Audit
B.14.1
Engineering
Engineering
Engineering & Programs and Nuclear
Oversight
Process 514010, Safety Culture, and Process 514020, Human Performance
These processes cover activities to promote the development of behavioural practices in both
leaders and staff that are proven to reduce human error and thereby reduce events. Activities
include implementing Human Performance (HU) procedures, training and testing; using OPEX,
communicating lessons and information to enhance staff awareness; leading assessments to
analyze HU program implementation, events, safety culture and HU trends and related problems;
running simulator training lab to reinforce error prevention behaviours; providing oversight for
the Observation & Coaching (O&C) process; leading HU based studies and development of
interventions to address identified opportunities for improvement; and in collaboration with other
safety programs and processes, driving a strong positive safety culture across RTO and
enhancing safe work performance of all staff.
B.14.2
Process 514100, Maintain and Improve Overall Management System
This process covers activities to manage and improve the management system. Activities
include governing documentation such as policies and procedures; organizational descriptions
including delegation of authority and organization change control processes.
B.14.3
Process 514200, Prescribe Quality Requirements and Improve Business
Processes
This process covers various quality and business process-related activities not covered
elsewhere. Activities include sharing of information such as advisory notices, lessons learned
and feedback; selection of quality program requirements and preparation of quality assurance
manuals and plans; directive to stop work due to poor quality; change management; and
developing and managing company business processes.
B.14.4
Process 514300, Ensure Compliance with Requirements
This process covers activities to assess performance and compliance of work. Activities include
self-assessments, audits, preventive actions, program reviews, improvement action (ImpAct)
process, including identification, processing and notification of non-conformances, defects and
failures to comply, audits and qualification of auditors, root and apparent cause assessments.
145-514100-MAN-001 2010/09/23
Organization
ORGANIZATION TO SUPPORT CRL
OPERATIONS
CRL-514100-ORG-001
Revision 0
Prepared by
Rédigé par
Chilton John E - Regulatory
Affairs
Reviewed by
Vérifié par
Lavoie Robert - Management
System Specialist
Approved by
Approuvé par
Arthur Terence - Manager ­
Regulatory Affairs
2010/09/23
2010/09/23
AECL - OFFICIAL
USE ONLY
À L'USAGE EXCLUSIF
D'EACL
Atomic Energy of
Canada Limited
Énergie Atomique du
Canada Limitée
2251 Speakman Drive
Mississauga, Ontario
Canada L5K 1B2
2251 rue Speakman
Mississauga (Ontario)
Canada L5K 1B2
AECL - OFFICIAL USE ONLY
Information Use
Organization
À USAGE EXCLUSIF - EACL
CRL-51400-ORG-001 Page i
Rev. 0
Always refer to myAECL for latest and OFFICIAL version.
()
Utilisation de
l'information
ORGANIZATION
TO SUPPORT CRL OPERATION
TABLE OF CONTENTS
SECTION
SECTION
1.
1.
2.
2.
3.
3.
4.
4.
4.1
4.2
4.1
4.2.1
4.2
4.2.2
4.2.1
4.2.3
4.2.2
4.2.4
4.2.3
4.2.5
4.2.4
4.2.5.1
4.2.5
4.2.5.2
4.2.5.1
4.2.5.3
4.2.5.2
4.2.6
4.2.5.3
4.2.6
5.
5.
PAGE
TABLE OF CONTENTS
PAGE
SCOPE ................................................................................................................1
SCOPE ................................................................................................................1
PURPOSE............................................................................................................1
PURPOSE............................................................................................................1
DEFINITIONS ....................................................................................................1
DEFINITIONS ....................................................................................................1
RESPONSIBILITIES AND ORGANIZATION ...................................................1
RESPONSIBILITIES
AND
ORGANIZATION ...................................................1
Research and Technology
Operations...................................................................1
Organizational
Units ............................................................................................2
Research
and Technology
Operations...................................................................1
Operations......................................................................................................2
Organizational
Units ............................................................................................2
Decommissioning
and Waste Management.....................................................3
Operations......................................................................................................2
Research
and Development
............................................................................4
Decommissioning
and Waste
Management.....................................................3
Finance
and
Business
Services
.......................................................................4
Research and Development ............................................................................4
Programs
and
Nuclear
Oversight
....................................................................5
Finance and Business Services .......................................................................4
Director,
Improvement
and Nuclear Oversight .....................5
Programs
andPerformance
Nuclear Oversight
....................................................................5
Senior
Director,
Nuclear
Programs
and
Director, Performance Improvement andServices
Nuclear.......................................5
Oversight .....................5
Manager,
Regulatory
Affairs
....................................................................6
Senior Director, Nuclear Programs and Services.......................................5
Engineering
Manager,....................................................................................................6
Regulatory Affairs ....................................................................6
Engineering ....................................................................................................6
REFERENCES ....................................................................................................6
REFERENCES ....................................................................................................6
APPENDICES
No table of contents entries found.
Prepared by:
Date:
Reviewed by:
Date:
Approved by:
Date:
J. Chilton
2010/09/23
R. G. Lavoie
2010/09/23
T. Arthur
2010/09/23
CRL-51400-ORG-001 2010/09/23
 Atomic Energy of Canada Limited
Information Use
Utilisation de
l'information
AECL - OFFICIAL USE ONLY
Organization
À USAGE EXCLUSIF - EACL
CRL-51400-ORG-001 Page 1
Rev. 0
Always refer to myAECL for latest and OFFICIAL version.
()
TABLE OF CONTENTS
ORGANIZATION TO SUPPORT CRL OPERATION
SECTION
PAGE
1.
SCOPE
1.
SCOPE ................................................................................................................1
This document describes direct responsibilities for the management and control of the licensed
activities
at CRL.
2.
PURPOSE............................................................................................................1
The information supplements the general responsibilities and senior management responsibilities
3.
DEFINITIONS
....................................................................................................1
covered in the Research
and Technology
Operations (RTO) Management System Manual [1].
Not
covered herein have AND
directORGANIZATION
responsibilities for ...................................................1
the management and control of
4. all positions
RESPONSIBILITIES
the licensed activities as defined in Section IV of the current licences. However, the additional
4.1
Research
and Technology
positions/functions
are included
to provideOperations...................................................................1
a more complete picture of the management structure.
4.2
............................................................................................2
The content andOrganizational
level of detailUnits
is consistent
with that which was provided to the CNSC [2] [3].
4.2.1
Operations......................................................................................................2
This
on an interimand
basis,
untilManagement.....................................................3
each line organization in RTO prepares and
4.2.2document is issued
Decommissioning
Waste
issues
their
respective
ORG
document
in
support
of
the management system defined in [1].
4.2.3
Research and Development ............................................................................4
4.2.4
Finance and
Services
.......................................................................4
This document is maintained
byBusiness
the Regulatory
Affairs
Branch within RTO.
4.2.5
Programs and Nuclear Oversight ....................................................................5
2.
PURPOSE
4.2.5.1
Director, Performance Improvement and Nuclear Oversight .....................5
4.2.5.2
Senior Director, Nuclear Programs and Services .......................................5
To meet licensing requirements, specifically Subsection 15(b) of the General Nuclear Safety and
4.2.5.3
Manager, Regulatory Affairs ....................................................................6
Control Regulations.
4.2.6
Engineering ....................................................................................................6
3.
DEFINITIONS
5.
REFERENCES ....................................................................................................6
For terms and abbreviations refer to the Acronyms, Abbreviations, and Definitions of Terms web
site on myAECL (http://sps39/terms_definitions/terms.asp).
APPENDICES RESPONSIBILITIES AND ORGANIZATION
4.
No table of contents entries found.
4.1
Research and Technology Operations
The organization structure, senior management responsibilities, and the general responsibilities
of the site licence holders, process/program management and facility management is covered in
[1].
NOTE:
CRL-51400-ORG-001 2010/09/23
Should there be a change in responsibility from those in [1], this section would
provide the required information such as to meet the purpose of this document until
[1] is updated.
Information Use
4.2
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CRL-51400-ORG-001 Page 2
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Organizational Units
The positions that have direct responsibility for management and control of the licensed
activities at CRL are shaded.
4.2.1
Operations
The Operations group is headed by the Vice-President and General Manager, Operations and
Chief Nuclear Officer, and comprises the following direct reports:
 Director, Site Maintenance: responsible for the development and implementation of RTO’s
maintenance program organized into the following branches: (i) Site Support Services, (ii)
Construction and Commissioning, (iii) Manufacturing Services, (iv) Mechanical Services, (v)
Controlled Area 2 Maintenance, and (vi) Electrical Maintenance.
 Director, NRU: responsible for the safe conduct of licensed activities associated with the
safe and effective operation of the NRU reactor and organized into the following areas: (i)
NRU Improvements, (ii) Production, and (iii) Operations.
 Director, Dedicated Isotope Facilities Operations: responsible for transfer to safe shutdown
surveillance state for MAPLE 1 reactor, MAPLE 2 reactor, and New Processing Facility, and
support to the MDS Nordion Medial Isotopes Reactor (MMIR) Project and organized into:
(i) Maintenance, and (ii) Operations.
 Director, Site and Nuclear Operations: responsible for the safe conduct of licensed activities
associated with the safe and effective operation of the Class I nuclear facilities: Nuclear Fuel
Fabrication Facilities (Buildings 429A/B and 405), Molybdenum-99 Processing Facility,
Nuclear Facility Operations (Universal Cells, Fuels and Materials Cells and Heavy Water
Upgrading Plant), and provision of site services and utilities. Area is organized into (i) Site
Utilities, (ii) Site Planning and Property Management, (iii) Site Landlord, and (iv)
Infrastructure Management and Site Services.
 Director, Technical Support Unit: responsible to Operations for the provision of: (i)
Maintenance and Engineering Assessment, (ii) Programs and Standards, and (iii) Plant
Health and Projects.
 Director, Work Management & Control: responsible for timely identification, selection,
planning, coordination, and execution of work, organized into: (i) Site Work Management,
(ii) NRU Work Management, and (iii) Extended NRU Shutdown.
 General Manager, Isotope Supply Reliability Program: responsible for continued provision
of isotopes from CRL.
 Manager, Operations Support: responsible for centralized support to Operations and
organized into: (i) Resourcing and Training, (ii) Support Services, (iii) Operations Business
Planning, (iv) Quality Control, and (v) Quality Assurance.
 Manager, Operations Special Projects.
 Nuclear Safety Advisor.
CRL-51400-ORG-001 2010/09/23
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4.2.2
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CRL-51400-ORG-001 Page 3
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Decommissioning and Waste Management
The Decommissioning and Waste Management group is headed by the Vice-President and
General Manager, Decommissioning and Waste Management, and comprises the following
direct reports:

Director, Waste Management Division: responsible for all aspects of waste management
services and the safe conduct of licensed activities associated with the operation of the Class
I nuclear facilities (Waste Management Areas and Waste Treatment Centre) at CRL. This
includes planning and execution of Major Projects, management of the Waste Management
Program and the incorporation of new practices and facilities for waste processing and
storage, or disposal, in accordance with AECL’s Waste Management Program.
 Director, Facilities Decommissioning: responsible for the detailed planning and safe conduct
of licensed activities associated with the execution of the facilities decommissioning program
component of the Nuclear Legacy Liabilities Program. This includes the permanently
shutdown nuclear facilities on the CRL site and off-site (e.g., Gentilly 1, Douglas Point and
Nuclear Power Demonstration reactor).
 Director, Liability Management Unit: is responsible for the framework, planning, business
processes, and oversight of the funds (including program delivery) received from the
Government of Canada for the Nuclear Legacy Liabilities Program.
 Manager, Technology Support and Development: is responsible to provide technical
expertise to the various programs, major projects, and facilities within the D&WM unit.
 Director, Whiteshell Decommissioning Project: responsible for the safe conduct of licensed
activities associated with the decommissioning activities being carried out at the Whiteshell
Laboratories site.
 Director, Whiteshell Decommissioning Operations: responsible for the safe conduct of
licensed activities associated with the operation of the nuclear facilities at the Whiteshell
Laboratories site.
 Director, Waste Technology: responsible for providing technical services associated with
geological disposal of radioactive waste, and to internal and external programs.
 Director, Low-Level Radioactive Waste Management Office: is responsible for carry out the
responsibilities for the management of low-level radioactive waste in Canada on behalf of the
Government of Canada and is responsible for five CNSC licences related to its operations in
Port Hope and across Canada.
 Manager, Program & Standards: responsible for overseeing D&WM Quality, Performance
Improvement and Information Management.
 Project Director, Port Hope Area Initiative: responsible for the planning and implementation
of the Port Hope Area Initiative (PHAI), the federally-sponsored project to clean-up historic
low-level radioactive waste situated in the Municipalities of Port Hope and Clarington, and
leadership of the PHAI Management Office, the agency designated by the Government of
Canada to carry out its responsibilities set out in the Legal Agreement that established the
PHAI.
CRL-51400-ORG-001 2010/09/23
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4.2.3
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CRL-51400-ORG-001 Page 4
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Research and Development
The Research & Development group is headed by the Vice-President and General Manager,
Research & Development, and comprises the following direct reports:
 Senior Director, Strategic and Operational Planning: responsible for the oversight of COG
Programs, R&D planning and general operations, and is organized as follows: (i) R&D
Operations and Planning, and (ii) Special Projects.





Director, Components and Systems Division: responsible for providing customers with
products and services, and for the safe conduct of licensed activities associated with the
operation of the laboratories under their control and the Class I Nuclear facilities in R&D.
This includes the Tritium Facility and Combined Electrolysis Catalytic Exchange
Upgrading/Detritiation Facility, and is organized as follows: (i) Hydrogen Isotopes
Technology, (ii) Component Life Technology, (iii) Inspection Monitoring & Dynamics, (iv)
Fluid Sealing Technology, and (v) Mechanical Equipment Development.
Director, Fuel Channels Division: responsible for providing customers with products and
services, and for the safe conduct of licensed activities associated with the operation of the
laboratories under their control, and is organized as follows: (i) Materials & Mechanics, (ii)
Deformation Technology, and (iii) Reactor Chemistry and Corrosion.
Director, Nuclear Science: responsible for providing customers with products and services,
and the safe conduct of licensed activities associated with the operation of the laboratories
under their control. The area is organized as follows: (i) Environmental Technologies, (ii)
Computational Reactor Physics, (iii) Radiation Protection Research and Instrumentation, (iv)
Applied Physics, (v) Systems Engineering, and (vi) Non-Proliferation and Safeguards.
Director, Reactor Safety: responsible for providing customers with products and services,
and for the safe conduct of licensed activities associated with the operation of the laboratories
under their control, and is organized as follows: (i) Code Center & Software, (ii) Thermal
Hydraulics, (iii) Fuel & Fuel Channel Safety, (iv) Fuel Development, and (v) Analytical
Chemistry.
Director, R&D Facilities Operations: is responsible for the safe conduct of licensed activities
associated with the operation of the Class I and II nuclear facilities in R&D, (i.e., Zero
Energy Deuterium (ZED)-2 reactor, Recycle Fuel Fabrication Laboratories, Health Physics
Neutron Generator, GC 60 Gamma Irradiator, and Gammabeam 150C Facility).
4.2.4
Finance and Business Services
The Finance and Business Operations group is headed by the General Manager, Finance and
Business Operations, and comprises the following direct reports:





Finance Director, Strategic Initiatives & Stakeholder Relations
Finance Director, Business Support and Analysis
Director, Supply
Director, Program and Business Integration
Director, CRL IT Services
CRL-51400-ORG-001 2010/09/23
4
Information Use





AECL - OFFICIAL USE ONLY
CRL-51400-ORG-001 Page 5
Rev. 0
Manager, Business Development & Intellectual Property
Manager, Site & Community Affairs
Manager, Policy & Strategic Planning
Manager, Finance Reporting & Accounting
Manager, Information Assets Services
4.2.5
Programs and Nuclear Oversight
The Programs and Nuclear Oversight group is headed by the General Manager, Programs and
Nuclear Oversight and Chief Regulatory Officer, and comprises the following direct reports:



Director, Performance Improvement and Nuclear Oversight
Senior Director, Nuclear Programs and Services
Manager, Regulatory Affairs
4.2.5.1
Director, Performance Improvement and Nuclear Oversight
The Director, Performance Improvement and Nuclear Oversight is responsible for:






Developing and managing the Operating Experience Program (OPEX) as Program Authority.
Acting as the Chairperson for the ImpAct Review Board and the Operational Oversight
Safety Committee.
Ensuring that all aspects of the OPEX program comply with all AECL policies and
regulatory requirements.
Representing all aspect of the OPEX programs to CNSC.
Independent assessments.
Reporting periodically to the Site Licence Holder on program performance (e.g., summary of
issues, non-compliances, trends, timeliness of reporting, and corrective actions, etc.).
4.2.5.2
Senior Director, Nuclear Programs and Services
The Senior Director, Nuclear Programs and Services, is responsible for three departments that
design and deliver programs that enable AECL to work safely and compliant with regulatory
standards, codes, legal requirements and corporate policies. This also includes the division
office that provides leadership and support to the departments and programs, and is the interface
for the Nuclear Training branch (which reports administratively to Nuclear Programs and
functionally to the Organizational Development & Training Division in Human Resources).
The three main departments and eight programs in Nuclear Programs and Services are:
1. Nuclear Materials and Emergency Preparedness Branch
 Nuclear Criticality Safety Program
 Radioactive Materials Transportation Program
 Nuclear Materials & Safeguards Management Program
 Emergency Preparedness Program
CRL-51400-ORG-001 2010/09/23
5
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CRL-51400-ORG-001 Page 6
Rev. 0
2. Radiation Protection & Environmental Protection Division
 Radiation Protection Program
 Environmental Protection Program
3. Emergency & Protective Services Division
 Physical Security Program
 Fire Protection Program
4.2.5.3
Manager, Regulatory Affairs
The Manager, Regulatory Affairs is responsible for providing guidance, advice, and support to
senior management with respect to the maintenance, amendment and renewal of Licences issued
to RTO by the CNSC.
4.2.6
Engineering
The Engineering group is headed by the General Manager, Engineering and Chief Nuclear
Engineer, and comprises the following direct reports:




Director, Design Engineering
Director, Safety Engineering and Licensing
Manager, Engineering Operations
Manager, Engineering Programs & Standards
5.
[1]
[2]
[3]
REFERENCES
145-514100-MAN-001, Management System Manual.
T. Arthur, Letter to M. Santini, Research and Technology Operations Reorganization,
145-ACNO-10-0003-L, RA-10-001, 2010 June 15.
T. Arthur, Letter to M. Santini, Research and Technology Operations Reorganization,
145-ACNO-10-0008-L, RA-10-011, 2010 July 08.
CRL-51400-ORG-001 2010/09/23
6
Revision History
Liste de révisions
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À USAGE EXCLUSIF - EACL
Page 1 of / de 1
CW-511300-FM-168 Rev. 0
Ref. Procedure CW-511300-PRO-161
Document No. / Numéro de document:
CRL
514100
ORG
001
Doc. Collection ID
ID de la collection de doc.
SI
Répertoire du sujet
Section
Serial No.
o
N de série
Document Details / Détails sur le document
Total no. of pages
Nbre total de pages
Title
Titre
ORGANIZATION TO SUPPORT CRL OPERATION
8
For Release Information, refer to the Document Transmittal Sheet accompanying this document. / Pour des renseignements portant sur la diffusion,
consultez la feuille de transmission de documents ci-jointe.
Revision History / Liste de révisions
Revision / Révision
No./N
0
dsfpdfscs
o
Date
(yyyy/mm/dd)
Details of Rev. / Détails de la rév.
Prepared/Revised by
Rédigé/Examiné par
Reviewed by
Examiné par
Approved by
Approuvé par
2010/09/23
Issued as “Approved for Use”.
J. Chilton
R. G. Lavoie
T. Arthur
CRL-51400-ORG-001 2010/09/23
AECL EACL
145-514100-016-000
Research and Technology
Operations
Revision 0
Management System
Contact and Responsibility List
2010 September
Prepared by:
R.G. Lavoie
,(jJ;;#4'J
'~/
Approved by:
(\ ' L( n ~
, V ".0.runen
]
\ \
~\,
)
~--~
AECL - OFFICIAL USE ONLY
A USAGE
This document and the information contained in it is the property of Atomic
Energy of Canada Limited (AECL). No use, disclosure, exploitation or
transfer of any information contained herein is permitted in the absence of
an agreement with AECL, and the document may not be released without
the written consent of AECL.
Le present document et I'information qu'i1 contient sont la proprlets
d'Enerpie atomique du Canada Iimitee (EACL). Le present document ne
peut etre transmis sans I'autorisation ecrlte d'EACL et les renseignements
qu'i1contient ne peuvent etre utilises, ni divulques, ni exploltss ni
communiques sans entente a cet elfet avec EACL.
© Atomic Energy of Canada Limited
© Energie atomique du Canada limitee
2251 Speakman Drive
Mississauga, Ontario
Canada L5K 1B2
2251, rue Speakman
Mississauga (Ontario)
Canada L5K 1B2
C\Documents and Senings\lavoier\Local Senings\Temporary Internet
Files\Content.Out1ook\IUY3CQZ~IS
EXCLUSIF - EACL·
Contact and Responsibility List (2).doc
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Date
2010/09/23
Revision
0
Purpose of Issue
“Issued as approved for use.”
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Changes Made
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page ii Rev. 0 Table of Contents
1. SCOPE AND PURPOSE..................................................................................................................................... 1
2. NUCLEAR LEADERSHIP TEAM.................................................................................................................... 2
3. COMMITTEES ................................................................................................................................................... 3
4. PROCESSES AND PROGRAMS ...................................................................................................................... 4
5. FACILITIES AND LABORATORIES.............................................................................................................. 9
5.1 CHALK RIVER LABORATORIES .......................................................................................................................9
5.1.1 Class I Nuclear Facilities ...................................................................................................................... 9
5.1.2 Class II Nuclear Facilities ................................................................................................................... 10
5.1.3 Class B Radioisotope Laboratories ..................................................................................................... 10
5.1.4 Class C Radioisotope Laboratories ..................................................................................................... 11
5.1.5 Permanently Shut Down Facilities ...................................................................................................... 13
5.1.6 Other Facilities .................................................................................................................................... 13
5.2 WHITESHELL LABORATORIES .......................................................................................................................13
5.2.1 Nuclear Facilities ................................................................................................................................ 13
5.2.2 Class B Radioisotope Laboratories ..................................................................................................... 13
5.2.3 Class C Radioisotope Laboratories ..................................................................................................... 14
5.2.4 Permanently Shutdown Facilities ........................................................................................................ 14
5.2.5 Other Facilities and Laboratories ....................................................................................................... 15
6. OTHERS ............................................................................................................................................................ 16
6.1 6.2 6.3 6.4 PROJECTS ..................................................................................................................................................... 16
SENIOR QUALITY REPRESENTATIVES ...........................................................................................................16
SAFETY AND LICENSING ............................................................................................................................... 17
LINE ORGANIZATIONS .................................................................................................................................. 17
7. REFERENCES .................................................................................................................................................. 18
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1.
SCOPE AND PURPOSE
This document contains the names and positions of managers and senior staff responsible for
and/or contact for the various elements of the Management System in Research and Technology
Operations (RTO). The Management System is defined in a manual [1] and supporting GDIs [2]
[3].
The document includes executives, senior managers, facility/program authorities and managers,
process owners, subject matter experts, laboratory contacts, and senior quality representatives.
The purpose of the list is to identify a point of contact for RTO staff as well as CNSC staff,
should there be a particular question or concern regarding any aspect of the management system.
Individuals in this document are authorized to act for the licensee (i.e. AECL) in there dealings
with the CNSC staff within their area of responsibilities.
The document includes identification of individuals and positions having direct responsibility for
the management and control of the licensed activities. The names of these individuals are
shaded.
This document is not used to assign an individual to a particular position or to a set of
responsibilities. These assignments are covered by other processes.
Comments or out of date information listed in here should be communicated to the Management
System Specialist, who maintains this document.
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2.
NUCLEAR LEADERSHIP TEAM
This section covers the Nuclear Leadership Team described in the Management System Manual
(MSM) [1] in Section 7.2.
Title
Senior Vice-President
Name
MSM
Section No.
W. (Bill) Kupferschmidt 7.2.1
Vice-President & General
Manager, Operations & Chief
Nuclear Officer
General Manager, Isotope
Supply Reliability Program
Vice-President & General
Manager, Waste Management
and Decommissioning
Vice-President & General
Manager, Research and
Development
E. (Hank) Drumhiller
7.2.2
S. (Steve) Bushby
7.2.2.1
J. (Joan) Miller
7.2.3
R. (Rick) Didsbury
7.2.4
Principle Scientist
Vice-President, Commercial
General Manager, Finance and
Business Services
General Manager Programs and
Nuclear Oversight and Chief
Regulatory Officer
General Manager Engineering
and Chief Nuclear Engineer
RTO General Counsel
Manager Human Resources
R. (Romney) Duffey
R. (Richard) Coté
S. (Steve) Halpenny
7.2.5
7.2.6
7.2.7
A. (Andrew) White
7.2.8
R. (Randy) Lesco
7.2.9
D. (Doug) McIntyre
S. (Susan) Sweet
7.2.10
7.2.11
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
Comment
Acting. Dr. Robert
Walker to begin in
this role on
2010 Nov 15th
Acting.
W. Kupferschmidt
to return in this role
on 2010 Nov 15th
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 3
Rev. 0
3.
COMMITTEES
This section covers the committees described in the MSM Section 7.4.
Committee
Operational Safety Oversight
Committee (OSOC)
Performance Oversight
Committee (POC)
Business Operations Strategy
(BOS)
Project Performance Oversight
Committee (PPOC)
ImpAct Review Board (IRB)
Health, Safety, Security and
Environment Business
Performance Council (HSSE
BPC)
Environmental Panel (EP)
Site Safety and Health
Committees
Nuclear Performance Assurance
Review Board
Safety Review Committee
Chair/Secondary
Contact
A. (Andrew) White
MSM
Section No.
7.4.1
S. (Steve) Halpenny
7.4.2
Comment
W. (Bill) Kupferschmidt 7.4.3
N. (Nancy) Wagner
7.4.4
K. (Kathy) Smith
H. (Hugh) MacDiarmid/
J. (Jim) Bond
7.4.5
7.4.6
G. (George) Dolinar
----
7.4.7
7.4.8
J. (Jim) Bond/
P.(Patricia) Verch
J. (Jim) Bond/
D. (Davelyn) Hickey
7.4.9
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
7.4.10
Site specific
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4.
PROCESSES AND PROGRAMS
This section covers the processes (and programs) described in the MSM Appendix B.
(PA) = Program Authority
(PM) = Program Manager
* = AECL contact not RTO employees
Process
ID
501000
502000
503000
504000
505000
505210
505240
505250
506000
507000
507100
507200
1
Process /Program
Process Owner/SME 1
Understand Markets and R. (Richard) Coté
Customers
Define Vision, Strategy
R. (Steve) Halpenny
and Corporate Plan
Design and Develop
Refer to 508120
Products, Services and
Projects
Market and Sell Products R. (Richard) Coté
and Services
Produce, Build, Modify and Deliver Products, Services or
Projects
Perform Procurement
L. (Laura) Dykstra
and Materials
Management
Manage
S. (Simon) Ellison/
Construction/Installation P. (Paul) D’Arcy
Manage
S. (Simon) Ellison/
Commissioning/Testing S. (Steve) Reaume
Provide After-sales
R. (Richard) Coté
Customer Support
Develop and Maintain Nuclear Technology
Plan Technology
W. (Bill) Kupferschmidt
Development Activities
Develop Technology
W. (Bill) Kupferschmidt
SME = Subject Matter Expert
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MSM
Section
No.
B.1
B.2
B.3
B.4
B.5
B.5.1
B.5.2
B.5.3
B.6
B.7
Comment
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507230
507300
507320
508000
508110
508120
508130
508140
508210
508220
508230
508238
508240
508300
508400
508500
508510
508520
508530
508540
508550
508600
508710
Develop Analytical,
G. (Glen) McGee
Scientific and Design
Software
Maintain and Secure
W. (Bill) Kupferschmidt
Technology
Manage Intellectual
D. (Doug) McIntyre
Property
Manage Facilities, Nuclear Laboratories, Materials and
associated Liabilities
Provide Project
N. (Nancy) Wagner
Management
Provide Design and
C. (Colette) Taylor
Engineering
Configuration
C. (Colette) Taylor
Management
Management Of Pressure R. (Randy) Lesco (PA)
Boundary System
Operate Sites
G. (Garry) Yaraskavitch
Operate Facilities
G. (Garry) Yaraskavitch
Provide Maintenance
M. (Mike) Corrigan/
A. (Annie) Beauchamp
Work Management
S. (Scott) Forbes
Provide Manufacturing
G. (Garry) Yaraskavitch
and other Support
Decommission Sites and D. (Dianne) Lemire
Facilities
Manage and Maintain
S. (Sue) D'Eon
Offices and Buildings
Manage Materials
Manage Nuclear
R. (Richard) Nishimura (PA)/
Materials and Safeguards K (Kathy) Leroux (PM)
Manage Transportation
R. (Richard) Nishimura (PA)/
of Radioactive Materials B. (Bernadette) Macdonald (PM)
Manage non nuclear
L. (Laura) Dykstra
materials
Manage Services
L. (Laura) Dykstra
Provide Nuclear
J. (Jeremy) Whitlock
Criticality Safety Control (PA)/L. (Lloyd) Dunn (PM)
Manage Wastes
P. (Pierre) Wong (PA)
Provide Physical
K. (Keith) Lafreniere (PA)/
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B.7
B.8
B.8.1
CRL only
B.8.2
B.8.3
B.8.4
B.8.5
B.8.6
B.8.7
B.8.8
B.8.9
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 6
Rev. 0
508720
Security
Provide Fire Protection
508730
Provide Emergency
Preparedness
508740
Provide Radiation
Protection
Provide Operating
Experience
Provide Licensing
Services
508750
508760
M. (Mike) Molson
S. (Shahina) Kurien (PA)/
R. (Richard) Sparling
C. (Cathy) Fisher (PA)/
K. (Kathryn) Garven (PM-CRL)/
R. (Rich) Hamon (PM-WL)
A. (Andy) Bugg (PA)/
K. (Kevin) Wegner
K. (Kathy) Smith (PA)/
F. (Frank) Szostak
1. T. (Terry) Arthur/
J. (John) Chilton
B.8.10
B.8.11
B.8.12
B.8.13
B.8.14
2. D. (Dave) Cox
508770
508790
508800
508810
508820
509000
510000
510100
510200
510300
510400
510500
510600
Provide Safety Analysis D. (Dave) Cox
and Operational Safety
Assessment
Provide Dosimetry
A. (Andy) Bugg (PA)/
Services
H. (Heinrich) Ziegler (PM)
Manage Physical Liabilities
Manage Legacy
J. (Joan) Miller
Liabilities (AECL sites)
Manage Historic
R. (Robert) Zelmer
Liabilities (non AECL
sites)
Manage Environmental
G. (George) Dolinar (PA)/
Protection
A. (Annie) Morin
Develop and Manage Human Resources
Manage Staffing
S. (Susan) Sweet
Train and Develop
R. (Randall) Burnett */
Employees
K. (Kent) Olsheski *
Assess and Reward
S. (Susan) Sweet
Employee Performance
Ensure Employee Safety S. (Shannon) Jones (PA) */
& Well being
S. (Scott) Blain *
Manage Relations with
S. (Susan) Sweet
Employees
Manage Employee
B. (Barry) Dubreuil
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
B.8.15
B.9
B.10.1
B.10.2
B.10.3
1. Site
CNSC
interface &
2011
Licence
Renewal.
2. Other
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 7
Rev. 0
510700
511000
511100
511200
511300
511400
511500
512000
513000
513100
513200
513300
513400
513500
513600
513700
514000
514010
514020
Security
Manage Employee
P. (Pat) Quinn/
Communications
P. (Philip) Kompass
Manage Information and Associated Technology
Design, Implement and
S. (Sandra) Thompson
Maintain Systems for
Software, Hardware and
Network Systems
Design, Implement and
S. (Sandra) Thompson
Maintain Information
Systems
Manage Information
M. (Mary) Clements
Assets
S. (Sandra) Thompson
Provide Security of IT
Infrastructure and of
Information Assets
Provide Desktop Support S. (Sandra) Thompson
Services
Manage Financial
S. (Steve) Halpenny/
Resources
D. (Dave) Smith
Manage External Relationships
Manage Relationships
D. (Doug) Christensen *
with Governments
Manage Relationships
D. (Dale) Coffin *
with Nuclear and Other
Related Industry
Stakeholders
Manage Community
P. (Pat) Quinn/
Relationships
P. (Philip) Kompass
Manage External
D. (Dale) Coffin *
Communications,
including media relations
Manage Interactions
L. (Laurence) Leung
with Educational
Institutions
Interface with the Board J. (Jon) Lundy*
of Directors
Manage Legal Issues
D. (Doug) McIntyre
Improve Organizational Performance and Manage Change
Safety Culture
K. (Kathy) Smith/
Human Performance
P. (Paul) Chiasson
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
B.10.4
B.11
B.11.1
B.12
B.13
B.13.1
B.13.2
B.14.1
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 8
Rev. 0
514030
514100
514200
514300
Knowledge Management
Maintain and Improve
Overall Management
System
Prescribe Quality
Requirements and
Improve Business
Processes
Ensure Compliance and
Performance
R. (Bob) Tapping
R. (Randy) Lesco/
C. (Christina) Van Drunen
R&D only
B.14.2
1. K. (Kathy) Smith
2. R. (Randy) Lesco &
C. (Christina) Van Drunen
B.14.3
1. Change
Management
2. All other
1. C. (Christina) Van Drunen
2. K. (Kathy) Smith
B.14.4
1. Self
Assessment
2. All other
514400
514500
Perform Independent
Reviews of HSE
Conduct Internal Audits
and Report on Findings
J. (Jim) Bond
K. (Kathy) Palmer *
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AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 9
Rev. 0
5.
FACILITIES AND LABORATORIES
This section covers the sites, facilities and laboratories described in the Sites and Facilities
Governing Documentation Index [3].
5.1
Chalk River Laboratories
5.1.1
Class I Nuclear Facilities
Facility
NRU Reactor
Nuclear Fuel Fabrication
Facility (NFFF), Building 405
Nuclear Fuel Fabrication
Facility (NFFF), Buildings
429A & 429B
Recycle Fuel Fabrication
Laboratories (RFFL)
Heavy Water Upgrading Plant
Facility Authority/Facility
Manager
W.R. (Bill) Shorter/
J. B (John) Arnold
N. D. (Norm) MacDonald/
V. (Vaughan) Rosien
N. D. (Norm) MacDonald/
V. (Vaughan) Rosien
D.B. (Brock) Sanderson/
F.C. (Ike) Dimayuga
A.K (Allan) Bakewell/
K.R. (Keith) Greenfield
ZED-2 Reactor
D.B. (Brock) Sanderson/
G.P. (Gerald) McPhee
Universal Cells
A.K (Allan) Bakewell/
J. ( Jonathan) Williams
Molybdenum-99 Production
J.T. (John) Felix/
Facility
S. (Sean) Deighton
Tritium Laboratory
S. (Sam) Suppiah/
L. (Lakshman) Rodrigo
Waste Treatment Centre and
E.L. (Ed) Plaice/
K.J. (Kevin) Sullivan
Associated Facilities
Fuels and Materials Cells
A.K (Allan) Bakewell/
T. (Tony) Scott
Waste Management Areas
W.R. (Bill) Graham/
D.K. (Dave) Raman
Combined Electrolysis Catalytic S. (Sam) Suppiah/
and Exchange
D.K. (Donald) Ryland
Upgrading/Detritiation Test
Facility
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
GDI-002
Section
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
4.1.1
Comments
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 10
Rev. 0
5.1.2
Class II Nuclear Facilities
Facility
Health Physics Neutron Generator
Gamma Beam 150C Irradiation
Facility
Gamma Beam Irradiator Model
GC60
5.1.3
Facility
Authority/Facility
Manager
D.B. Sanderson/
S.M. Carlisle
D.E. Sanderson/
H.M. Wyatt
D.B. Sanderson/
S.M. Carlisle
GDI-002
Section
Comments
4.1.2
4.1.2
4.1.2
Class B Radioisotope Laboratories
Laboratories
Storage Facility
Molten-Fuel-Moderator-Interaction
Laboratory
Radiation Growth Laboratory
NRU Laboratory
Control/Loop Laboratories
Iodine Preparation Laboratory
TIMS Sample Preparation
Laboratory
Gammacell Laboratory
Laboratory 324
Chromatography Laboratory
Containment Chemistry Laboratory
ICP-MS Laboratory
Principal/Secondary
Contacts
C.A. Fisher/
R.N. Nishimura
D.B. Sanderson/
T. Nitheanandan
D.B. Sanderson/
M. Griffiths
W.R. Shorter/
J.B. Arnold
E.J. Villeneuve/
S.D. McLaughlin
A. Bugg/K. Wegner
D.B.Sanderson/
L.W. Dickson
D.B. Sanderson/
I.J. Muir
D.B. Sanderson/
L.W. Dickson
D.B. Sanderson/
L.W. Dickson
D.B. Sanderson/
I.J. Muir
D.B. Sanderson/
L.W. Dickson
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
GDI-002
Section
4.1.3
Comments
B539 - R8
4.1.3
B137 - R117, 119
4.1.3
B150 - R201B
4.1.3
B150 - R534
4.1.3
4.1.3
4.1.3
B150 - R219, 322,
326
B226 -R113
B320 - R212
4.1.3
B320 - R334
4.1.3
B320 - R324
4.1.3
4.1.3
B320 - R317, 318,
319, 320
B320 - R333
4.1.3
B330 - R316, 318
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 11 Rev. 0 Laboratories
Radiochemistry Laboratories
Radiochemistry Laboratory
Neutron Activation Analysis
Laboratories
Hydrogen and Deuterium Analysis
Laboratories
SIMS and Radioactive Specimen
Preparation Laboratories
Coulometric Titration Laboratory
Advanced CANDU Fuel
Development Laboratories
Research Reactor Fuel
Development Laboratories
Imaging-XPS Laboratory
Waste Processing Technology
Development Laboratory
5.1.4
Principal/Secondary
Contacts
D.B. Sanderson/
L.W.Dickson
D.B. Sanderson/
L.W.Dickson
D.B. Sanderson/
L.W.Dickson
D.B. Sanderson/
L.W.Dickson
D.B. Sanderson/
I.J. Muir
D.B. Sanderson/
R. Ham-Su
D.B. Sanderson/
R. Ham-Su
D.B. Sanderson/
R. Ham-Su
D.B. Sanderson/
I.J. Muir
D.B. Sanderson/
L.W. Dickson
GDI-002
Section
4.1.3
B330 - R325, 328
4.1.3
B330 - R326
4.1.3
B330 - R319, 321
4.1.3
B330 - R326A, 327
4.1.3
B375 - R153, 157,
157A, 159
B375 - R253, 257,
257A
B375 - R43, 258 262
B375 - R38, 40, 50,
162
B375 - R160
4.1.3
4.1.3
4.1.3
4.1.3
4.1.3
Comments
B467 - R101, 102,
106, 106A, 110
Class C Radioisotope Laboratories
Laboratories
Principal/Secondary Contacts
H3 Loop
D.B. Sanderson/P. Angell
GDI-002
Section
4.1.4
Corrosion and Activity
Transports Tests
Activity Transport Loop Facility
D.B. Sanderson/I.J. Muir
4.1.4
D.B. Sanderson/I.J. Muir
4.1.4
Waste Processing and Analysis
Laboratory
CAN-DECON Decontamination
Test Loops
Coupons for Corrosion Test
Chemical Cleaning Laboratory
D.B. Sanderson/S. Liblong
4.1.4
B250 - R213,
215
B250 - R216
D.B. Sanderson/P. Angell
4.1.4
B250 - R221
D.B. Sanderson/P. Angell
D.B. Sanderson/P. Angell
4.1.4
4.1.4
B250 - R110
B250 - R415,
417
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
Comments
B250 - R111.
111A
B250 - R210
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 12 Rev. 0 Laboratories
Principal/Secondary Contacts
Geochemistry Laboratory
Heat Exchanger Technology
Branch Laboratory
Shipping & Receiving
RoomlLaboratory
Fuel Fabrication Development
Laboratory
Laser Laboratory
Solubility Studies Laboratory
ICP-AES Laboratory
D.B. Sanderson/L.W. Dickson
D.B. Sanderson/P. Angell
GDI-002
Section
4.1.4
4.1.4
D.B. Sanderson/P. Angell
4.1.4
B250 - R114
D.B. Sanderson/R. Ham-Su
4.1.4
B300 - R222
Autoclave Laboratory
Heat Treatment and
Homogenization Laboratory
Metallographic Services
Laboratory
Surface Science Laboratory
D.B. Sanderson/I.J. Muir
D.B. Sanderson/A. Celovsky
4.1.4
4.1.4
D.B. Sanderson/A. Celovsky
4.1.4
D.B. Sanderson/I.J. Muir
4.1.4
D.B. Sanderson/T. Nitheanandan 4.1.4
D.B. Sanderson/L.W. Dickson
4.1.4
D.B. Sanderson/L.W. Dickson
4.1.4
Fission Product Release Group
D.B. Sanderson/T. Nitheanandan 4.1.4
Laboratory
Carcinogen Handling Laboratory D.B. Sanderson/N. Priest
4.1.4
Bioassay Laboratories
D.B. Sanderson/S. Carlisle
4.1.4
Heat Treatment and
Homogenization Laboratory
Metallographic Services
Laboratory
Surface Science Laboratory
D.B. Sanderson/A. Celovsky
4.1.4
D.B. Sanderson/A. Celovsky
4.1.4
D.B. Sanderson/I.J. Muir
4.1.4
Fission Product Release Group
D.B. Sanderson/T. Nitheanandan 4.1.4
Laboratory
Carcinogen Handling Laboratory D.B. Sanderson/N. Priest
4.1.4
Bioassay Laboratories
D.B. Sanderson/S. Carlisle
4.1.4
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
Comments
B250 - R116
B250 - R112
B300 - R133, 134
B320 - R326
B320 - R309,
309A, 312
B320 - R220
B375 - R117,
118A, 118B, 120B
B375 - R125,
125A, 127, 127A
B380 - R114, 116,
117, 120
B469 - R105, 125,
126B
B513 - R25, 27
B513 - R115,219,
219A, 263-266
B375 - R117,
118A, 118B, 120B
B375 - R125,
125A, 127, 127A
B380 - R114, 116,
117, 120
B469 - R105, 125,
126B
B513 - R25, 27
B513 - R115, 219,
219A, 263-266
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 13
Rev. 0
5.1.5
Permanently Shut Down Facilities
Facilities
NRX Reactor and Fuel Bays
Pool Test Reactor (PTR)
Plutonium Recovery Laboratory
Plutonium Tower
Waste Water Evaporator
5.1.6
Principal/Secondary
Contacts
S.B. Kenny/J.R. Tremblay
S.B. Kenny/J.R. Tremblay
S.B. Kenny/J.R. Tremblay
S.B. Kenny/J.R. Tremblay
S.B. Kenny/J.R. Tremblay
Comments
Other Facilities
Facilities
MAPLE 1 and 2 Reactors
New Processing Facility
Principal/Secondary
Contacts
J.K. Lee/R.J. Jardine
J.K. Lee/R.J. Jardine
5.2
Whiteshell Laboratories
5.2.1
Nuclear Facilities
Facilities
Concrete Canister Storage
Facility
Active-Liquid Waste Treatment
Centre
Shielded Facilities
Waste Management Area
5.2.2
GDI-002
Section
4.1.5
4.1.5
4.1.5
4.1.5
4.1.5
GDI-002
Section
4.1.6
4.1.6
Comments
GDI-002
Section
Comments
Facility
Authority/Facility
Manager
P.J. Ingham/G. Scharer
4.2.1
P.J. Ingham/G. Scharer
4.2.1
P.J. Ingham/D.J. Graham 4.2.1
P.J. Ingham/G. Scharer
4.2.1
Class B Radioisotope Laboratories
Laboratories
Inorganic Preparation Laboratory
Inorganic Spectrochemistry
Laboratory.
Radiochemistry Laboratory
Principal/Secondary GDI-002 Comments
Contacts Section
B300 2-168 and
G. MacLean/M. Attas 4.2.2
2-172
B300 2-119, 139
G. MacLean/M. Attas 4.2.2
G. MacLean/M. Attas
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4.2.2
B100 - R650
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 14
Rev. 0
5.2.3
Class C Radioisotope Laboratories
Laboratories
Inorganic Analysis Lab
Organic Preparation and Analysis
Lab
Environmental Monitoring Lab
5.2.4
GDI-002
Section
4.2.3
G. MacLean/M. Attas
4.2.3
R. Hamon/K. Ross
4.2.3
Comments
B300 Rooms 2-173
and 2-184
B300 Rooms 2-169
and 2-170
B100 Room 702
Permanently Shutdown Facilities
Facilities
WR-1
Principal/Secondary
Contacts
G. MacLean/M. Attas
Facility
GDI-002
Section
Authority/Facility
Manager
P.J. Ingham/G. Scharer 4.2.4
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Comments
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 15
Rev. 0
5.2.5
Other Facilities and Laboratories
Facilities
B402 Gamma Irradiator
B412 Radiography Room
RD-14M Loop Neutron
Scatterometer
RD-14M Loop Gamma
Densitometers
The Environmental
Monitoring/ASB Joint
Radiochemical Counting Lab
100-658 Radiation Work
Procedure
Radiation and Industrial Safety
Instrumentation Shop
WL XRD Laboratory
WL Laundry and Decontamination
Principal/Secondary
Contacts
R. Hamon/K. Ross
K. Borgford/A. Caron
H.F. Khartabil/J. Buel
GDI-002
Section
4.2.5
4.2.5
4.2.5
H.F. Khartabil/J. Buel
4.2.5
R. Hamon/K. Ross/
G. MacLean/M. Attas
4.2.5
R. Hamon/P. Barnsdale 4.2.5
P. Sargent/P. Vilks
4.2.5
R. Hamon/P. Barnsdale 4.2.5
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Comments
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 16
Rev. 0
6.
OTHERS
6.1
Projects
Projects
Facility and Infrastructure Projects
Waste Management Projects
Environmental Restoration Projects
Isotope Supply Reliability Program
Projects
6.2
Principal/Secondary
Contacts
G. (Garry) Yaraskavitch/
A. (Angela) Coulas
P. (Paul) Tonner/
E. (Ernie) Aikens
A. (Alan) Melnyk/
G. (Glen) Walker
S. (Steve) Bushby
Comments
Senior Quality Representatives
Organization
All of RTO
Research & Development
Operations
Decommissioning and Waste
Management
Finance & Business Services
Engineering
Regulatory Affairs
PINO and Nuclear Programs &
Services
Principal/Secondary
Contacts
R. (Randy) Lesco/
C. (Christina) Van Drunen
D.B. (Brock) Sanderson/
H. (Henrik) Andersen
B. (Bob) Zadarko
D. (Dianne) Lemire
S. (Steve) Lawton
C. (Christina) Van Drunen
T. (Terry) Arthur
R.G. (Bob) Lavoie/
E. (Ed) Nicholson
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Comments
Delegated to
S. (Stephen) Beauchamp
AECL - OFFICIAL USE ONLY 145-514100-016-000 Page 17
Rev. 0
6.3
Safety and Licensing
Position
Director, Safety Engineering and
Licensing
Manager, Safety Assurance
Manager, Isotope Safety and Licensing
Manager, Decommissioning Safety and
Licensing
Manager, Sites Safety and Licensing
6.4
Name
D. (Dave) Cox
Comments
A. (Andy) Ashworth
D. (David) Garrick
J. (Jim) Walker
C. (Charles) De Vries
Line Organizations
This section covers other individuals in the various line organizations that have specific
responsibilities for the management and control of the licensed activities.
Organization
Operations
D&WM
Research and
Development
Programs and
Nuclear
Oversight
Position
Director, Site and Nuclear
Operations
Director, Waste Management
Division
Director, Facilities
Decommissioning
Director, WL
Decommissioning
Operations
Director, WL
Decommissioning Project
Director, LLRWMO
PHAI Management Office
Director, Components and
Systems Division
Director, Nuclear Science
Director, Reactor Safety
Director R&D Facilities
Operations:
Director Fuel Channels
Senior Director, Nuclear
Programs and Services
\\SPS100\Worklocs\rousseal_WL\145-514100-016-000-0001\145-514100-016-000-0001.docx
Name
G. (Garry) Yaraskavitch
Comments
At CRL
P. (Paul) Tonner
At CRL
R. (Randy) Lovelace
At CRL
P. (Paul) Ingham
At WL
G. (Grant) Koroll
At WL
R. (Bob) Zelmer
C. (Christine) Fahey
R. (Bob) Tapping
Various locations
Port Hope
At CRL
B. (Bhaskar) Sur (Acting)
J. (Joanne) Ball
D.B. (Brock) Sanderson
At CRL
At CRL
At CRL
D. (Doug) Rodgers
J. (John) Osborne
At CRL
At various locations
AECL - OFFICIAL USE ONLY
145-514100-016-000 Page 18
Rev. 0
7.
[1]
[2]
[3]
REFERENCES
145-514100-MAN-001, Management System Manual.
145-514100-GDI-001, Management System Governing Documentation Index.
145-514100-GDI-002, Sites and Facilities Governing Documentation Index.
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