Last Revision of this Section on:
July 24 th, 2007
Page 1 of 1
Title & Revision History
Radiation Safety Manual
of the
Montreal Neurological Institute & Hospital
Draft: July 2007
Revision History of Radiation Safety Manual (RSM)
(All revisions listed below have been approved by the Radiation Safety Committee of the MNH/I)
Version No.:
Issue Date:
1
May, 1999
J.M.Lupien, RSO, RVH
First version
2
September 1st, 2007
E. Meyer, RSO, MNH/I
First revision since
inception of CNSC
Radiation Safety Manual of the
MNI/H
Submitted by:
Comments:
Version No.: 2
September 1st, 2007
Last Revision of this Section on:
July 24th, 2007
Page 1 of 1
Distribution List
Distribution List for Radiation Safety Manual (RSM)
Name of Recipient:
Title or Position:
Dr. M. Diksic
Chairman, RS
Committee, MNH/I
Version No.:
2
Distribution Date:
Recipient’s Signature (or
confirmation of reception) *:
September 1st, 2007
All Lab. Directors
* this information to be kept in RSO’s copy
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last Revision of this Section on: January 17 th, 2006
Page 1 of 1
Foreword
Foreword
This document is the second version of the Radiation Safety Manual (RSM) of the Montreal Neurological Institute
and Hospital. The policies and procedures described herein reflect the Regulations of the Canadian Nuclear Safety
Commission (CNSC), which replaced the Atomic Energy Control Board (AECB) on May 31 st, 2000. The website of
the CNSC is: www.nuclearsafety.gc.ca
Parts of the first version (May 1999) of this document had been adapted from radiation safety manuals available
from other institutions such as the Royal Victoria Hospital, McGill University (www.mcgill.ca/ehs) and the
University of California. The present revision of the manual has been approved by the members of the Radiation
Safety Committee of the MNI/H.
We are grateful for financial assistance given towards this manual by the Director of the MNI and by the Associate
Director General of the MUHC. We would like to thank Ms. Belinda Preziosi for help with the preparation of the
manuscript.
The Radiation Safety Committee hopes that this manual will help maintain high standards in radiation safety at the
Montreal Neurological Institute and Hospital.
The manual is accessible on the internet from the MNI homepage at the following address: www.mni.mcgill.ca.
Mirko Diksic, PhD
Chairman, Radiation Safety Committee
MNI & MNH/MUHC
Summer, 2006
Radiation Safety Manual of the
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Version No.: 2
September 1st, 2007
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January 17th, 2006
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Relevant Sections
It is essential for personnel handling radioactive materials or
radiation emitting equipment to read the following sections of the
Radiation Safety Manual:
1.
Technologists, Radiologists, Medical and Nursing Personnel:
Chapters 1-11, 13, 14
2.
Laboratory Technologists and Researchers:
Chapters 1-7, 10, 11, 13, 14
Cyclotron Personnel shall read Chapter 12 as well
3.
Administrative assistants, Security, Receiving and Maintenance Personnel:
Chapters 1-3, 5, 6, 13
4.
Nuclear Medicine Technologists:
Chapters 1-7, 10-13
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Version No.: 2
September 1st, 2007
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August 2nd, 2007
Page 1 of 3
Table of Contents
Table of Contents
1.
Purpose of the Manual
2.
Organization and Responsibilities
2.1
Radiation Safety Committee (RSC)
2.2
Radiation Safety Officer (RSO)
2.3
Responsible Radiation User (RRU)
2.4
Departmental Radiation Supervisor (DRS)
2.5
Individual "Radiation Workers"
3.
Effective Dose Limits
3.1
Nuclear Energy Workers
3.2
Pregnant Nuclear Energy Workers
3.3
General Public
4.
Licensing and Authorization
4.1
CNSC License
4.2
MNI/MNH Internal Permits
5.
Purchase, Reception, Storage and Transfer of Radioactive Material
5.1
Purchase of Radioisotopes
5.2
Reception of Radioactive Material
5.3
Storage of Radioactive Material
5.4
Transfer of Radioactive Material and Devices
6.
Radiation Monitoring
6.1
General Principles
6.2
Area and Procedure Monitoring
6.3
Personnel Monitoring
6.4
Monitoring of Internal Radioactivity
6.5
Medical Surveillance
7.
Collection and Disposal of Radioactive Waste
7.1
General Principles
7.2
Collection and Storage of Radioactive Waste in the Laboratory
7.3
Disposal of Radioactive Waste from the Central Collection Area
7.4
Disposal of Irregular Radioactive Waste
8.
Safety Guidelines for Diagnostic Radiology
8.1
General Recommendations
8.2
Recommendations for Operation of Radiographic Units
8.3
Recommendations for Operation of Fluoroscopic Units
8.4
Recommendations for Operation of Mobile Units
8.5
Recommendations for Special Radiological Procedures
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Table of Contents
9.
Procedures for Minimizing Dose to Patients
9.1
Guidelines for the Prescription of Diagnostic X-Ray Examinations
9.2
Guidelines for Radiography in Pregnant Women
9.3
Recommendations for Reducing Gonadal Dose to the Patient
9.4
Guidelines for Carrying Out X-Ray Examinations
10.
Use of Unsealed Radioisotopes
10.1
General Principles
10.2
Classification of Laboratories
10.3
Handling of Unsealed Radioisotopes in Laboratories
10.4
Handling of Radioisotopes in the Department of Nuclear Medicine
11.
Radiation Safety in the Wards
11.1
Use of Mobile X-ray Units in Wards
11.2
In-Patient Undergoing Treatment with Unsealed Radioisotopes
12.
Procedures for the MNI/MNH Medical Cyclotron Facility
12.1
Introduction
12.2
Description of Cyclotron Facility
12.3
Radiation Monitoring in the Cyclotron Facility
12.4
Safety Interlock and Warning System
12.5
Laboratory Safety Instructions
12.6
Personal Responsibilities
12.7
Records
12.8
Radiation Safety Check List
12.9
Procedures for Handling of Irradiated Targets
12.10 References
13.
Radiation Accidents and Emergency Procedures
13.1
General Principles
13.2
Accidents Involving External Exposure Only
13.3
Contamination by Radioactive Material
13.4
Fires Involving Radioactive Material
13.5
Loss or Theft of Radioactive Material or Radiation Devices
14.
Education and Training of Personnel
15.
Appendices (* hardcopy or scanned version only)
1.
Radiation Measurement Units – Système International (SI)
2.
Radiotoxicity and Half Life of Selected Radionuclides
3.
Request Form to Use New Radiochemical
4.
Radiation Safety Declaration Forms
a) RSM Declaration
b) TLD Monitor Application
c) Radiation Training Form
5.
Pregnancy Declaration Form
6.
Internal Permit Application Form
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Table of Contents
7.
8.
9.
10.
11.
12.
13.
MNI/MNH Internal Radioisotope User Permit
Radioisotope Inventory Sheet
Minor Spill Incident Form
MNI/H Contamination Control Protocol
How to Convert CPM to Bq/cm2
Internal Inspection Checklist
Request for Decommissioning of Radioisotope Laboratory
14.
CNSC
a)
b)*
c)*
d)
e)*
f)*
g)*
h)*
i)*
k)*
l)*
m)*
15.
16.
17.
18.
19.
20.
Posters and Publications:
Physical Characteristics for Commonly used Radionuclides
Proper Care and Use of Personal Dosimeters (INFO-0742)
Receiving Radioactive Packages (INFO-0744)
Dose Limits for Pregnant Workers: Rationale for the Limits in the Radiation Protection
Regulations (INFO-0700)
Use of Unsealed Nuclear Substances Poster “Basic Level” (INFO-0728-1)
Use of Unsealed Nuclear Substances Poster “Intermediate Level” (INFO-0728-2)
Use of Unsealed Nuclear Substances Poster “High Level” (INFO-0728-3)
Use of Unsealed Nuclear Substances Poster “Nuclear Medicine” (INFO-0728-4)
Radioisotope Safety: Spill Procedures (INFO-0743)
Radioisotope Safety Information Poster - Iodine – 131 (INFO 0546-1)
Radioisotope Safety Information Poster - Iodine – 125 (INFO 0546-2)
Radioisotope Safety Data Sheet - Phosphorus – 32
(from Website: http://www.nuclearsafety.gc.ca/eng/publications/)
Exemption Quantities (EQ) for some Radioactive Nuclear Substances
Annual Limits on Intake (ALI) for some Radioactive Nuclear Substances (Area Classification)
Weekly Contamination Survey Log
PET Investigators Radiation Safety Information
microPET Investigators Radiation Safety Information and Radioisotope Transfer Protocol
Regulatory Quantities for some Radionuclides
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March 13 th, 2005
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Acronyms and Abbreviations
List of Acronyms
ALARA
ALI
AECB
AQ
BIC
CNSC
CRP
CTCR
DRS
ED
EDE
EHS
EPD
EQ
ERT
FDG
HMPAO
LSV
MNH
MNH/I
MNI
MPD
MUHC
NDS
NEW
PET
REB
RF
RG
RPB
RPR
RRU
RSC
RSM
RSO
RTS
RVH
SI
SPECT
SR
TLD
TDG
WHO
WMF
As Low As Reasonably Achievable
Annual Limit on Intake
Atomic Energy Control Board (became the CNSC in 2000)
Animal Quarters
Brain Imaging Center
Canadian Nuclear Safety Commission
Commission on Radiological Protection
Canadian Transport Commission Regulations
Departmental Radiation Supervisor
Effective Dose
Effective Dose Equivalent
Environmental Hygiene and Safety Office
Electronic Personal Dosimeter
Exemption Quantity
Emergency Response Team
Fluoro-Deoxy-Glucose
Hexa-Methyl-Propylene-Amine-Oxime
Liquid Scintillation Vial
Montreal Neurological Hospital
Montreal Neurological Hospital & Institute
Montreal Neurological Institute
Maximum Permissible Dose
McGill University Health Center
National Dosimetry Service
Nuclear Energy Worker
Positron Emission Tomography
Research Ethics Board
Radio Frequency
Regulatory Guide
Radiation Protection Bureau
Radiation Protection Regulations
Responsible Radiation User
Radiation Safety Committee
Radiation Safety Manual
Radiation Safety Officer
Radioisotope Tracking System
Royal Victoria Hospital (MUHC)
Système International
Single Photon Emission Computed Tomography
Safety Report
Thermo-Luminescent Dosimeter
Transport of Dangerous Goods
World Health Organization
Waste Management Facility
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Version No.: 2
September 1st, 2007
Last Revision of this Section on: January 17 th, 2006
Page 1 of 1
Attention
ATTENTION
IN CASE OF A RADIATION ACCIDENT AND/OR A
RADIOACTIVE CONTAMINATION
(if you think you cannot handle the situation)
1
Call ????? and say “Radiation Accident” or “Radiation Spill”
2
A “Code Brown” will then be issued, mobilizing the
Emergency Response Team (ERT).
3
The ERT will contact the RSO (ext. 8927 or pager No. 4063069) and both will proceed to the accident site.
4
Wait for ERT and RSO for further directions.
5
The ERT, with the help of the RSO, will initiate
decontamination and survey of the area.
Radiation Safety Manual of the
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Version No.: 2
September 1st, 2007
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January 17 th, 2006
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Useful Telephone Numbers
Useful Telephone Numbers:
MNH/I
Dr. Ernst Meyer, Radiation Safety Officer, MNH/I:
Office
398-8927
Home
525-0220
Pager
406-3069
RVH Locating
8888-53333
Dr. Mirko Diksic, Chairman, Radiation Safety Committee, MNH/I:
Office
398-8526
Home
697-9489
_____________________________________________________________________________________________
McGILL
Mr. Joseph Vincelli, McGill Environmental Safety Office:
Office
398-1538
MUHC
MUHC Radiation Safety Service:
Office
Radiation Safety Manual of the
MNI/H
(514) 934-1934
ext. 43866
Version No.: 2
September 1st, 2007
Last Revision of this Section on:
January 17 th, 2006
Page 1 of 1
1. Purpose of the Manual
1.
Purpose of the Manual
This manual constitutes a handbook of procedures for the safe handling and application of sources of
ionizing radiation. The rules, recommendations and information included in the manual have been
approved by the Radiation Safety Committee as the basis of radiation safety at the Montreal Neurological
Institute and Hospital. The overall intention of these rules and recommendations is as follows:
a)
protection of staff, patients and the general public from the hazards associated with the use of ionizing
radiation sources of all kinds.
b)
compliance with federal, provincial and local laws, regulations and licensing requirements related to such
sources.
In other words: The guiding principle throughout this manual is the ALARA Principle which demands that the
doses received by workers and members of the public be kept As Low As Reasonably Achievable, social and
economic factors taken into account (see CNSC Regulatory Guide G-129).
Adherence by this Institution to the ALARA Principle is demonstrated by the following elements:
1) a solid commitment from the management of the MNH/I towards radiation safety (i.e., awarding of a
budget for radiation safety, appointment of a RSO and a RSC and a continuing interest in their
activities, delegation of a representative from the administration to the RSC, continuing interest and
support for upgrading radiation safety, purchasing and renewal of equipment);
2) the provision of resources (see under 1), organization and support of training sessions (i.e., the MNH/I
assumes the cost of employee training sessions organized by McGill), establishment of “action levels”
(see chapter 6), continuing efforts to further reduce radiation doses to employees and to the
environment, documentation of radiation safety-related procedures, data and events;
3) operational reviews of dose records, frequency of incidents (contamination control),
review and introduction of new technology for improved radiation protection (e.g., the purchase of
modern electronic direct reading personal dosimeters or EPDs).
We believe that there is ample evidence to be found throughout the present Radiation Safety Manual indicating that
radiation safety at the MNH/I is managed in the spirit of the above statements.
Notes:
-Throughout this manual “shall” is used to designate features or actions which are essential, while “should”
is used to designate features or actions which are recommended.
-This manual will be amended and supplemented from time to time in the light of changes in regulations,
knowledge, equipment, organization or legal requirements.
- All quantities in this manual, unless otherwise stated, are given in the Système International (SI) units.
The table in Appendix 1 gives conversion factors between the old and the SI units.
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Version No.: 2
September 1st, 2007
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2. Organization and Responsibilities
2.
Organization and Responsibilities
The licensee of our current CNSC licenses is the Montreal Neurological Hospital & Institute. The
management of the MNH/I is thoroughly committed to radiation safety as demonstrated by its assumption
of the following responsibilities:
1)
2)
3)
4)
Provision of a radiation safety budget
Appointment of a radiation safety officer (RSO)
Provision of physical resources (space) for the radiation safety program
Requesting operational reviews from time to time
The organizational basis of radiation safety at the Montreal Neurological Institute and Hospital is as
follows:
a)
A Radiation Safety Committee initially appointed on the advice of the Director of the Montreal
Neurological Institute and the Associate Executive Director of the MNH/MUHC.
b)
A Radiation Safety Officer who reports to and works under the general directives of the Radiation
Safety Committee.
c)
Responsible Radiation Users, who are persons officially designated, for licensing and other
purposes, as the individuals responsible for the procurement and use of specified radiation sources.
d)
Departmental Radiation Supervisors who, in co-operation with Heads of Departments and
Directors of Laboratories and with the Radiation Safety Officer, ensure compliance with the
relevant radiation safety requirements within a defined geographical or departmental area.
e)
Individual members of laboratories or departmental staff who have the responsibility of using
radiation sources in such a way that they do not endanger themselves or other people.
2.1
Radiation Safety Committee (RSC)
2.1.1
Membership of the RSC
The membership of the RSC is chosen such that all major radiation user groups at the MNH/I are
represented. These include in-vitro and animal research laboratories, radiochemistry cyclotron operations,
PET research and nuclear medicine operations. Furthermore, in addition to the RSO, representatives from
the administration, radiology, security, McGill University radiation safety and MUHC radiation safety are
included as well. At present, the RSC consists of 13 voting members. The quorum for meetings therefore is
7 members.
The RSC has access to an administrative assistant who organizes the meeting dates, takes minutes and
distributes them to the members of the RSC as well as to the Director of the MNI, the Associate Executive
Director of the MNH/MUHC as well as to the CNSC.
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September 1st, 2007
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2. Organization and Responsibilities
2.1.2
Terms of Reference of the RSC
a)
To review at least four times a year, and whenever necessary, the matters and problems arising
from the use of ionizing radiation in the Montreal Neurological Institute and Hospital in diagnosis,
therapy and research, with a view to ensuring satisfactory standards of safety for patients, staff and
the general public.
b)
To ensure that radiation equipment, sources, handling and shielding procedures and safety
standards satisfy such legal requirements and/or recommendations as may be issued from time to
time by national, provincial and municipal regulatory authorities.
c)
To review and to approve, or disapprove, the use of radioisotopes and radio-pharmaceuticals in the
Institute and Hospital for both human and non-human applications, from the standpoint of
radiation safety; to authorize the acquisition of these materials through the license holder; where
necessary, to apply additional conditions to such use, other than those stated in the relevant
license; and to suspend such use where appropriate, irrespective of the source of the original
authorization.
d)
To review and to approve, or disapprove, requests for the acquisition, installation and housing of
equipment capable of producing ionizing radiation, from the standpoint of radiation safety.
e)
To review arrangements for the disposal of radioactive waste, including unused radioisotopes and
radio-pharmaceuticals, to ensure adequate protection of the staff and the environment.
f)
To ensure that an adequate system of radiation monitoring is implemented, in all departments in
which ionizing radiation is employed, in collaboration with the appropriate national and/or
provincial health authorities.
g)
To ensure that adequate records are maintained of all matters pertaining to radiation hazards and
radiation doses received by Institute and Hospital personnel and, where applicable, patients and
other persons; and to ensure that cases of over-exposure or unwarranted hazard are investigated
and that remedial action is taken.
h)
To ensure that Institute and Hospital personnel are properly instructed in matters of radiation
hazards and radiation safety.
i)
To ensure that plans are prepared and suitable equipment made available to deal with accidents
and emergencies involving an actual or potential radiation hazard. Such emergencies include
incidents occurring within or outside the Institute and Hospital which result in the arrival at the
Institute or Hospital of persons who are contaminated with radioactive materials and/or have
received excessive doses of radiation. ???
j)
To prepare, and to revise from time to time, a "Radiation Safety Manual" which incorporates the
rules, recommendations, instructions, data and other information required for the implementation
of these Terms of Reference.
k)
To supervise and direct the activities of the Radiation Safety Officer in implementing the various
measures laid down in these Terms of Reference.
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September 1st, 2007
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2. Organization and Responsibilities
l)
2.2
To report to the Director of the MNI and to the Associate Executive Director of the MNH/MUHC
as well as to the Canadian Nuclear Safety Commission whenever a situation arises, involving an
actual or potential radiation hazard, such that the effective control of the hazard lies outside the
authority vested in the Radiation Safety Committee and/or the Radiation Safety Officer.
Radiation Safety Officer (RSO)
The RSO is responsible for implementing the Terms of Reference of the Committee set out in 2.1.2 above.
In particular, the duties of the RSO shall include:
2.2.1
Assessment of the status of radiation safety measures undertaken in all rooms, laboratories, wards and other
locations where radiation sources (including patients containing radioactive sources) are housed and/or
used.
2.2.2
Providing or organizing such services as may be required for radiation safety and for compliance with
federal, provincial and local laws and recommendations, where these services cannot be provided internally
by individual departments or laboratories. Examples of these services are:
a)
Instruction and training of employees in the safe handling of radiation sources.
b)
Calibration, certification and maintenance of radiation monitoring equipment.
c)
Carrying out radiation surveys, including environmental surveys, personnel monitoring (additional
to that provided by the national monitoring service) and surveys relating to particular equipment
or procedures.
d)
Survey of the collection and disposal of radioactive waste.
e)
Planning for, and supervision of, emergency procedures and special decontamination operations.
f)
Maintenance of records relating to all aspects of radiation safety, including personnel exposure
records, radiation survey records and licensing documents.
g)
Participation in the planning of new installations or procedures involving radiation sources.
h)
Co-operation with federal, provincial and local authorities in all matters relating to radiation
safety.
2.2.3
Reporting to the Radiation Safety Committee regularly and whenever any unusual or emergency situation
arises or has recently been dealt with. In particular, the RSO shall perform internal inspections (see
“Internal Inspection Checklist” in Appendix 12) of all radioisotope facilities that operate under a CNSC
license issued to the MNH/I and present the results of such inspections to the RSC.
2.3
Responsible Radiation User (RRU)
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September 1st, 2007
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2. Organization and Responsibilities
A Responsible Radiation User, sometimes also called Permit Holder, is a person who is officially
designated, for licensing or other purposes, as the individual responsible for the procurement and use of
specified radiation sources. A Responsible Radiation User is normally the director of a department,
division or laboratory. As such, he is ultimately responsible for providing adequate facilities, equipment,
supervision and instruction needed by his staff to enable radiation sources to be handled safely and in
compliance with the requirements of this manual. Frequently, the day-to-day responsibilities for some of
these matters are delegated to a Departmental Radiation Supervisor (DRS) (e.g., chief technician, see 2.4
below). Whether the responsibility is exercised directly or is delegated, the list of duties related to radiation
safety is as given in 2.4 below.
2.3.1
Internal Permit Application
Responsible Radiation Users performing in-vitro and animal laboratory studies that are covered by a
Consolidated License issued by the CNSC to the MNH/I must obtain an internal permit (see Appendix 7).
The application form (see Appendix 6) requires information such as:
-
name and position of Responsible Radiation User
name and position of Departmental Radiation Supervisor
names of radiation badge users
list of radioisotopes to be used and means and areas of storage
radioisotope reception procedures
intended use
list of sealed radioisotopes in use, with their respective activities (per manipulation; per year)
available radiation monitoring equipment
waste disposal procedure
proof of radiation safety training for staff, willingness to attend RS course
(see also paragraph 4.2 of Chapter 4: Licensing and Authorization)
2.4
Departmental Radiation Supervisor (DRS)
The Departmental Radiation Supervisor (DRS) is a person who works full-time in a given area, laboratory
or other circumscribed location, such that he/she is able to provide day-to-day supervision of the work of
employees in matters of radiation safety. The DRS derives his/her authority from the Head of the
Department, Director of the Laboratory or other Responsible Radiation User as defined in 2.3. In particular,
the DRS is responsible for:
a)
Maintaining (in co-operation with the RSO) an up-to-date list of rooms in which radiation sources
are installed, stored, handled, used or applied.
b)
Maintaining a day-to-day inventory of radiation sources in the form of radiation-emitting
equipment and/or radioactive sources (open or sealed) received, used or disposed of (relative to
each project). The MNI/MNH radioisotope inventory form is given in Appendix 8.
As of March 22nd, 2004, the MNI/H has subscribed to the Radioisotope Tracking System (RTS),
a computerized method of keeping track of the amount and location of a radioactive substance
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January 18th, 2006
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2. Organization and Responsibilities
from its acquisition to disposal. This program is administered by the McIntyre Waste Management
Program of McGill University. The RTS inventory established by each radiation user together
with the radioactive waste pick-up date information kept by the RSO may be used to replace the
inventory form given in Appendix 8.
c)
Ensuring that all persons handling radiation sources receive adequate instruction in the safety
aspects of such handling. For that purpose, the DRS will direct new radiation users (fellows, postdocs, technicians, students) to the RSO who will assure that these individuals will attend the
appropriate training sessions (see Chapter 14: Education and Training of Personnel for more
information on this topic).
d)
Allowing only authorized persons to enter areas that are specified as restricted for reasons of
radiation safety.
e)
Ensuring that personnel wear assigned radiation monitors throughout the working day and that
such monitors:
i)
ii)
2.5
are not left in close proximity to radiation sources when not being worn; and
are handed in promptly at the end of each monitoring period or before the user
commences a period of prolonged absence.
f)
Posting warning labels and signs as required by current laws and safety codes.
g)
Establishing, and ensuring observation of, appropriate working procedures (in co-operation with
the RSO) to guarantee compliance with applicable laws and safety codes.
h)
Ensuring that radioactive waste is disposed of in strict accordance with Section 7 of this manual.
i)
Notifying the RSO when any female Nuclear Energy Worker under his/her supervision, or any
such worker about to come under his/her supervision, is known to be pregnant (see Appendix 5
and Appendix 14 (d).
j)
Supplying the RSO with all the information needed for licensing purposes and/or issuing of the
internal permit.
k)
Ensuring that, when required, personnel make themselves available for bioassay procedures such
as thyroid monitoring and that adequate records of the results of such procedures are maintained.
l)
Monitoring the work area for radioactive contamination by means of a wipe test at least
weekly and recording the results in a log book.
Individual "Radiation Workers" (RW)
An individual RW, for the purpose of this manual, is an individual that handles radioactive substances
under the direction of a DRS or, by extension, of a RRU as defined earlier in this chapter. RSC of the
MNH/I requests that every RW abides by the rules set out in paragraphs a) to c) below:
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January 18th, 2006
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2. Organization and Responsibilities
a)
Every individual RW who acquires, installs, stores, handles or applies radiation sources is responsible for
working in such a way that he/she does not endanger either himself/herself or his/her colleagues and that
he/she complies with the procedures and rules laid down by the Departmental Radiation Supervisor and/or
listed in the applicable sections of this manual.
b)
An RW is responsible for any radiation monitor (e.g., TLD monitor) assigned to him/her and must carry it
on his/her person throughout the working day. He/she must not lend or assign his/her personal monitor to
anyone else, nor leave the monitor outside working hours in such a location that it could be exposed to
radiation.
c)
An RW must read and understand the relevant sections of this manual and other regulatory documents
applicable to his/her type of work. (The sections concerned will be assigned by the Responsible Radiation
User, in consultation with the RSO. See also the page Relevant Sections at the beginning of this manual).
The appropriate declaration form (Appendix 4a) must be signed and returned to the RSO. To this end the
worker may request a copy of this manual and a copy of the relevant Safety Code (edited by the CNSC or
Quebec provincial authorities) for his/her personal use, if he/she so desires.
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3. Effective Dose Limits
3.
Effective Dose Limits
The Canadian Nuclear Safety Commission (CNSC), formerly the Atomic Energy Control Board (AECB), under the
Nuclear Safety and Control Act and Regulations requires that the licensee ensure that the effective dose (due to
exposure to radioactive substances or equipment regulated by the CNSC) of a person described in column I during
the corresponding period in column II does not exceed the corresponding effective dose in column III of the
following table:
column I
column II
column III
person
period
effective dose (ED) in mSv
item
1
Nuclear Energy Worker, including one year dosimetry period
a pregnant nuclear energy worker five-year dosimetry period
50
100
2
pregnant Nuclear Energy Worker
the balance of pregnancy
4
3
any other person (general public)
1 calendar year
1
Nuclear Energy Worker: A person who is required, in the course of the person’s business or occupation in
connection with a nuclear facility, to perform duties in such circumstances that there is a reasonable probability that
the person may receive a dose of radiation that is greater than the prescribed limit for the general public.
One year dosimetry period : a period of one calendar year beginning on January 1, and every period of one
calendar year thereafter.
Five year dosimetry period: a period of five calendar years beginning on January 1, and every period of five
calendar years thereafter.
Balance of pregnancy: period of time from the moment the licensee is informed in writing of the pregnancy, until
the end of pregnancy. The following segments (1) and (2) are excerpts adapted from the Radiation Protection
Regulations (paragraph 11) issued on May 31st, 2000 by the Canadian Nuclear Safety Commission:
Obligations of Pregnant Nuclear Energy Workers:
(1) Every nuclear energy worker who becomes aware that she is pregnant shall immediately inform the licensee in
writing.
(2)
On being informed by a nuclear energy worker that she is pregnant, the licensee shall, in order to comply with
the legal limits shown in the preceding table, make any accommodation that will not occasion costs or business
inconvenience constituting undue hardship to the licensee.
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3. Effective Dose Limits
3.1
Nuclear Energy Workers
The doses listed are maximum permissible doses or MPD (also referred to as dose limits). They are in no
sense "dose allotments" which can and should be used up. On the contrary, the guiding principle of all
radiation work is: the dose should be as low as is reasonably achievable, economic and social factors being
taken into account. This is called the "ALARA" principle and is central to all radiation safety. Any
Nuclear Energy Worker whose dose exceeds his personal action level (see paragraph 6.3 for specific action
levels, ALs) is subject to investigation by the Radiation Safety Officer.
3.1.1
Both external and internal radiation may contribute to the dose received by an individual. External radiation
arises from radiation sources, including x-ray machines and radioisotope sources, which are external to the
body. Internal exposure occurs when radioactive material is ingested, swallowed, inhaled, or otherwise
enters the body and is deposited in body tissue. Internal contamination is particularly hazardous for
radioactive materials that have long half-lives and are deposited in bone or lung (e.g., radium-226,
strontium-90), but all internal radiation carries some risk and should be avoided. For this reason, stringent
precautions are needed in laboratories where unsealed (liquid and gaseous) radioisotopes are handled.
3.2
Pregnant Nuclear Energy Workers
The dose limits include special provisions for female nuclear energy workers of reproductive age:
3.3
a)
the annual maximum permissible dose must be evenly distributed throughout the year;
b)
if pregnancy is diagnosed, the worker's duties must be such that the dose to the abdomen, after the
licensee has been informed of the pregnancy, shall not exceed a total of 4mSv for the remaining
period of the pregnancy accumulated at the rate of no more than 0.6mSv per two weeks. 1
General Public
The dose limit for non-Nuclear Energy Workers and members of the public is 1mSv in one calendar year.
As stressed in paragraph 3.1, the ALARA principle applies, and every effort must be made to reduce the
actual doses received by non-Nuclear Energy Workers to as low a level as possible. This applies to any
situation in the hospital in which non-Nuclear Energy Workers or members of public, including patients,
may be exposed to radiation from devices or substances regulated by the CNSC or to radioactive
contamination, in circumstances such that the individual concerned derives no personal benefit from the
exposure.
1
AECB (CNSC) report INFO-0700, Dose Limits for Pregnant Workers: Rationale for the Limits in the Radiation
Protection Regulations (Appendix 14d).
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4. Licensing and Authorization
4.
Licensing and Authorization
4.1
CNSC License
4.1.1
The Canadian Nuclear Safety Commission (CNSC) licenses the possession and use of radiation sources in
Canadian hospitals and research institutions. Licensed activities include the following categories:
a)
Unsealed radioisotopes and radio-pharmaceuticals used for diagnosis or therapy on human
subjects, whether in a Department of Nuclear Medicine or elsewhere.
b)
Unsealed radioisotopes used for investigations and research not involving human subjects (in-vitro
or animal laboratory studies).
c)
Unsealed radioisotopes used for investigations and research involving human subjects (human
research studies such as positron emission tomography investigations on human volunteers).
d)
Sealed radioisotopes used in therapy, including sources intended for implantation (brachytherapy)
and sources housed in teletherapy (e.g. cobalt) units.
e)
Sealed radioisotopes permanently housed in instruments and equipment. This category includes
sealed isotopic sources provided for instrument calibration, for diagnostic purposes (e.g. bone
mineralization scanners) and for neutron activation analysis.
f)
Particle accelerators that are capable of giving rise to high-energy ionizing particles, either as the
useful product (e.g. a beam of high energy electrons) or as a by-product (e.g. stray neutrons). In
practice this means that all medical accelerators (linear accelerators, betatrons, cyclotrons) are
licensable.
g)
Processing and shipping of radioisotopes produced by a particle accelerator (e.g., production and
transfer or sale of 18F-FDG produced by a medical cyclotron).
4.1.2
The list in 4.1.1 excludes all radiographic and fluoroscopic equipment in the Diagnostic X-ray Department
(at present under the jurisdiction of the “Laboratoire de Santé Publique du Québec).
4.1.3
All radioisotope users in category b) above (in-vitro or animal laboratory studies) at present are covered
under a single collective or Consolidated License issued to the Montreal Neurological Hospital and
Institute. Each Responsible Radiation User in this category is then issued an Internal Radioisotope User
Permit (see section 4.2).
4.1.4
The application of radiation sources of any kind (external or internal) to human volunteers for research, or
for other purposes not directly linked to the welfare of the individuals concerned, is subject to further
restrictions. Investigations of this nature fall under the jurisdiction of the Biologics and Genetic Therapies
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4. Licensing and Authorization
Directorate of Health Canada (see letter, dated October 22, 2003, to Dr. Jean-Paul Soucy, PET Unit
Coordinator, MNI), the role of the Radiation Safety Committee being to advise the REB on the radiation
dosimetry aspects of the proposal. Also, the guidelines issued by the World Health Organization in 1973
provide a suitable basis for decision-making in these areas of research.
An applicant for a license for the use of radiation sources in human subjects has to satisfy the following
conditions, as required by the CNSC:
a)
he/she is a qualified and registered Nuclear Medicine specialist of the province of Quebec;
b)
he/she is qualified and experienced in the handling of radioisotopes and radiation sources;
c)
the quantities of radioisotopes to be purchased, stored and handled at any one time do not exceed
the safe limits for the type of laboratory and facilities available;
d)
the procedure (protocol) and administered radioactivity per subject (human volunteer) are
approved by the Research Ethics Board (REB);
e)
adequate instrumentation for measurement and monitoring of radiation is available.
Information on all of these points is asked for on the license application form (CNSC Regulatory
Guide C-292).
Other specific information is required for each of the licensing categories listed above, particularly for category
4.1.1.f (particle accelerators).
The Radiation Safety Officer of the MNH/I, in consultation with the applicant, will assure the complete and timely
processing and/or renewal of any specific license application to be submitted to the CNSC.
4.2
MNI/MNH Internal Permits
As already mentioned above, all users of radioisotopes under category b) (in-vitro or animal laboratory
studies) are covered by a Consolidated License issued to the MNH/I by the CNSC. However, each
Responsible Radiation User must hold a current “Internal Radioisotope User Permit” issued by the RSO on
behalf of the Radiation Safety Committee. This permit is valid at the very most for a period not exceeding
the validity duration of the Consolidated License. It contains specified conditions of approval, compliance
with which is mandatory. Failure to comply may result in the cancellation of the permit and may even
jeopardize the MNH/I’s Consolidated License.
4.2.1
Procedure for Obtaining Internal Permits
To apply for an Internal Permit, the RRU has to complete the "Internal Permit Application Form", a
sample of which is given in Appendix 6. This form has to be completed in full and returned to the RSO.
(Notice that this form includes a clause on radiation safety training!). The application is then reviewed by
the Radiation Safety Committee (if the next Radiation Safety Committee Meeting is some time away, the
chairman of this committee together with the RSO may temporarily approve a permit application) and
detailed conditions of approval are formulated. A copy of the approved “Internal Radioisotope User
Permit” is then sent to the applicant, and another copy is retained by the RSO. An example of the “Internal
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4. Licensing and Authorization
Radioisotope User Permit”, which has to be posted at the location(s) specified on the permit, is shown in
Appendix 7.
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5. Purchase, Reception, Storage and Transfer of Radioactive Material
5.
Purchase, Reception, Storage and Transfer of Radioactive
Material
5.1
Purchase of Radioisotopes
5.1.1
All purchases of radioactive materials must be approved by a Responsible Radiation User (RRU) who is
the holder of an MNI/MNH internal permit, which in turn is issued in accordance with a valid CNSC
license. All purchases of radioactive materials must be signed by the RSO prior to processing. The RSO’s
office signs the purchase orders only if the following conditions are met:
(1) RESULTS of the most recent routine (weekly) wipe test are included with the order (the RSO may ask
to see further wipe tests to verify full compliance with contamination control requirements).
(2) If areas of contamination are apparent from these wipe tests, a second wipe test has been performed
AFTER SUCCESSFUL CLEANUP and the results of both wipe tests, BEFORE and AFTER cleanup, are
included with the order.
The RSO’s office maintains a record of all radioactive materials purchased at the MNI/MNH.
5.1.2
The Montreal Neurological Institute and Hospital has a standardized system for the purchase, reception and
distribution of radioisotopes.
5.1.3
The activity of each type of radioisotope that can be purchased, stored and used by the individual
Responsible Radiation User is limited by the possession limit indicated on the internal permit and, for the
institution as a whole, by the maximum quantities (possession limits) specified on the CNSC license.
5.1.4
Up-to-date individual inventories have to be maintained by each RRU with detailed data about each
incoming shipment and its partial or total use in the laboratory and its disposal. The inventories have to be
presented for inspection by the RSO/CNSC or other competent authority. A copy of the recommended form
of a radioisotope inventory is included as Appendix 8.
Since the implantation at the MNH/I of the Radioisotope Tracking System (RTS) by the McGill Waste
Management Facility on March 22nd, 2004, the computer record generated by this comprehensive program
is acceptable as a substitute for the Inventory Sheet shown in Appendix 8.
5.2
Reception of Radioactive Material
Each package containing radioactive material bears at least two RADIOACTIVE warning labels which
display the required information about the contents and activity of the package. Packages are classified
according to the dose-equivalent rate at the surface and at a distance of 1 meter from the surface.
Category I:
Category II:
Category III:
Less than 5µSv/hr on the surface.
Less than 500μSv/hr on the surface and a transport index of 1.0.
Less than 2mSv/hr on the surface and a transport index of less than 10.
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5. Purchase, Reception, Storage and Transfer of Radioactive Material
The transport index (TI) is the maximum radiation level in μSv (microsieverts) per hour measured at 1
meter from the surface of a package, divided by 10. The TI is also equal to the radiation level measured in
mrem/h at 1m, or, for most practical purposes, equal to the radiation field measured in mR/h at 1m from the
surface of the parcel. Detailed information is given in the CNSC poster Guidelines for Handling Packages
Containing Nuclear Substances (INFO-0744) which is included as Appendix 14c in this manual.
Packages are usually delivered to stores, unless special arrangements are made between the supplier and a
particular laboratory in exceptional cases. Stores have outlined a specific area which is reserved for the
reception of radioactive packages. Packages are briefly examined for damage and eventual leakage by
stores personnel.
If the package shows obvious damage, then the addressee should be called immediately and the RSO
should be contacted as well.
If the damage is beyond control (severe leakage), the Radiation Emergency Number (?????) should be
called. The RSO will then automatically be alerted and called to provide assistance.
If no damage to the package is detected, stores personnel will deliver it to the addressee as quickly as
possible (delivery hours are from 8am to 3:30pm).
5.2.1
Only the holder of an internal permit or the person designated by the holder himself/herself may receive an
incoming radioactive shipment that is delivered to his/her laboratory.
5.2.2
The RRU of a given laboratory should designate: i) a room or area as the reception point and ii) a suitable
person, or persons, authorized to accept delivery of packages containing radioactive materials.
5.2.3
Incoming packages containing radioactive material have to be examined for leakage, damage and
contamination by the RRU or another qualified individual designated by the latter.
5.2.4.
Under no circumstances should it be possible for radioactive materials to be delivered and left unattended,
without the knowledge of an authorized person.
5.2.5
The MNH/I Receiving (Stores) Department personnel and Security personnel are instructed to call the RSO
when radioactive material of unknown destination within the MNH/I arrives. ???
5.2.6
If any delivery is made during holidays or off-duty hours, only MNH/I Security personnel can accept it.
The on-duty Security Officer has a key to the appropriate storage room (central waste storage facility in the
basement, room #045) and is instructed to leave incoming radioactive packages there under lock and key.
The Responsible Radiation User should then be informed as soon as possible.
5.3
Storage of Radioactive Material
5.3.1
All radioactive material (activity > 1EQ) must be kept in appropriately shielded containers that carry a label
indicating the name of the radionuclide (e.g., 32P), its activity (e.g., 50MBq) and date of the assay
(determination) of the activity (e.g., May 20 th, 2003). The label has to have the exact appearance (color and
wording) of the symbol shown in Fig. 5.3.1a below.
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5. Purchase, Reception, Storage and Transfer of Radioactive Material
5.3.2
All containers with radioactive material must be stored in a safe area, compartment or facility, which must
be lockable. (Freezers located in hallways, if permitted by the Fire Marshal, that contain radioactive
materials must be lockable).
The storage area has to be identified with the proper radiation warning sign shown in Fig. 5.3.1a (symbol
and writing - “RAYONNEMENT – DANGER – RADIATION” - in black or magenta on a yellow
background) if:
a) more than 100 exemption quantities (see Appendix 15 for a list of exemption quantities) of a radioactive
substance are stored in the area, or
b) there is a reasonable probability that a person in the area will be exposed to an effective dose rate
greater than 25µSv/hr (2.5mR/hr).
5.3.3
The storage location or facility must have sufficient shielding to reduce the radiation level to no more than
25µSv/hr (2.5mR/hr) in areas accessible to Nuclear Energy Workers only, and to a level not exceeding
2.5µSv/hr (0.25mR/hr) in areas accessible to other persons.
5.3.4
It is strictly forbidden to store or to consume any kind of food or beverage in an area where radioactive
material is used or stored.
5.3.5
Gaseous radioactive materials must be kept in a designated fume-hood provided with adequate
ventilation.
Figure 5.3.1a: Official Radiation Warning Signs
Figure 5.3.1b: Unofficial Radiation Warning Sign
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5. Purchase, Reception, Storage and Transfer of Radioactive Material
5.4
Transfer of Radioactive Material and Devices
5.4.1
The following instructions have to be observed when transferring radioactive material or radiation devices
(i.e., a piece of equipment that permanently incorporates a radioactive substance) to recipients elsewhere in
Canada:
a)
b)
c)
d)
5.4.2
It is the sender’s responsibility to make sure that the recipient has a valid CNSC license to accept the
shipment.
Valid leak test results have to be sent to the recipient of sealed sources.
Transfer records including date of transfer, the recipient’s license #, name and address, make, model,
serial # and name of nuclear substance or source as well as its activity with date of assay have to be
maintained.
Only certified radiation devices may be transferred to other users within Canada.
At the MNH/I, in addition to the above regulations, the following instruction has to be adhered to:
The RSO has to be informed of any intent by a responsible radiation user to transfer a radioactive source
(or device) to a third party at least one month prior to the planned shipping date, and then again at least
24hours before the actual time the shipment is scheduled to leave the MNH/I.
Nonobservance of this obligation may lead to a temporary suspension of the sender’s internal license.
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6. Radiation Monitoring
6.
Radiation Monitoring
6.1
General Principles
Monitoring of dose, dose-rate and internal contamination is an essential component of any program of
radiation safety. Such monitoring takes four forms:
a)
Area monitoring, i.e., measurement of radiation dose or dose rate at various points in a laboratory,
room or department where sources are stored, handled and applied.
b)
Procedure monitoring, i.e., measurement of radiation dose or dose rate received by specific
individuals and/or at specific locations, during particular procedures involving radiation sources.
c)
Personnel monitoring, i.e., measurement of the total dose received by individual workers
(mandatory for Nuclear Energy Workers) over a period of time.
d)
Monitoring of internal radioactivity to determine the level of gamma-emitting radioisotopes
ingested by workers. In addition, medical surveillance is an adjunct to radiation monitoring,
especially where over-exposure is known or suspected.
Another type of monitoring is concerned with radioactive contamination of laboratory surfaces, equipment
and personnel. These procedures are considered in Chapter 10.
6.2
Area and Procedure Monitoring
The responsibility for these types of monitoring rests with the Radiation Safety Officer. It is his/her duty to
carry out, either directly or by delegation, whatever surveys and measurements are needed to ensure that
room and equipment shielding are adequate to ensure a proper standard of radiation safety. Responsible
Radiation Users, heads of departments, departmental radiation supervisors and individual Nuclear Energy
Workers have the duty to collaborate with the RSO in this task and, in particular, to draw the RSO's
attention to any situation or procedure that warrants special investigation. In addition, Responsible
Radiation Users and/or heads of departments and departmental radiation supervisors have the responsibility
of carrying out whatever recommendations are made as a result of such investigations.
6.3
Personnel Monitoring
Nuclear Energy Workers are subject to routine, continuous monitoring of the radiation dose received from
external sources by means of a Thermoluminescent Dosimeter (TLD) badge. TLDs are the official
dosimeters for dose measurements for external beta and gamma radiation and must be worn by Nuclear
Energy Workers. Radiation exposure monitoring with TLDs may be performed on any individual handling
radioactive substances or devices, or working in the vicinity of sources of radiation, in mutual agreement
between the worker and the RSO. The dosimeter service at the MNH/I is provided by the National
Dosimeter Service (NDS) of the Radiation Protection Bureau (RPB) of Health Canada, which
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6. Radiation Monitoring
is a service of the Federal Ministry of Health and Welfare. The RPB is a provider of dosimetry services
recognized by the CNSC.
Depending on the service requested by the various radiation users, TLDs are provided periodically by the
RPB at intervals of ½, 1 or 3 months. The distribution within the Hospital and the Institute is undertaken by
the RSO and/or his/her assistant. The TLD service for Radiology at the MNH/MUHC is handled by the
manager of this department via the MUHC. He also sends a copy of the exposure reports to the RSO.
Exposed TLDs are read and records maintained by the RPB as well as by the RSO. Exposure reports are
examined by the RSO and any unusually high doses are subject to investigation by the RSO. Formal action
levels (ALs) have been established for NEWs working at the Medical Cyclotron Facility and in the PETSuite (Nuclear Medicine) of the MNH/I. The informal internal action level for all other radiation users is
background level, for on very rare occasions only do their doses exceed background levels).
What is a radiation badge?
The radiation badge (TLD) consists of two square elements which are made of lithium fluoride (LiF)
mounted on a removable metal insert. The TLD element with the very thin aluminized Mylar light shield
detects beta radiation. This element measures the shallow equivalent dose, or the surface or skin dose. The
other element is covered by a layer of aluminum, a radiation attenuator, whose thickness is equivalent to
1cm of tissue. This element measures the equivalent dose at a depth of 1cm or more in tissue, usually called
the body dose (H10). A reading of the skin dose (H07) is obtained with the same TLD.
Lithium fluoride is a thermoluminescent compound. When a thermoluminescent material is exposed to
ionizing radiation, some electrons freed by ionization get enough energy to move through the crystal lattice.
Some of the free electrons get trapped in imperfections in the crystal lattice where they remain until
subjected to high temperatures. Upon heating, the trapped electrons are evicted and promptly undergo
recombination, releasing their surplus energy in the form of light. The light emitted is measured with
photo-tubes. The amount of light emitted is proportional to the number of trapped electrons, which in turn
is proportional to the dose received by the individual wearing the TLD.
Wearing a radiation badge does not protect the wearer from radiation - it is merely a means of monitoring
the radiation each individual is exposed to. See Appendix 14b (Proper Care and Use of Personal
Dosimeters) for more details on the proper use of TLDs.
Remember and practice the three rules for radiation safety in the workplace:
1)
minimize exposure time
2)
maximize the distance from the radiation source (remember: the radiation intensity drops
as the inverse square of the distance between the source and the worker)
3)
use adequate shielding to keep your exposure levels low
Who needs a TLD radiation badge?
TLDs have an important inherent limitation in that they are insensitive to weak beta radiation such as that
from H-3, C-14 and S-35.
Personnel who work in labs which use only these isotopes do not need dosimeters. They might, however,
be subject to other forms of radiation monitoring (see paragraph 6.4 on bioassays).
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A TLD radiation badge is appropriate if:
1)
you use radioisotopes other than H-3, C-14 and S-35 in your work
2)
you work with more than 50MBq (~ 1.5mCi) of P-32; in this case you also need an extremity
(finger) ring TLD monitor as required by CNSC regulations (remember to wear the ring monitor
such that the TLD crystal faces the palm of the hand where the handled radioisotope is closest ).
your work-space is located in close proximity to an area where substantial amounts (> 370 MBq )
of radioisotopes (other than H-3, C-14 and S-35) are regularly being used.
you are pregnant and have chosen to continue working in an environment where you may be
exposed to radiation.
3)
4)
A TLD monitor may be obtained from the RSO upon completion of the “TLD Monitor
Application” form (see Appendix 4b).
6.3.1
6.3.2
The individual Worker or Nuclear Energy Worker is responsible for:
a)
taking good care of the monitor at all times (the RPB charges $75.00 for a lost or damaged TLD)
b)
wearing the monitor at work whenever there is a possibility of exposure to radioactivity. The
monitor is best worn at chest height. When a lead apron or protective clothing is worn, the
monitor should be carried under the apron, since its job is to record the radiation reaching the
body, not the radiation reaching the apron
c)
guarding the monitor as a personal monitor, issued to a named individual. Under no
circumstances may a monitor be loaned to another person or otherwise used to record doses
received by more than one individual
d)
taking care that the monitor does not accidentally drop onto the floor or onto any place (e.g., a
radiographic table) where it might accidentally become exposed to a direct radiation beam
e)
taking care that the monitor is not accidentally splashed or otherwise contaminated by a
radioactive solution
f)
taking care that, outside working hours, the monitor is left in a safe place which is well away from
any radiation source and from any source of intense heat, including a radiator. (See Appendix 14b
for information about proper use and care of personal dosimeters)
Personnel monitoring of the type described in the previous two sections is a satisfactory general indicator
of whole-body dose due to external X or gamma-radiation. However, the externally worn TLD has some
important limitations:
a)
it does not record the additional dose received by the hands, limbs or face in some procedures.
b)
it does not record exposure arising from ingestion or inhalation of radioactive materials.
c)
it does not record doses due to low-energy beta rays such as those from tritium, carbon-14 and
sulphur-35.
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6. Radiation Monitoring
d)
it does not record doses due to neutrons. However, special neutron monitors are available from the
RBP upon request. (The decision to monitor neutron doses should be made by the RSO in
consultation with the departmental radiation supervisor).
6.4
Monitoring of Internal Radioactivity requires the setting up of special sensitive equipment for external
counting of gamma radiation from radioisotopes deposited in the body. As an example the routine
measurement of radio-iodine uptake in the thyroid is carried out by using a calibrated thyroid rate meter
capable of detecting at least 1kBq of I-125 or I-131 (license condition 2600). Calibration phantoms to
verify the sensitivity of the rate meter are available from the RPB. Workers in this category should be
monitored as stipulated in the license conditions on bioassays (e.g. license conditions 2046-7, 2600-1 and
2601-4 for thyroid monitoring).
6.4.1
Who should be bio-assayed? 2)
A bioassay program is required for radiation users who work with significant amounts of volatile radioiodine in a soluble, inorganic form or in organic form which can be metabolized in the body to produce
iodide.
Activity levels above which bioassay for iodine-125 and iodine-131 (see Appendices 14k and 14l for
further safety information) is required within 5 days following exposure (CNSC license condition 2046-7):
Type of operation or event
Activity handled (or involved) at a single time
Processes carried out in open room
>5MBq
(135 Ci)
Processes carried out in fume hood
>50MBq
(1.350mCi)
Processes carried out in a glove box
>500MBq
(13.5mCi)
Any CNSC-approved containment
Any CNSC-approved quantity
Involvement in spill
>5MBq
External contamination on body
Any activity
(135 Ci)
Pregnant workers should not be allowed to handle volatile radio-iodine.
2)
see CNSC documents C-58, C-201 and R-58
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6. Radiation Monitoring
6.5
Medical Surveillance
6.5.1
A Nuclear Energy Worker whose dose in the preceding 12-month period, as evidenced by personnel
exposure records, exceeds 50mSv must undergo a medical examination. This is also required in case of
accidental over-exposure (real or suspected) of radiation or non-radiation staff or members of the public.
Where the over-exposure is severe, i.e., 200mSv or more, a cytogenetic examination is required.
(Recommendations by the RSC).
6.5.2
The CSST (Commission de Santé et Sécurité au Travail) has the authority to require the temporary
suspension of an employee from work involving the possibility of radiation exposure and the transfer of the
employee to other duties.
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7. Collection and Disposal of Radioactive Waste
7.
Collection and Disposal of Radioactive Waste
7.1
General Principles
The use of radio-nuclides or radio-pharmaceuticals usually gives rise to radioactive waste which has to be
disposed of in an authorized and safe manner. The waste may include residual amounts of the original
radio-nuclides, generators of short-lived radio-nuclides, disposable containers (vials, etc.), radioactive
samples, contaminated solids and radioactive animals. The method of disposal depends on the nature and
activity of the waste, in particular on whether the waste is solid or liquid, is chemically toxic, and contains
sufficient radioactivity to render it a potential hazard.
With the transition from the AECB to the CNSC in June 2000, the rules on radioactive waste disposal also
have changed. For example, the Scheduled Quantity approach is no longer valid.
7.2
Collection and Storage of Radioactive Waste in the Laboratory
The collection and storage of radioactive waste in the laboratories and/or collection center of the MNH/I
(metal cage in room B045) must be carried out according to the principles of radiation safety. As of March,
2004, the MNH/I has adopted McGill’s computerized Radio-Isotope Tracking System (RTS) which is
administered by the Waste Management Facility (call ext. 5066 for information). Strict adherence to the
rules governing this system is required by all radioisotope users.
7.2.1
In each laboratory, an area must be designated for the temporary storage of waste, preferably well out of
the usual traffic. Use proper radiation warning signs to outline this area (depending on the activity, the
regular sign, Fig. 5.3.1a, or the unofficial black sign on white background, Fig. 5.3.1b, may be used).
7.2.2
Laboratories are provided with labeled solid and liquid waste containers from the McGill Waste
Management Facility (call your RSO or ext. 5066 if supply is short). The empty containers are available
from the central radioactive disposal area in the basement (room B045). The key to this room has to be
signed out from the security front desk on the first floor.
7.2.3
Storage of radioactive waste must conform to the guidelines stated in 5.3.3. (Adequate shielding must be
used.)
7.2.4
Radioactive liquids must be placed in white plastic containers (1 or 4 liter).
Radioactive solids must be placed in the cardboard boxes (dry solid waste) or white plastic containers (if
only small amounts of waste present, but do not mix solid and liquid waste).
Note: In order to save money and valuable public waste storage space, the McGill WMF will store
radioactive waste according to half-life and will let decay the short-lived radio-isotopes until they are no
longer considered a radiation hazard and may be disposed of via regular garbage.
The radio-isotopes falling in this category are: P-32, P-33, S-35 and I-125. In order to assist the McGill
WMF in this effort, it is essential that you use separate containers for each of these four radioisotopes.
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7. Collection and Disposal of Radioactive Waste
Do not mix containers and tag them properly. Remember, one container, one isotope! The adoption of
McGill’s computerized Radio-Isotope Tracking System (RTS) facilitates this process.
7.2.5
Spill trays or absorbent material must be placed under each waste container in the labs.
7.2.6
Liquid scintillation vials (well capped!), whether bio-degradable or not, go into large metal drums (kept
in the central storage area) with the abbreviation “LSV” written on the lid. The inventory attached to the
lid of the barrel has to be filled in (disposal date, radionuclide and approximate activity).
Users of liquid scintillation counting are urged to use water-miscible bio-degradable scintillation
fluids unless there is a good reason for not doing so.
7.2.7
Identification labels on each container, listing the activity and radionuclide contained within, as well as the
name of the Responsible Radiation User and the date the activity was measured, have to be completed in
full. In particular, the RTS number (generated by the RTS program) has to be written onto each waste
container.
7.2.8
Only properly identified containers will be picked up. The RTS number of each container brought to
the central collection area has to be transcribed into the log book placed on the LSV barrel. (The
driver collecting the waste will use this log book to indicate which containers had been collected on which
date).
7.2.9
Pointed materials should be put in containers (sharps) identified with a yellow label. As soon as the
containers become full, they should be delivered to the central collection area located in the basement of
the MNI, room B045. and disposed of following RTS rules.
Keys to the radioactive waste storage room B045 are available upon signing a book, at the front desk
(security, main floor) 24 hours a day, 7 days a week.
7.2.10
Do not overfill containers in order to avoid spills that might occur during handling and transfer of waste
containers. Make sure you remove all radiation warning signs from waste items of any kind.
7.3
Disposal of Radioactive Waste from the Central Collection Area
7.3.1
Disposal of Regular Solid, Liquid or Gaseous Radioactive Waste
Since the coming into effect of the new Nuclear Safety and Control Regulations in June 2000, the RSC has
decided that, at the MNH/I, all radioactive waste shall be disposed of via the McGill Waste Management
Facility (phone: 398-5066), which also supplies the containers.
No radioactive waste shall be disposed of via regular garbage, sewer or ventilation systems,
except for:
1)
2)
3)
rinsing water from the final washing of radioactive utensils after initial cleaning
residual minor fumes from the storage of volatile radioactive material in fume hoods
limited quantities of short-lived radioactive gases from the medical cyclotron facility (see Safety
Report for Cyclotron Facility)
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7. Collection and Disposal of Radioactive Waste
4)
regulatory quantities of radioactive waste as specified in the CNSC license.
Before applying the provisions made in the individual CNSC licenses for the use of the public garbage,
sewer and atmospheric routes for disposal of radioactive waste, the RSO should be consulted, since the
lawful application of these provisions requires the knowledge and observation of additional data with
regard to the quantities of radioactive waste generated at the MNH/I.
7.3.2
Disposal of Animal Carcasses
Radioactive animal carcasses are also picked up by the McGill Waste Management Facility. Laboratory
workers who want to get rid of a radioactive animal carcass must insert the carcass into two (2) plastic
bags with an identification tag attached, displaying the name of the Responsible Radiation User (lab
director), the isotope used and its activity, and the date when the animal was killed. The carcass is then
brought to the freezer of the Animal Quarters, located on the eighth floor of the Penfield Wing of the
MNH/I. The carcass will be stored there along with bio-hazardous waste and non-radioactive carcasses
until they are picked up.
The Animal Quarters have controlled access, but workers of the facility will provide access to the freezer
from 8h30 to 16h30.
7.3.3
The identification tag provided by the McGill Waste Management Facility, if used alone, specifies the
waste as Class I under the Canadian Transport Commission Regulations (i.e., Category I). Therefore, the
Responsible Radiation User must ensure that the dose rate at the surface of each container leaving the
laboratory is less than 5µSv/hr. If this condition is not met, then Category II or Category III labels must be
attached to the container. See section 5.2.
7.4 Disposal of Irregular Radioactive Waste
On rare occasions, you might have to get rid of a piece of equipment that had served for radiation-related
purposes (e.g., a centrifuge, a target box from the cyclotron etc.) and therefore might be radioactive. In this
case, contact your RSO. It will be absolutely essential to remove all radiation warning signs from the piece of
equipment should it be decided that the item may be discarded as a non-radioactive object (regular garbage,
scrap yard etc.).
This also applies to empty shipping containers that served to send the various radioactive substances to your
laboratory. It is essential that you remove all radiation warning labels from such containers once they no
longer contain any radioactive material. Non-compliance with this directive will correctly be criticized by
CNSC inspectors as “frivolous“ use of radiation warning signs.
Non-contaminated (wipe tested!) empty lead containers may be placed in the container labeled “ lead pigs”
put in the waste storage cage from time to time (room B045); or arrangements may be made with the supplier
who might take the containers back for recycling. Remember, lead cannot be disposed of via regular garbage!
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8. Safety Guidelines for Diagnostic Radiology
8.
Safety Guidelines for Diagnostic Radiology
The guidelines in this section are based on Safety Code 20 A, prepared by the Radiation Protection Bureau
of the Federal Ministry of Health and Welfare, and a draft version of the “Guide Normatif en
Radioprotection Hospitalière (Radiologie Diagnostique)” of the Quebec Ministry of Health and Social
Services.
8.1
General Recommendations
8.1.1
X-ray equipment must be operated only by properly trained individuals.
8.1.2
An x-ray room must not be used simultaneously for more than one radiological investigation.
8.1.3
All personnel must take full advantage of the protective devices available.
8.1.4
No person whose presence is not essential for the investigation may be in an x-ray room when an exposure
is carried out.
8.1.5
Personnel must at all times keep as far away from the useful beam as is practicable. Exposure of personnel
to the useful beam must never be allowed unless the beam is adequately attenuated by the patient and by
protective clothing or screens.
8.1.6
Operators should remain inside the control booth or behind protective screens when making an x-ray
exposure. If, for special reasons, this is impractical, protective clothing must be worn.
8.1.7
When there is a need to support children or weak patients, holding devices should be used. If parents,
escorts or other personnel are called to assist, they must be provided with protective aprons and gloves and
be positioned so as to avoid the useful beam and to minimize exposure to scattered radiation. No one
person should regularly perform these duties.
8.1.8
All entrance doors to an x-ray room, including patient cubicle and preparation room doors, should be kept
closed and secured while a patient is in the room.
8.1.9
An x-ray tube housing must not be held by hand during operation.
8.1.10
X-ray machines which are energized and ready to produce radiation must not be left unattended.
8.2
Recommendations for Operation of Radiographic Units
8.2.1
The x-ray exposure should, as a general rule, be controlled from the control panel located inside the control
booth or behind a shielded wall. For techniques requiring the operator to control the exposure while at the
side of the patient, appropriate protective clothing must be worn.
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8. Safety Guidelines for Diagnostic Radiology
8.2.2
The operator must have a clear view of the patient during every exposure and be able to communicate with
the patient and/or attendants without leaving the control booth.
8.2.3
Film cassettes must never be held by hand during an exposure.
8.3
Recommendations for Operation of Fluoroscopic Units
8.3.1
All persons required to be in the room during a fluoroscopic procedure should wear protective aprons.
Lead shields or curtains mounted on the fluoroscopic unit must not be considered a sufficient substitute for
protective clothing.
8.3.2
Protective gauntlets should be worn by the radiologist during every fluoroscopic examination. During
fluoroscopy, palpation with the hand should be kept to a minimum.
8.3.3
During fluoroscopy and spot film operation, associated personnel required to be at the side of the patient
must wear appropriate protective clothing.
8.3.4
All fluoroscopic examinations should be carried out as rapidly as possible and with minimum dose-rate and
x-ray field size compatible with the diagnostic requirements.
8.4
Recommendations for Operation of Mobile Units
8.4.1
Mobile units shall be used only if the condition of the patient is such as to make it inadvisable for the
examination to be carried out with a permanent unit in the main x-ray department.
8.4.2
During operation, the primary beam should be directed away from other occupied areas if at all possible,
and every effort must be made to ensure that the beam does not irradiate any other person in the vicinity of
the patient.
8.4.3
The operator must stand at least 3 meters from the x-ray tube and out of the direct beam.
8.4.4
The operator should wear a leaded apron when exposures are made.
8.4.5
In a capacitor discharge unit (if still in use), a residual charge is left in the capacitors after an x-ray
exposure has been made. This charge can give rise to a "dark current" and result in x-ray emission even
though the exposure switch is not activated. The residual charge must therefore be fully discharged before
the unit is left unattended.
8.5
Recommendations for Special Radiological Procedures
8.5.1
In these procedures, the radiologist and other personnel in the vicinity of the patient can be subjected to
appreciable scattered radiation from the patient when the x-ray beam is on. The radiologist and other
personnel should wear protective glasses and clothing and remain as far away from the patient as practical.
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8. Safety Guidelines for Diagnostic Radiology
The protective devices (e.g., shield panels, leaded drapes, extended collimator cones, etc.) provided with
the x-ray equipment should be used whenever they do not interfere unduly with the diagnostic procedure.
The smallest x-ray field consistent with the procedure should be used. When possible, pulsed fluoroscopy
should be used.
8.5.2
Angiography: Angiography is potentially one of the main sources of exposure to personnel in diagnostic
radiology, since it requires the presence of many personnel close to the patient and involves fluoroscopy for
extended periods of time and multiple radiographic exposures. For such procedures, all personnel must be
aware of the radiation hazards involved and make every effort to adhere to the recommendations below:
a)
Full use must be made of the protective devices provided with x-ray equipment (e.g., shielded
panels, leaded drapes, bucky slot covers, etc.).
b)
All personnel must wear protective clothing and personal dosimeters, which might include head
and hand (finger ring type) dosimeters. Protective glasses should also be worn.
c)
All personnel who are not required to be immediately adjacent to the patient when the radiation
beam is activated must stand back as far as possible and, if at all possible, behind a protective
shield.
d)
When possible, pulsed fluoroscopy should be used.
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9. Procedures for Minimizing Dose to Patients
9.
Procedures for Minimizing Dose to Patients
The following recommendations for the protection of the patient are directed toward the physician, the
radiologist, and the operator. They provide guidelines for the elimination of unnecessary radiological
procedures and for minimizing exposure of patients to radiation when a radiological examination is
indicated.
9.1
Guidelines for the Prescription of Diagnostic X-Ray Examinations
The medical practitioner is in a unique position to reduce unnecessary radiation exposure to the patient by
eliminating examinations that are not clinically justified. The practitioner can achieve this by adhering, as
far as possible, to the following recommendations:
9.1.1
The prescription of an x-ray examination of the patient should be based only on a clinical evaluation of the
patient and should be for the purpose of obtaining diagnostic information or carrying out specialized
interventional procedures.
9.1.2
Routine or screening procedures, such as for pre-employment examinations, tuberculosis or mass
mammographic screening etc., in which there is no prior clinical evaluation of the patient, should not be
prescribed.
9.1.3
The practitioner shall determine whether there have been any previous x-ray examinations that would make
a further examination unnecessary, or would allow the ordering of an abbreviated examination. The
previous radiographs should be examined along with a clinical evaluation of the patient.
9.1.4
When a patient is transferred from one physician or hospital to another, any relevant radiographs should
accompany the patient and should be reviewed by the consulting physician.
9.1.5
When prescribing a radiological examination, the physician should specify precisely the clinical indications
and information required.
9.1.6
The number of radiographic views required in an examination should be kept to the minimum consistent
with the clinical objectives of the examination.
9.1.7
In prescribing an x-ray examination of a pregnant or possibly pregnant woman, full consideration should be
taken of the consequences of fetal exposure. (See section 9.2)
9.1.8
If the radiograph contains the required information, repeat exposures should not be prescribed simply
because a radiograph may not be of the "best" diagnostic quality.
9.1.9
Specialized studies should be undertaken only by, or in close collaboration with, a qualified radiologist.
9.1.10
Staff must not operate x-ray equipment, or be responsible for the use of such equipment, unless qualified to
do so (i.e., physicians or members of the ORTQ).
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9. Procedures for Minimizing Dose to Patients
9.1.11
Radiographs must be monitored routinely to ensure that they satisfy diagnostic requirements with minimal
patient exposure.
9.1.12
A patient's imaging record should include details of all x-ray examinations carried out (e.g., kV & mAs)
9.2
Guidelines for Radiography in Pregnant Women
The following recommendations apply to x-ray examinations involving pregnant or potentially pregnant
women.
9.2.1
Only essential investigations should be undertaken in the case of a pregnant or suspected pregnant woman.
9.2.2
Elective radiography of the abdominal and pelvic area in a pregnant woman must be avoided. ("Elective"
is taken to mean an examination of the abdomen and pelvis that does not contribute to the diagnosis or
treatment of a female patient in relation to her immediate illness.)
9.2.3
When radiography of the pelvic area or abdomen is required, the exposure must be kept to the absolute
minimum necessary and full use must be made of gonadal and other protective shielding if the clinical
objectives of the examination will not be compromised.
9.2.4
If a radiographic examination of the fetus is required the prone position should be used. This has the effect
of shielding the fetus from the softer x-rays and hence reducing the fetal dose.
9.2.5
Radiography should not be used for the determination of abnormal presentations of the fetus or for
placental localizations. Other techniques such as ultrasonography are better suited for this purpose and are
less hazardous.
9.2.6
Radiography of the chest, extremities, etc., of a pregnant woman, for valid clinical reasons, should only be
carried out using a well-collimated x-ray beam and with proper regard for shielding of the abdominal area.
9.3
Recommendations for Reducing Gonadal Dose to the Patient
Radiologists and technologists must pay special attention to four factors that are important for reducing
gonadal dose to the patient.
9.3.1
Correct collimation of the x-ray beam. It is insufficient merely to limit the beam to the size of the image
receptor: care should be taken to further restrict the beam to the region of the patient's body that is of
diagnostic interest. Irradiation of any part of the body outside that region contributes nothing to the
examination and increases the dose to the body and to the gonads.
9.3.2
Gonadal shields. Appropriate use of specific-area gonadal shielding is strongly advised when:
a)
the gonads of necessity lie within, or are in close proximity to, the primary x-ray beam;
b)
the patient has reproductive potential; and
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9. Procedures for Minimizing Dose to Patients
c)
clinical objectives will not be compromised.
9.3.3
Appropriate selection of technique factors. An appropriate selection of tube voltage, current and filtration,
is particularly important for diagnostic procedures in which the gonads lie within or near the primary x-ray
beam. For example, in fluoroscopy, use of higher tube voltage and filtration and lower tube current will
almost always reduce the gonadal dose.
9.3.4
Sensitivity of imaging systems. The gonadal dose is inversely proportional to the sensitivity of the imaging
system. Thus, doubling the sensitivity halves the gonadal dose; conversely, halving the sensitivity doubles
the gonadal dose. It is therefore very important to maintain the sensitivity of the imaging system at its
optimum value and to be alert for any significant deterioration. In this sense, semi-dark adaptation for
image-intensified fluoroscopy is important.
9.4
Guidelines for Carrying Out X-Ray Examinations
The recommendations that follow are intended to provide guidance to the operator and radiologist in
exercising their responsibility towards reduction of patient exposure.
9.4.1
General Recommendations
a)
The operator must not perform any examination which has not been prescribed by the physician
responsible for the patient.
b)
The exposure of the patient must be kept to the lowest practicable value, consistent with clinical
objectives and without loss of essential diagnostic information. To achieve this, techniques
appropriate to the equipment available should be used.
c)
Particular care, consistent with recommendations of Section 9.2, must be taken when radiological
examinations of pregnant or potentially pregnant women are carried out.
d)
The x-ray beam must be collimated so as to restrict it as far as practicable to the area of diagnostic
interest.
e)
The x-ray beam size must be limited to the size of the image receptor or smaller.
f)
The x-ray beam should not be directed towards the gonads unless it is absolutely essential, in
which case gonadal shielding is strongly advised.
g)
Shielding should be used where appropriate and practicable to limit the exposure of body tissues.
It is particularly important that a special effort be made to protect the blood-forming organs,
gonads and thyroids of children.
h)
The target-to-skin distance should be as large as possible, consistent with good radiographic
technique.
i)
For young children, special devices should be employed to restrict movement.
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9. Procedures for Minimizing Dose to Patients
j)
9.4.2
Full details of the radiological procedures carried out should be noted on the patient's imaging
records.
Recommendations for Radiographic Procedures
a)
The edges of the x-ray beam should be seen on all x-ray films to ensure that no more than the
desired area has been irradiated. The film size used should be as small as possible, consistent with
the diagnostic objectives of the examination.
b)
Screen-type film should not be used for non-screen techniques because it is less sensitive to direct
x-radiation than non-screen film.
c)
The fastest film or intensifying screen-film combination, consistent with diagnostically acceptable
results, should be used. When highest definition is not required a high-speed film-screen
combination should be used. X-ray intensifying screens made from rare earth phosphors should
be used where appropriate.
d)
To ensure that patient exposure is kept to a minimum consistent with image quality, full advantage
should be taken of a combination of techniques such as:
-
use of an anti-scatter grid between the patient and the image receptor.
-
use of the optimum focus-to-film distance appropriate to the examination.
-
use of the highest kilovoltage that produces films of good quality.
-
use of automatic exposure control devices designed to keep all exposures and repeat exposures to
a minimum.
e)
The radiographer should see the films after processing in order to verify that the techniques being
used are producing diagnostic quality films and that the x-ray equipment is functioning correctly.
f)
Before taking a long series of films, it is particularly important to avoid the need for retakes by
taking and processing a preliminary film in order to verify the correctness of the machine settings.
9.4.3
Recommendations for Fluoroscopic Procedures
a)
In view of the relatively high exposure that results from fluoroscopy, such procedures should not be carried
out when an equivalent result can be obtained from radiography. Fluoroscopy must not be used as a
substitute for radiography.
b)
Fluoroscopy must only be carried out by, or under the immediate supervision of, a radiologist or physician
properly trained in fluoroscopic procedures.
c)
A fluoroscopic procedure should be carried out as rapidly as possible with the smallest practical x-ray field
size.
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9. Procedures for Minimizing Dose to Patients
d)
The exposure rate used in fluoroscopy should be as low as possible and must not exceed 5 Roentgens per
minute at the position where the central axis of the x-ray beam enters the patient.
e)
The ambient light level in the fluoroscopic room should be set as low as possible.
f)
Image intensification must be used in order to reduce patient exposure. Image intensifiers can significantly
reduce both exposure rate and exposure time. However, the operator must monitor the x-ray tube current
and voltage on equipment with automatic brightness control, since both can rise to high values without the
knowledge of the operator, particularly if the gain of the intensifier is decreased.
g)
Television monitoring should be used in conjunction with the image intensifier.
h)
Mobile fluoroscopic equipment should be used only for examinations where it is impractical to transfer
patients to a permanent fluoroscopic installation.
i)
Whenever possible, pulsed fluoroscopy should be used in order to reduce the dose to the patient and the
operator.
9.4.4
Recommendation for Special Procedures
a)
Significant exposure to the patient's eyes can result from neurological radiography, such as carotid
angiography. An eye shield, therefore, should be used in projections where it does not interfere
with the diagnostic information sought.
b)
During angiography, significant exposure of the patient's thyroid gland can occur. Appropriate
shielding should be used whenever possible.
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10. Use of Unsealed Radioisotopes
10. Use of Unsealed Radioisotopes
10.1
General Principles
10.1.1
The internal permit holder shall ensure that only persons who are properly trained in work with radioactive
materials and informed of the hazards involved are allowed to handle radioisotopes. Any other individual
who handles radioactive material shall do so only temporarily (until her/his training is completed), and
under the supervision of a trained person.
10.1.2
A copy of the relevant Internal Permit shall be prominently displayed on the permit holder's premises in
each location where radioactive substances are handled or stored, while the consolidated license from the
CNSC is kept by the RSO.
10.1.3
A copy of the proper CNSC poster with the subtitle “Use of Unsealed Nuclear Substances” shall be
prominently displayed in each laboratory where radioisotopes are used. This poster has to correspond to the
level of radioactivity being used in the area of the laboratory under consideration.
The Classification of Areas is specified in the corresponding CNSC license and reads as follows:
Each area where more than one exemption quantity (EQ) is used at a single time shall be classified as:
a)
basic-level if the quantity does not exceed 5 ALI
b)
intermediate-level if the quantity used does not exceed 50 ALI
c)
high-level if the quantity does not exceed 500 ALI
d)
containment-level if the quantity exceeds 500 ALI
e)
special purpose area, e.g. Nuclear Medicine
The Annual Limit on Intake (ALI) is a quantity that has to do with the radiation dose from ingestion or
inhalation of a specific radioisotope and its relation to accepted radiation dose limits. More on the ALI may
be found in ICRP Publication 61, where a table of ALI values for the majority of radio-isotopes is given. A
summary of ALI and EQ values for the most frequently used radio-isotopes is also given in Appendix C to
CNSC License Application Guide C-237 as well as in Appendices 15, 16 and 20 of this manual.
10.2
Classification of Laboratories
10.2.1
Based on the above classification, in laboratories falling into the basic-level category, the “Basic Level”
poster (INFO-0728-1) shall be shown. For areas in the intermediate-level category, the “Intermediate
Level” poster (INFO-0728-2) applies and for high-level areas, the “High Level” poster (INFO-0728-3).
Finally, a room is classified as “Nuclear Medicine” for the use of unsealed nuclear substances where
diagnostic or therapeutic nuclear medicine procedures are performed. In these rooms, the “Nuclear
Medicine” poster (INFO-0728-4) has to be displayed.
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10. Use of Unsealed Radioisotopes
Copies of the four posters mentioned above are included as Appendices 14e, 14f , 14g and 14h of this
manual.
10.2.2
Any laboratory or area in which unsealed radioisotopes are stored, handled, or used shall be equipped in
accordance with the AECB Regulatory Document R-52, Rev. 1 (June, 1991). This code, entitled "Design
guide for Basic and Intermediate level Radioisotope Laboratories", details the facilities (including surface
finishes, bench tops, fume hoods, air movement, floors, sinks and drains) required in laboratories
designated as "Basic level", "Intermediate level" or "High level". Copies of this code are available through
the RSO. (N.B: A well functioning fume hood should have an air flow with a face velocity of 80 to 100
linear feet per minute with a sash opening of 30cm).
10.2.3
Most laboratories used for tracer investigations are of the "basic level" type (i.e., essentially a good
chemistry laboratory), but upgrading of such laboratories to "intermediate level" is required wherever the
activity of open sources handled at any one time exceeds 5ALIs (example: a user might avoid upgrading a
lab by ordering several vials containing less than 5ALIs each).
10.2.4
The maximum activity of an unsealed radioactive material that may be used in a laboratory of a given
classification depends on its ALI, which is linked to the "radio-toxicity" of the radioisotope concerned and
the type of procedure undertaken. Appendix 2 gives the radio-toxicity classification of various
radioisotopes.
10.3
Handling of Unsealed Radioisotopes in Laboratories
10.3.1
In any laboratory where both radioactive and non-radioactive work is carried out, a separate area must be
set aside and clearly designated as the "radioactive area". (Do not use the official yellow and black, or
yellow and magenta, radiation warning labels for outlining this area; rather use another type of warning
label, e.g., an “unofficial” black on white background radiation warning sign).
10.3.2
Smoking, eating, drinking and storage of food or drink are prohibited in any area used for storage, handling
or use of radioactive material.
10.3.3
Pipetting of radioactive solutions must not be carried out by mouth.
10.3.4
Procedures involving radioactive materials should be carried out in trays or on benches lined with
disposable absorbent material. Secondary containments should be used for all radioactive liquids.
10.3.5
Procedures that might produce airborne contamination (e.g. iodination with I-125 etc.) should be carried
out in a fume hood. In any case, some method of containment should be adopted.
10.3.6
Procedures involving dry radioactive powdered materials should be carried out in a glove box.
10.3.7
Laboratories must be kept locked when not in use. (Freezers that are kept in the hallways, if permitted by
the Fire Marshall, must be locked at all times).
10.3.8
Protective gloves and clothing must be worn at all times.
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10. Use of Unsealed Radioisotopes
10.3.9
10.3.10
After handling unsealed radioactive materials, and before leaving the laboratory, the operator must wash
his/her hands.
Equipment, tools and utensils used for work with radioactive materials should not be used for other
purposes and should be surveyed for contamination prior to removal from the laboratory.
10.3.11 Wipe tests must be performed on surfaces and equipment that may become contaminated with radioactive
material. These tests must be done weekly and also after each significant work-load. Records of these tests
must be properly documented and filed in a log-book. In particular, areas that read three times background
level have to be decontaminated and wipe-tested again ! (See Appendices 10, 11 and 17 for contamination
–related topics).
The following exception has been granted by the CNSC: Wipe tests are not required when working only
with the following short-lived (PET) radioisotopes: C-11, N-13, O-15 and F-18. All other license
conditions
however apply!
10.3.12
Before any radioisotope facility is decommissioned, a radiation survey shall be performed and
appropriate actions shall be taken to decontaminate any areas where the count rate is above background.
At the same time, the form “Request for Decommissioning Radioisotope Laboratory” (see Appendix 13
for a copy of the form) has to be completed by the RRU and sent to the RSO.
10.3.13 Animals used in experiments involving radioactive material shall be housed in a separate enclosure and all
waste, including carcasses, shall be treated as radioactive (see section 7.3.2).
10.3.14 Investigators working in the microPET laboratory and their associates or assistants - performing research
studies in the microPET-Suite but not handling radioactive substances themselves - shall, in compliance
with CNSC regulations, read and sign, in the presence of an authorized individual, the “microPET
Investigators Radiation Safety Information Sheet “ (see Appendix 19).
10.3.15 Investigators working in the microPET laboratory and their associates or assistants shall make sure that the
positron emitting radiopharmaceutical used in the experiment is transferred from the cyclotron
radiochemistry facility of the MNH/I to the microPET laboratory by an authorized individual following the
protocol described in the abovementioned information sheet (see Appendix 19).
10.4
Handling of Radioisotopes in the Department of Nuclear Medicine
PET procedures are carried out with radio-nuclides such as: 15O (T1/2=124s), 13N (T1/2=10 min), 11C (T1/2=
20 min), and 18F (T1/2=110 min). These radio-nuclides are positron emitters and are produced by the
medical cyclotron located in the basement of the MNH/I.
Some of the PET tracers such as the radioactive gases 15O -CO or 15O-CO2 produced at the
radiochemistry laboratory in the cyclotron facility are sent directly to the PET unit by means of a system
of stainless steel tubes, so that the exposure to personnel is minimal, and the gases are utilized for imaging
(inhalation studies) without delay .
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10. Use of Unsealed Radioisotopes
Some non-volatile compounds are also produced at the cyclotron facility. These ready-to-inject
compounds, such as 18F-FDG, are shipped to the PET scanning suite via a pneumatic system.
In addition to the precautions recommended in section 10.3, staff undertaking radioisotope procedures
directly involving patients in the Positron Emission Tomography (PET) Unit, or elsewhere, are required to
adhere to the practices outlined below.
10.4.1
Syringes or needles used for injection of radioactive material should be kept separate from those used for
non-radioactive work.
10.4.2
Used syringes or needles containing residues of radioactive material should be separated from other
radioactive waste.
10.4.3
Disposable gloves should be worn during preparation and during injection of radioactive material.
10.4.4
Procedures involving a radioactive gas must be carried out in such a way that no diffusion of the
radioactivity into the immediate environment is possible; and these gases are dispersed into the outside
environment according to the procedure described in Section 7.3.
10.4.5
PET researchers and their associates or assistants, performing PET research studies in the PET-Suite
without handling radioactive substances themselves, shall, in compliance with CNSC regulations, read and
sign, in the presence of an authorized individual, the “PET Investigators Radiation Safety Information
Sheet“ (see Appendix 18).
Remember that:
lab coats must be worn at all times when working with radioactive materials;
-
eating and drinking is prohibited in the scanning room;
-
TLDs must be worn when there is possibility of exposure;
-
a contamination meter in good working order must be readily available in case of spills and to
verify contamination;
-
the ALARA principle must be applied here as well.
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11. Radiation Safety in the Wards
11. Radiation Safety in the Wards
Sources of ionizing radiation may be encountered in a hospital ward in the following circumstances:
11.1
a)
A mobile x-ray unit may be used in a ward for diagnostic investigation of a patient.
b)
An in-patient may undergo a diagnostic investigation with an unsealed radioisotope in the PET
Unit (or Department of Nuclear Medicine) and be transported back to the ward.
c)
An in-patient may undergo an investigation using radioisotopes in certain other locations in the
hospital (e.g. administration of 99mTc-HMPAO to patients in the epilepsy clinic for subsequent
ictal SPECT scanning).
d)
An in-patient may undergo a treatment which requires the administration of an unsealed
radioisotope such as the injection of P-32 in the patient's room. (N.B.: such procedures are not
currently performed at the MNH/I).
Use of Mobile X-ray Units in Wards
The safety aspects of the use of mobile x-ray units have already been covered in chapter 8, particularly in
section 8.4. It must be stressed that, when a radiographic examination is carried out in the ward, the
operator must take every precaution to ensure that other patients and personnel are not irradiated by the
direct beam and are sufficiently far from the patient under investigation (more than 1 meter) to reduce the
dose from scattered radiation to a low level. If necessary, portable screens or lead-rubber aprons arranged
as screens should be used to protect the other patients.
11.2
In-Patient Undergoing Treatment with Unsealed Radioisotopes
(N.B.: this section is included for the sake of completeness only, as such procedures are not currently
performed at the MNH/I).
11.2.1
Occasionally, P-32 is used for treatment, the activity being about 166.5MBq (4.5mCi). Injections might be
done at the MUHC (RVH), but patients may return to the MNH/I for further evaluations, etc.
11.2.2
In-patients being treated with unsealed radioisotopes must be housed in a single-bedded room. Any
patient who receives a dose exceeding 1.11GBq (30mCi) will perforce be an in-patient.
11.2.3
Before the administration of a radioactive dose, the responsible staff must ensure that the floor of the
patient's bathroom and the toilet seat are covered with absorbent material.
11.2.4
The patient should be instructed to flush the toilet several times after every use.
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11. Radiation Safety in the Wards
11.2.5
Visits to patients undergoing treatment with unsealed sources should be restricted. In particular, visits by
young and/or pregnant persons should be severely curtailed. Direct contact between visitors and patients
should be avoided and visitors should be instructed to remain as far as possible from the patient. The
Responsible Radiation User and/or RSO will give more detailed instructions according to the individual
patient and dose.
11.2.6
When surgery has to be performed on a patient who has recently received unsealed radioisotopes for
therapeutic purposes, the Responsible Radiation User, in consultation with the RSO, must assess the degree
of hazard arising from the activity remaining in the patient's body and advise the surgeon and operating
room staff if any special precautions need to be taken.
11.2.7
A patient can only be discharged after consultation with the RSO who will ascertain that regulatory
radiation dose rate limits are respected.
11.2.8
After discharge of the patient, the RSO must monitor the room and its contents before freeing the room for
future use. Further instructions will be given to the ward staff by the RSO.
11.2.9
If a patient should die soon after receiving unsealed radioisotopes for therapeutic purposes, the
Responsible Radiation User must be notified. He/she will then, in conjunction with the RSO, notify the
pathologist and all other staff concerned of the possible existence of a hazard and of the precautionary
procedures to be followed.
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12. Procedures for the MNI/H Medical Cyclotron Facility
12. Procedures for the MNI/MNH Medical Cyclotron Facility
12.1
Introduction
The MNI/H Medical Cyclotron produces radioactive nuclides for use in medical and biological research
and nuclear medicine procedures by bombarding target materials with accelerated protons and deuterons.
The nuclides so produced are transferred to the radiochemistry laboratory or "hot lab" for processing.
Because of the nature of the operations, radiation as well as non-radiation hazards exist.
Depending upon the particle energy and the material irradiated, high fluxes of secondary neutrons and
gamma radiation may be produced. Residual radioactivity may be induced in the cyclotron structure and
components and in the structural materials surrounding the cyclotron. The radioactive nuclides created by
the irradiation of target materials and transferred to the hot lab may also emit significant amounts of
radiation. During the handling and processing of irradiated target materials, radioactive gases or
particulates may escape into the atmosphere. In addition to these radiological health hazards, non-radiation
hazards such as mechanical, electrical, toxic chemical, fire and explosion hazards exist.
The purpose of these safety procedures is to ensure maximum safety to all personnel in and around the
Medical Cyclotron Facility. They are intended to establish and maintain correct methods of operational
safety and to familiarize personnel with the potential hazards. The procedures reflect the policies and
recommendations of the MNI/H Radiation Safety Committee and conform to the Regulations and
Requirements of the Government of Quebec and the Canadian Nuclear Safety Commission.
The procedures and instructions that are unique to the activities and operations in the facility are covered in
detail in this chapter. General safety practices pertaining to the initiation and maintenance of records,
radioactive material labeling, waste disposal, and non-radiation hazards are discussed only briefly.
12.2
Description of Cyclotron Facility
The Cyclone 18/9, designed by IBA (Ion Beam Applications, Belgium, at the time of acquisition marketed
through Siemens Medical Systems), is a negative ion machine that produces protons of 18MeV and
deuterons of 9MeV at maximum beam currents of approximately 100µA and 40µA respectively. There are
two radially mounted ion sources, one for each particle. Acceleration is achieved by using a magnet and RF
system. It has eight external beam ports with dedicated chemistry targets. Beam may be extracted at two
diametrically opposed ports simultaneously (same type of particle at both ports) which allows a very
efficient operation of the facility with one port, for instance, supplying radioisotopes for PET imaging and
the other one being used for radiochemistry research.
The Cyclotron Radiochemistry Facility is part of the McConnell Brain Imaging Center (BIC) of the MNI. It
produces selected positron emitting radioisotopes for medical research and diagnosis. By means of
positron emission tomography (PET), the in-vivo investigation of (cerebral) physiological processes in
humans is feasible. Cyclotron operation is highly automated, which means reduced operator intervention in
the vault and, therefore, reduced radiation exposure to personnel.
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The following four positron emitting radioisotopes are produced by the Cyclone 18/9 and used for the
labeling of a variety of compounds:
Isotope
Physical half-life (T1/2) in minutes
11
C
20
13
N
10
15
2
O
18
F
110
The above radioisotopes are used to label a variety of compounds which serve to study such quantities as
cerebral blood volume, cerebral blood flow, cerebral glucose and oxygen metabolism, protein synthesis
rates, cerebral enzyme activities, cognitive activities, neuro-receptor occupancies and many more. These
investigations are performed on normal subjects as well as on patients.
The Cyclotron Radiochemistry Facility is located at the following address:
Cyclotron Radiochemistry Facility
Montreal Neurological Institute
3801 University Street
Montreal, P.Q., H3A 2B4, CANADA
The facility occupies an area of approximately 500 m2 in total with 120 m2 being used for the cyclotron and
associated equipment (control room, power supply room, transformer room) and the remainder for the
chemical and radio-chemical laboratories, offices, a washroom and emergency shower, and storage area.
Except for a cyclotron secondary cooling circuit remote water chiller located on the roof, the facility is
wholly contained within the basement of a single building. Services are drawn from neighboring buildings.
The facility places no restrictions on the development of neighboring areas. The buildings and land
surrounding the facility are all owned and administered by McGill University.
12.2.1
Area Designation
The cyclotron facility comprises several distinct areas. These are: 1) the vault where the cyclotron is
located, 2) the Hot Lab where large quantities (Curies) of radioactive material are transformed into the
various PET radiopharmaceuticals mainly using automated synthesis units and hot cells, 3) the clean room
where the ready-to-inject products are prepared, 4) the quality control room for the final products, 5) radiochemistry labs for research activities, 6) chemistry labs (no radioactivity), 7) the cyclotron control room
and 8) the power supply room. The cyclotron vault is a zone of "no access" (exclusion area) during
accelerator operation. There are, however, two potentially high radiation areas, namely the maze entrance
and the Hot Lab. duct. Both areas are marked with radioactive warning signs, and personnel avoid these
areas during accelerator operation. All other areas are shielded sufficiently so that no physical access
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12. Procedures for the MNI/H Medical Cyclotron Facility
control is necessary while the accelerator is operating. However, because of the nature of the work
involved, the entire cyclotron facility, with the exception of the offices, is designated a limited access area.
The clean room is designated a high radiation area whereas the hot lab is an intermediate level facility. The
two entrances to the Facility are locked whenever operational personnel are not present in the facility.
Access to the facility at other times is through the main entrance only which is kept locked at all times (ring
a bell to ask for access).
12.3
Radiation Monitoring in the Cyclotron Facility
12.3.1
Radiation Surveys
The purpose of radiation monitoring is to verify the existence of safe operating levels. Radiation surveys
are necessary to establish these levels. Initial, or reference, surveys are performed whenever new target
materials or configurations are used. They consist of the measurement of leakage radiation through vault
walls while the accelerator beam is on. In this case, neutron radiation is monitored as well. Special surveys
may be conducted whenever radiation hazards are suspected.
Routine surveys are also performed with the beam turned off to establish reference radiation levels. These
surveys involve the measurement of residual beta-gamma radioactivity in the cyclotron vault,
contamination in the vault, Hot Lab and radio assay areas with the cyclotron shut off. Surveys of
contamination and exposure levels in the radioactive material storage room are also performed.
12.3.2
Access Control and Personnel Monitoring
The cyclotron facility is a limited access area with the exception of the offices. The cyclotron vault, the
clean room and parts of the Hot Lab are high radiation areas. Access to the facility is through the main
entrance (MP024) and through Room MP012 (for authorized personnel only). All entrances are locked
whenever operational personnel are not in the facility. Keys to the Facility are controlled.
Routine TLD badge service (body and extremity) is provided for all personnel permanently assigned to the
facility. Some workers are also given electronic personal dosimeters (EPDs) with continuous digital readout and audible alarm capabilities. Visitors and temporary personnel are assigned TLD badges according to
their degree of access to radiation areas. All personnel areas are controlled in accordance with the MNI/H
Regulations. Occasional visitors must be accompanied by an escort who is a member of the cyclotron unit.
12.3.3
Area Monitoring (gamma radiation)
Continuous monitoring of the gamma dose rate at several locations in the cyclotron facility is performed by
a Remote Area Monitoring System. This system consists of three multi-range ion-chamber monitors with
associated controls. These ion-chambers are permanently wall-mounted and are located inside the vault, in
the Hot Lab, and on the duct leading to the roof.
12.3.4
Exhaust Air Monitoring
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The exhaust air from the vault and from the fume hoods in the Hot Lab is monitored with an Eberline
Model RMS II Continuous Air Monitor. This monitor provides continuous measurement of beta-gamma
activities of air-borne particulate and gaseous components in the exhaust duct of the ventilation system.
12.3.5
Portable Survey Instruments
In addition to the above radiation detection systems, the following survey instruments are available:
One Berthold LB 1210B Contamination Meter
One Victoreen Model 190 “Frisker”
One Victoreen Thyac IV Model 290-SI Survey Meter
One Victoreen 488A-511 Neutron Monitor
One Siemens Mk2.2 Electronic Personal Dosimeter (EPD)
One Siemens Mk2.3 Electronic Personal Dosimeter (EPD)
12.4
Safety Interlock and Warning Systems
The purpose of the safety interlock and a warning system is to ensure that no person is in the vault at any
time when the cyclotron is producing hazardous levels of ionizing radiation. The system is "fail-safe", i.e.,
if the safety procedures are followed, generation of a beam of accelerated particles is possible only when
the entrance door is closed.
Details on the functioning of this safety interlock are described in the cyclotron Safety Report which is on
file with the CNSC.
12.4.1
Cyclotron Vault Entry and Clearance Sequence
The vault-ready interlock system requires that the cyclotron operator actually enter each bay in the vault
and manually reset the interlock system. This operation ensures that the operator himself/herself makes a
personal examination of both bays for clearance of personnel before proceeding with beam generation.
Furthermore, after cocking the second of the two vault-ready switches, the operator must leave the vault
and close the safety door to the vault within the time allotted (30 seconds), or the "ready" condition of the
interlock system reverts back to the "stand-by" condition, and the entire procedure must be repeated. The
interlock is fail-safe in that the machine is immediately shut down if any one of the interlock switches is
interrupted.
Details on the operation are described in the cyclotron Safety Report.
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12. Procedures for the MNI/H Medical Cyclotron Facility
12.5
Laboratory Safety Instructions
12.5.1
General Safety Practices
Hazards of a general nature include fire and explosion, falls, accidents during lifting and handling of heavy
equipment, electrical shock and toxic material release and dispersion. All of these topics are covered in
detail in a number of regulations and publications, some of which are contained in the references at the end
of this manual. The RSO, under the direction of the Director of the cyclotron facility, is responsible for the
general cyclotron operational safety. He will ensure that all personnel are thoroughly familiar with the
safety procedures and that all operations are conducted safely. All experiments, irradiations and processing
operations will be reviewed and evaluated with regard to potential non-radiation hazards. Any operation
which is considered to be unsafe will be discontinued immediately and will not be resumed until corrected
and approved.
Special attention has to be given to electrical hazards because of the existence of high voltage in the
accelerator and its power supplies. Standard operating procedures and precautions, which are observed by
all personnel, include the following:
12.5.2
1.
Never perform a new servicing operation or manipulation alone for the first time.
2.
Always use grounding hooks to discharge capacitors.
3.
Always have grounding hooks across high-voltage sources while working on the equipment.
4.
Never by-pass interlock circuits in the protective interlock system unless absolutely essential. If a
by-pass is necessary, then a large sign indicating the by-pass condition must be displayed on the
equipment and on the operating console.
General Facility Safety
1.
All personnel are required to wear TLD badges or dosimeters where required by CNSC and/or
MNI/H Regulations.
2.
Eating, drinking, smoking or application of cosmetics is not permitted in the laboratory areas and
the cyclotron vault.
3.
No food or drink storage is permitted in the radiation areas (only allowed in control room).
4.
Protective clothing should be worn in all areas where the handling of radioactive materials may
result in contamination.
5.
Radioactive materials with substantial radiation levels should be handled with tongs and
transferred and stored in approved shielded containers.
6.
All radioactive materials and their containers have to be labeled in accordance with Section 5.3 of
the MNI/H Radiation Safety Manual.
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12. Procedures for the MNI/H Medical Cyclotron Facility
12.5.3
12.5.4
7.
Transfer and control of all radioactive materials should be under the direction of the RSO or a
qualified user.
8.
Personnel entering exclusion areas should be instructed of the hazards and safety and emergency
procedures.
9.
All radioactive waste should be deposited in designated containers only and should be packaged
and disposed of in accordance with Section 7 of the MNI/H Radiation Safety Manual.
10.
Decontamination operations should be performed under the direction of the RSO or his qualified
alternate.
11.
All personnel exposed to radioactive contamination must monitor their hands, feet and clothing
before leaving the contaminated area. If contamination is found, decontamination procedures
must be followed before leaving the area.
12.
Two cyclotron laboratory staff members should be present when the cyclotron is operated or
radioisotopes are processed in the Hot Lab.
Vault Safety
1.
Each day at the start-up of the cyclotron, an operational check should be made of interlocks, fixed
monitors and warning devices.
2.
Before the cyclotron vault is secured and an irradiation begun, the target system and/or
experimental arrangements should be inspected for conformity with approved safety practices, and
the vault cleared of all personnel.
3.
Entry into the cyclotron vault should not be permitted without the approval of the cyclotron
operator.
4.
Vault areas to be occupied for extended periods by personnel should be monitored with portable
survey instruments prior to entry.
Hot Lab Safety
1.
No radioactive materials are to be washed down the floor or sink drains in the Hot Lab.
2.
All materials must be packaged, labeled and monitored in accordance with approved procedures
before transfer from the Hot Lab.
3.
All personnel in the clean room or the Hot Lab during radioisotope processing operations must
monitor their hands and feet before leaving the facility. If contamination is found,
decontamination procedures must be followed.
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12.5.5
Emergency Procedures
The purpose of this plan is to provide step-by-step procedures to be followed in the event of an emergencysituation. The goal of any emergency procedure is to prevent injury if none has occurred yet in an accident
and to prevent further injury if some has already occurred. Furthermore, every effort must be made to
confine and control any radioactivity that may be released as a result of an accident. Safety procedures
have been established in the laboratory, which are designed to reduce the possibility of an accident to a
minimum; however, it is recognized that even with the most efficient safety program the possibility of an
emergency situation still exists. In the Medical Cyclotron Laboratory such emergencies may arise as a
result of operational accidents, natural disasters (earthquakes, floods) or civil disturbances such as riots,
sabotage, vandalism. The responsibility for the safety program rests with the Director of the Medical
Cyclotron Facility, Dr. M. Diksic. In the event of an emergency at least one of the following persons is to
be notified. Priority of notification begins at the top of the list.
NAME:
MNI/H PHONE
HOME PHONE
398-8526
398-8527
398-8927
398-8527
697-9489
455-1162
525-0220
669-7263
Dr. M. Diksic
Mr. D. Jolly
Dr. E. Meyer (RSO)
Ms. M. Kovacevic
All persons listed above are trained in radiation safety practices and are authorized to direct/or perform
decontamination operations.
Cyclotron personnel should be familiar with the locations of the fire extinguishers, telephones, alarm box and
electrical breaker panels as well as with the evacuation routes to be taken in an emergency. The cyclotron is located
inside a vault consisting of concrete walls 1m thick. In addition to the cyclotron, there is a variety of electronic
equipment and vacuum systems.
The step-by-step procedure to be followed in the event of one or more of the above emergencies is outlined below:
1.
Turn off, disconnect or otherwise disable all equipment involved.
NOTE
In the event of an electric shock situation, where the individual, or individuals, are still in contact with the
power source and it cannot be shut off, remove the source or the victim (s) using an insulating material
such as dry wood, a cloth or a newspapers.
2.
Evacuate the area using the hallway exits.
3.
Close all doors to isolate any fires.
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4.
Notify the MNI/MNH Emergency Response Team (?????). For fires, use the alarm box in the hallway and
phone ?????. Give the operator the name and location of the building, room number, fire box number and
the nature and extent of the fire, and personnel injuries.
5.
Use available fire equipment to extinguish fires.
6.
Administer first aid to injured personnel.
7.
Notify at least one of the persons on the notification list above.
8.
Notify hospital maintenance of the emergency, describing the accident and the extent of any damage, and
inform them of any persons who may have been subjected to radioactive contamination.
9.
Secure the area, sealing off openings if flooding or gas leaks are present. In the event of a fire, wait until
the fire has been completely extinguished and fire department personnel have declared the area safe to enter
with regard to fire safety.
10.
If radioactivity is involved, check all personnel, including fire and rescue personnel, for contamination. If
contamination is found, follow the personnel decontamination procedures.
11.
Transfer injured contaminated persons to the special contaminated personnel handling facility located in the
Emergency Room of the Royal Victoria Hospital (MUHC).
12.
Record as much of the following information as possible:
a.
Time and place of accident.
b.
Names of persons involved.
c.
Radiation monitor readings and instrument settings, if applicable.
d.
Description of accident in as much detail as possible, with the probable cause and the action taken.
NOTE
If radioactive materials are involved, every person who might have been in the area at the time of
the accident, or following it, is considered contaminated until a personnel radiation survey has
been performed by one of the individuals on the notification list. Those involved in the accident or
its control must remain in the immediate vicinity until decontamination has been performed. Do
not enter the accident area until an authorized survey and decontamination procedure has been
performed and the area has been declared safe by one of the individuals on the notification list
above.
N.B.: In the case of a malfunction of the pneumatic tube system used to transfer radioactive
samples from the cyclotron facility to the PET-suite, i.e., if a transport container should get
stuck underway, the container should be pulled back to the start position by means of a
vacuum generator. If this attempt fails, radiation levels in the vicinity of the transport duct
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will be monitored and personnel working in its vicinity (analysis room WB205) relocated
temporarily if needed (e.g. if radiation field larger than 25μSv/hr (2.5mR/hr).
In the case of an emergency entry into the vault, unplug the mains power supply of the
Eberline monitoring unit in the Control Room (remember: under normal circumstances, the
vault cannot be entered until the vault Eberline monitor reading is below a preset safe
radiation level).
In the event of an earthquake, the following action is to be taken in addition to the above procedure:
1.
After the earthquake has passed, remain in the vicinity for notification form the MNI/H emergency units or
other competent authority.
2.
Check the area for fires, floods, gas leaks and other damage and take appropriate action to eliminate or
control the hazard.
3.
Initiate the step-by-step emergency procedure above.
4.
Prepare for possible aftershocks. Secure all rolling equipment or objects that may fall.
DO NOT:
a.
b.
12.5.6
Smoke or light a flame.
Make unnecessary telephone calls.
Decontamination
The RSO should be notified of all human contamination. Emergency personnel decontamination materials
are located on shelves above the sinks in the shop area and in the Hot Lab. Radiation survey meters are
located in the quality control room and in the storage cabinet next to the control room.
Decontamination of equipment, furniture and building surfaces should be performed only by a qualified
person, an individual who has been trained and/or approved by the RSO. Contaminated areas should be
isolated, secured and warning signs posted until decontamination can be performed.
Whenever possible, personnel decontamination should be performed by a qualified person. However, since
prompt removal of the contamination is of the utmost importance to reduce the potential hazard, if a
qualified person is not readily available, other persons are permitted to perform decontamination following
the procedures outlined in this section.
All operating personnel should receive instruction on the use of the portable radiation survey instruments in
the facility.
a)
Contamination Measurement of an Area
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b)
1.
Perform preliminary working check of the instrument outside and away from the contaminated
area.
2.
Ensure that the instrument selected for the measurement is sensitive to the radiation to be
measured and is in operating condition.
3.
Measure background before and periodically during the survey.
4.
When measuring alpha or beta radiation, keep the survey meter shield open and hold the detector
window as close to the surface as possible without touching it.
5.
Close the shield when measuring gamma radiation.
6.
Pass the detector window slowly and carefully over the entire surface. When the meter indicates a
radiation level above background, stop and wait for the maximum deflection.
7.
If the radiation level exceeds the maximum meter reading, switch to the next highest scale.
8.
As soon as reasonably possible, record contamination data in a log-book, including
location, radiation level and time of measurement.
Emergency Personnel Decontamination Procedure
1.
On completion of a quick contamination survey, remove all contaminated clothing, including
shoes, and place together in a small area to avoid spreading the contamination.
2.
Proceed to the nearest sink, and wash all contaminated areas thoroughly with the soap and solutions
provided. Be sure to scrub all parts of the hands, under the nails, and across the knuckles with a
surgical scrub brush.
3.
Dry with paper towels and place the used towels in a radioactive waste container.
4.
Check all areas of the body with a survey meter and repeat the washing operation until the radiation
level reaches background, or until successive washings fail to lower the level significantly. Do not
abrade the skin.
5.
Blow nose, using absorbent paper tissue, and save the tissues for assay of radioactivity. Do not
attempt to wash out the nasal passages until medical assistance is available.
12.6
Personal Responsibilities
12.6.1
Director of the Medical Cyclotron Facility
All activities that are conducted in the Medical Cyclotron Facility are under the direction and supervision
of the Director of the Medical Cyclotron Facility.
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No irradiation, beam experiment or radiochemical processing operation may be conducted without his
approval. He is responsible for ensuring that all procedures are performed in compliance with MNI/H
safety practice.
12.6.2
Chief Cyclotron Operator
The chief cyclotron operator is directly responsible to the Director of the Medical Cyclotron Facility and
through him to the Director of the MNI.
All radiochemical operations, including target preparation and processing and handling of the irradiated
target, are under the direction of the Director of the Medical Cyclotron. He is responsible for the activities
of all individuals involved in these operations and, with their assistance, he ensures compliance with all
regulations and safety procedures. Whenever new radio chemical or target handling operations are
considered, the operator should consult with the Director of the Medical Cyclotron and the Radiation
Safety Officer. He must ensure that all persons working in the Hot Lab are thoroughly familiar with
regulations and safety procedures.
12.7
Records
Regulations governing the procedures for initiating and maintaining radiation records and reports are set
forth elsewhere in this manual. These Regulations should be followed and, in addition, other records
pertinent to the activities of the Medical Cyclotron Facility should be maintained.
12.7.1
Personal Dosimeter and Access Log
Individual TLD badge records are routinely maintained by the chief cyclotron operator and posted at the
main entrance to the facility. Additionally, the RSO’s office keeps a copy of all exposure reports. All
visitors and transient operational personnel are required to sign in. If personnel dosimeters are required, the
relevant information will be entered into the record. Also, the RSO has to file a report to the CNSC within
21 days of noticing that the action level of a worker has been reached.
12.7.2
Radiation Survey Record
This record contains detailed information regarding routine and special surveys as well as safety
inspections. Cyclotron equipment maintenance operations, details of unusual incidents and operational
conditions etc. are maintained separately.
12.7.3
Radioactive Material Accountability Record
Information and records regarding radioactive material inventories, transfer and waste disposal are
maintained in this record. Copies of current valid radioisotope applications from persons and agencies
requesting radioisotopes are maintained as a part of the record (e.g., nuclear medicine license of
MGH/MUHC).
12.7.4
Radiation Instrument Maintenance and Calibration Record
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This record contains the maintenance and calibration information and dates for all radiation survey
instruments, gamma area monitors, and direct reading personnel dosimeters (pocket dosimeters). The RSO
keeps a record of the compulsory yearly calibrations of all radiation survey meters.
12.7.5
Cyclotron Operational Log
This log contains the operational data of the cyclotron, including pertinent instrument settings, nature of
experiment or irradiation, irradiation periods and names of responsible individuals. It is usually maintained
by the chief cyclotron operator.
12.8
Radiation Safety Check List
12.8.1
Cyclotron Safety Tests
Consolidated Cyclotron Safety Tests
Based on suggestions by Dr. S. Jovanovich, CNSC, and discussions with Mr. Dean Jolly, Chief
Cyclotron Operator.
Approved by the CNSC on May 5, 2006.
New: Every 6 months, 1/2 day will be requested to perform six-monthly and yearly cyclotron- related safety
tests listed below.
Every day: (new)

Morning inspection, 5min or less: at the start-up of the cyclotron, an operational check is made of
such indispensable safety features as:
1.
2.
3.
4.
5.
“last person out of vault” (i.e., green button in vault)
“emergency cyclotron shut-off operations”(i.e., red button in vault)
“audible warning devices” (i.e., vault bell)
“vault door interlock mechanism” (sliding maze door)
“operational state of interlocked radiation level survey instruments” (Eberline
monitors)
- We have modified the “IBA Cyclone 18/9 Daily Log Sheet “accordingly (see Appendix 1). There
are 5 check boxes to be filled in daily by the operator.
-The testing of points 1 to 4 is achieved in a single step by making sure that the vault bell rings. If
either of the buttons or the door interlock is malfunctioning, the door bell will not ring (see circuit
diagram).
-The vault and hot lab fixed Eberline monitors are checked visually by making sure that they are
reading a non-zero radiation level as soon as the beam is turned on.
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Every week: (new: no more weekly routine tests)
Every 1 month: (new)

As suggested by Dr. Jovanovich, the 3 fixed radiation monitors (Eberline) will be tested in turn, one
monitor every month, as to their capability to halt cyclotron operation by approaching a gamma
radiation source to the monitor and making sure that the cyclotron magnet power supply is shut off by
this manoeuvre.
Every 6 months: (new)

15

Monitoring of external cyclotron component activation around target areas (at 1 foot from
targets, at areas where personnel might occasionally perform interventions).
O-line leak check on radioactive gas steel tubing system to prevent escape of 15O-gases into the
environment.
Every 12 months: (as before)

Calibration of the three fixed radiation monitors (vault, hot lab and exhaust stack) using a
procedure approved by the CNSC.
Whenever required or feasible: (new)

Thorough radiation surveys (gamma and neutrons, see recent survey by Bubble Tech Inc.) shall be
performed following modification of target constellations and after major structural and/or
functional changes to the cyclotron equipment or its immediate surroundings (shielding, new
adjacent facilities) in order to confirm regulatory and safe operating radiation levels.

Radiation monitoring of internal cyclotron components (magnet poles, etc.) whenever the
cyclotron has to be opened for servicing or repair purposes.
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12.8.2
Interlock and Warning Systems
1.
2.
3.
12.8.3
SCRAM Button Tests
Vault Buzzer Check
Interlock Switches Functional Check
Radiation Monitors
Gamma Area Monitoring System (fixed “Eberline” area monitors)
a.
Calibration
b.
Check source reading
c.
Background reading
1.
12.9
Procedures for Handling of Irradiated Targets
12.9.1
Liquid Targets
The liquid target chambers are capable of retaining up to 10 cc of liquid. In general, a one-eighth-inch
diameter teflon tube is connected between the solution withdrawal port of the target chamber and a
container inside the shielded hot box. Extraction of the irradiated solution is accomplished either by
developing a negative pressure at the end of the system inside the hot box and allowing the solution to pass
into the container, or by passing a pressurized stream of dry air through the target chamber, thus forcing the
solution through the teflon tube and into the container. This latter method permits the flushing out of the
system after withdrawal of the irradiated solution. When the irradiated solution has been completely
withdrawn, the tube is closed off inside the hot box and the solution container placed in a lead container
before removal from the hot box for further processing or transfer to authorized users.
12.9.2
Foils
Foils may break or develop pin-holes during bombardment. Because of the high dose involved, these must
be replaced only the following day.
_____________________________________________________________________________
In case of an accidental puncture of target or vacuum chamber foils, the following steps are to be taken:
1.
2.
3.
4.
Enter vault as soon as vault access radiation interlock allows the door to be entered.
Close all target gas supply valves.
Leave vault and close door.
Wait 24h to let radioactivity decay (typically over night) and perform repair the next day only.
N.B.: In case of a target foil puncture, the radioactive material produced in the target box will leak into the
helium target cooling system which is a closed circuit. If the vacuum foil only is punctured, all radioactive
material remains in the target box. If both the target and the vacuum foil are punctured, some radioactive
material will be retained in the oil of the vacuum pumps and the rest will be vented to the exhaust system of the
facility. Therefore, in the case of any foil puncture, no radioactive material will be leaked into the vault.
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It should also be remembered that the vault is under negative pressure with respect to the rest of the facility such
that, in the unlikely event that some activity should leak into the vault, this activity would not spread to the
other locations of the facility.
_____________________________________________________________________________
12.9.3
Gas Targets
Gaseous targets are irradiated while under positive pressure in cylindrical target chambers. Stainless steel
or copper tubing connects the target chamber to a valve station inside one of the fume hoods where
collection and treatment of the irradiated gas takes place. Following irradiation, gas is collected either in a
holding tank or appropriate solution. Solution traps are also located downstream from the collection
system together with terminal holding tanks to ensure that no gas escapes into the surrounding atmosphere
until it has sufficiently decayed. In addition, the fume hood is under negative pressure and vented so that
no gas escapes into the lab. All solutions are assayed for radioactivity before disposal or removal from the
laboratory. Both the laboratory and the fume hood are monitored with a gas monitor.
12.10 References
1.
Blatz, Hanson: Radiation Hygiene Handbook, McGraw-Hill, 1959.
2.
National Bureau of Standards: Radiological Safety in the Design and Operation of Particle Accelerators
(U.S.) Handbook, No. 107, June, 1970.
3.
United States Atomic Energy Commission, Division of Operational Safety: Electrical Safety Guide for
Research, Safety and Fire Protection Technical Bulletin 13, December 1967.
4.
United States Atomic Energy Commission, National Accelerator Safety Committee: Safety Guidelines for
High Energy Accelerator Facilities, TID 23992, 1967.
5.
United States Department of Health, Education, and Welfare: Particle Accelerator Safety Manual
Handbook, MORP 68-12, October, 1968.
6.
University of California at Los Angeles, Office of Environmental Health and Safety: UCLA Radiation
Safety Handbook, 1964.
7.
State of California Department of Public Health, California Radiation Control Regulations, Title 17,
California Administrative Code, Chapter 5, Subchapter 4.
8.
Federal Register, Standards for Protection Against Radiation, Title 10, Chapter 1, Part 20.
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13. Radiation Accidents and Emergency Procedures
13. Radiation Accidents and Emergency Procedures
13.1
General Principles
A radiation accident is any unplanned incident or occurrence, which results, or may result, in exposure of
human beings to either external or internal irradiation. Such an incident can occur in one of two basic
ways, the responses to which are different:
1.
External exposure without contamination: this may result from a failure or breakdown of a radiation
generator such as an x-ray unit or an accelerator such as a cyclotron, or from a departure from the
procedures designed to ensure safe working conditions with such machines.
2.
Contamination: as a consequence of the spreading or dispersal of unsealed radioisotopes, which may
lead to internal or external exposure, or both.
3.
If you have been involved in a radiation accident or an emergency situation involving radiation,, you
must report this event to your superior as well as to the RSO as soon as possible. The RSO will
immediately file the necessary reports to the appropriate instances.
Reporting periods: immediate and 21days follow-up (check: General Nuclear Safety and Control
Regulations items 29, 30 & 31.
Action level reached: 21days
Transm. Source servicing location change or cessation: 7days notice
Gammacell: 7d before transfer or export and within 48hrs after receipt of a transfer or import.
Labs.: new location (more than 90d): 7d notification upon start and also after decommissioning.
13.2
Accidents Involving External Exposure Only
Accidental exposure of the whole or part of the body to a direct radiation beam, or an unplanned exposure
of the body to high activity sealed sources is unlikely but not impossible. Anybody who knows or suspects
that he/she has been exposed to a direct radiation beam or unshielded source must immediately report the
fact, with as much detail as possible, to the RSO, who will:
a)
Take immediate precautions to avoid the possibility of exposure to others (turn off the beam,
shield the source, cordon off the area, etc.).
b)
Arrange for the exposed person to receive a medical examination, including a full blood
examination.
c)
Arrange for a cytogenetic examination if the exposure is likely to be above 200mSv.
d)
Investigate the accident with a view to assessing the dose received by the individual and the cause
of the accident.
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e)
Collect the individual’s radiation monitor (if worn) and send it to the Radiation Protection Bureau
immediately.
f)
Remove or re-shield the source of radiation, if necessary with the help of provincial or federal
radiation safety authorities.
g)
Write a detailed report about the accident for submission to the RSC, the CNSC and other
pertinent authorities.
h)
In the case of a malfunction of the pneumatic tube system used to transfer radioactive samples
from the cyclotron facility to the PET-suite, i.e., if a transport container should get stuck
underway, the container should be pulled back to the start position by means of a vacuum
generator. If this attempt fails, radiation levels in the vicinity of the transport duct will be
monitored and personnel working in its vicinity (analysis room WB205) relocated temporarily if
needed (e.g. if radiation field larger than 25μSv/hr (2.5mR/hr).
13.3
Contamination by Radioactive Material
13.3.1
“Minor spills” of a radioisotope (less than 100 EQ), without contamination of personnel (i.e., spills of a few
drops of radioactivity in a very well defined location, such that you think you can handle the situation):
13.3.2
a)
define activity, nature and spread of contamination; (INFORM)
b)
isolate contamination area; (CONTAIN)
c)
clean up with appropriate liquid and disposable absorbent material. Prevent spreading of the
contamination. Avoid contact with contaminated area (use disposable gloves);
(DECONTAMINATE)
d)
repeat the clean-up procedure with repeated wipe tests until an acceptable level of contamination
is obtained as per license condition 2642-2 (see Appendix 11).
e)
keep a sample log of the accident on file using the Minor Spill Incident Form a copy of which has
to be sent to the RSO. (A copy of a Minor Spill Incident Form is given in Appendix 9).
“Major spill” involving significant quantities of a radioisotope (more than 100 EQ) spilled in a random
uncontrollable fashion and/or contamination of personnel and/or release of volatile material (i.e., a spill
such that you think you cannot handle the situation): (see also section “Attention” at the beginning of this
manual)
a)
Call ????? and say “Radiation Accident” or “Radiation Spill”.
b)
A “Code Brown” will then be issued over the intercom, mobilizing the Emergency Response
Team (ERT).
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c)
The ERT will contact the RSO (ext. 8927, or pager No. 406-3069)
and both the ERT and the RSO will proceed to the accident site.
d)
Wait for the ERT and the RSO to arrive on accident site to receive further directions.
e)
The ERT, with the help of the RSO, will initiate decontamination and survey of the area.
The RSO will write a detailed report about the accident for submission to the CNSC and the RSC.
See also Appendix 14i on “Spill Procedures”.
13.3.3
Decontamination Procedures
The contaminated area must be defined and isolated. The RSO should investigate the nature and extent
of the contamination. In case of minor spills involving low toxicity material, the decontamination
procedures might involve the use of a simple cleaning substance (count-off and hand cleaner) only. All
decontaminating material (gloves, pails, etc.) should be stored or disposed of in the same way as other
radioactive waste. To test the success of the decontamination, wipe-tests should be applied in the
following manner:
With a square of absorbent paper, wetted with an appropriate solvent, a 100cm2 surface must be wiped
clean and the resulting activity analyzed by an appropriate scintillation or gamma counter. Cleaning and
monitoring should be continued until readings indicate no further decrease of contamination. At this point,
the residual activity has to be assessed and, if not within regulatory limits (see Appendix 11), further
decontamination measures have to be taken such as removing the wax on the floor etc.
In case of a major spill, protective clothing must be worn during the decontamination process.
Where isotopes of short half-lives are involved, it may be sufficient to decommission the lab temporarily
and lock it up or keep the contaminated area covered with lead or plastic sheets taped to the contaminated
surface for the necessary decay period. Appropriate warning signs and barriers must be posted and warning
given to other personnel and housekeeping staff.
13.3.4
Contaminated patients who need medical attention:
a)
Isolate the patient to protect the environment against the further spread of contaminating
radioactive material. Usual surgical isolation techniques should be applied.
b)
Notify the RSO, who has the necessary instruments and knowledge to determine the amount and
toxicity of the contamination and would also take care of the decontaminating procedures. In case
the RSO cannot be reached immediately, contact the Emergency Response Team (ERT) at
?????.
c)
Unless very grave injuries make delays impossible, allow the radiation control personnel to
decontaminate the patient and surrounding area.
d)
If the patient is seriously injured, give emergency lifesaving assistance immediately.
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13.4
e)
When external contamination is complicated by a wound, care must be taken NOT to crosscontaminate surrounding surfaces from the wound and vice versa. The wound and surrounding
surfaces should be cleaned separately and sealed off when clean. When crushed dirty tissue is
involved, early preliminary wet débridement following wound irrigation may be indicated.
Further débridement and more definitive therapy can await sophisticated measurement and health
physics consultant guidance.
f)
Do NOT use lead aprons or thick rubber gloves, which give protection only against diagnostic xrays and are of no use against radioisotope contamination. This heavy and cumbersome equipment
will only hinder your movements, cause more contamination and diminish your ability to deal
with the patient.
g)
Handle contaminated patient and wound as one would during a surgical procedure, i.e., use gown,
gloves, cap, mask, etc.
h)
When external contamination is involved, save all clothing and bedding from ambulance, blood,
urine, stool, vomitus, personal effects of the patient and your own surgical protective clothing for
the radiation control personnel to deal with. Disposable plastic bags should be used for this
purpose, with tags attached to show date and content.
i)
The RSO will forward a report of the incident to the CNSC as per license agreement.
Fires Involving Radioactive Material
The procedures to be followed in the event of a fire are well defined at the hospital and they have to be
carried out in all instances. It is imperative to give precise information to the fire-fighting units about the
location and extent of any additional radiation hazard. Once the fire is dealt with, the RSO must monitor
the whole area to detect any possible contamination. Only after a careful survey should the area be
declared open to access. The RSO will draw up a report summarizing the event and promptly
forward it to the CNSC.
In Case of an Emergency Which Can Result in Fatalities, Radiation Hazard Must Be Considered Only if
the Exposure that Anyone Could Reasonably Receive Is in Excess of the Relevant Annual Dose Limit.
13.5
Loss or Theft of Radioactive Material or Radiation Devices
If a worker notices that radioactive material or a radiation device has been either stolen or lost, he shall
inform his supervisor immediately and contact the RSO. The RSO will immediately file a preliminary
report to the CNSC and then investigate the incident, trying to trace the lost or stolen item. The
investigation will also include a review of the working and security procedures in place at the site or
laboratory of the incident and finding means to improve them. The results of this investigation will be
summarized in a detailed report and sent to the CNSC within 21 days of the incident.
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14. Education and Training of Personnel
14. Education and Training of Personnel
The purpose of a radiation safety program in any institution is to ensure that procedures involving the
handling and use of radiation sources are carried out with minimum hazard to all concerned. To this end,
the Radiation Safety Committee, the RSO, Responsible Radiation Users and Radiation Supervisors need to
establish and maintain close contact with all personnel who work with or near radiation sources. The
“human element” is the key factor in the application of all safety rules and regulations. Each department or
laboratory, each group or type of personnel and each application or use of radiation sources is associated
with specific hazards which require specific safety procedures. Safety implies understanding the working
procedures in each area and adjusting or modifying these procedures in order to minimize the hazards.
As an example, all nuclear medicine technologists at the MNH/I are certified professionals, and the
Medical Cyclotron Radiochemistry Facility personnel all have experience, some over 10 years, in
working with high levels of radioactivity and, to various degrees, have undergone training offered by the
manufacturer of the cyclotron.
As a rule, any individual who is going to be involved with the handling of radioactive substances or
devices at the MNH/I has to register with the RSO. At the time of registration, the applicant agrees (see
form in Appendix 4c) to attend the next available Radiation Safety Course offered by the Environmental
Hygiene and Safety Office (EHS) of McGill University.
If the next available Radiation Safety Course offered by the EHS is some time away (these courses are
given approximately every 2 to 3 months), the applicant has, before working independently with radiation,
to take a test (quiz), prepared by the RSO, that consists of 30 basic questions related to radiation matters. A
passing mark of 80% is required.
Individuals with previous pertinent experience in radiation work, as documented by a written statement
from another institution, may be required to only take the exam (rather than the 1-day course) that is
associated with the McGill Radiation Safety Course.
Furthermore, the RSO meets with the individual laboratory personnel for formal and informal
discussions on radiation issues whenever required.
In addition, each employee involved in radiation work must be provided access to a copy of the Radiation
Safety Manual and sign a form (see Appendix 4a) confirming that she/he has read the sections which are
“required reading” for her/his job category (see list at end of this chapter).
Refresher courses covering all aspects of radiation safety plus information on regulations are being
developed in collaboration with the Environmental Hygiene and Safety Office, McGill University. This
teaching module will be accessible over the internet to all radiation users and will provide documented
updated training for all individuals dealing with radiation.
All procedures at the MNH/I are subject to review and re-evaluation. Procedural changes and the
introduction of new techniques create a need for continuing education of existing personnel as well as for
training of new personnel. New employees usually receive on-the-job training and supervision, followed
by periodic retraining and further education.
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14. Education and Training of Personnel
In order to ensure that all persons handling radiation sources receive adequate instruction in the safety
aspects of such handling, the DRS will direct new radiation users (fellows, post-docs, technicians,
students) to the RSO who will assure that these individuals will attend the appropriate training sessions.
The employee is expected to study the assigned documents (e.g. the RSM) and must be given adequate
opportunity to discuss and query the material concerned with the Responsible Radiation User, the RSO or
other members of the safety organization in order to obtain further information or clarification. Once this
process is completed, the employee must sign the Declaration Forms (Appendices 4a and 4c), which are
then sent to the RSO for safe-keeping.
Notice also that individuals associated with studies where radioisotopes are being used, who do not,
however, handle the radioisotopes themselves (for example PET or microPET investigators), have to
undergo a “minimal training” by reading and signing the appropriate radiation safety information sheet
(Appendices 18 and 19).
At least one member of the Animal Care Facility has to be fully certified as a radiation user, i.e., has
attended the Radiation Safety Course offered by the EHS of McGill University and will attend future
refresher courses.
The sections of the Radiation Safety Manual (RSM) which apply to different groups of personnel at the
MNH/I are as follows:
1.
Technologists, Radiologists, Medical and Nursing Personnel:
Chapters 1-11, 13, 14
2.
Laboratory Technologists and Researchers:
Chapters 1-7, 10, 11, 13, 14
Cyclotron Personnel shall read Chapter 12 as well
3.
Secretaries, Security, Receiving and Maintenance Personnel:
Chapters 1-3, 5, 6, 13
4.
Nuclear Medicine Technologists:
Chapters 1-7, 10-13
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15. Appendices
Appendices
to the
Radiation Safety Manual
of the
Montreal Neurological Institute & Hospital
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Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 20th, 2006
Appendix 1
Appendix 11)
Systme International (Si) Units
The rad (rad) is replaced by the gray (Gy)
1 kilorad (krad)
=
10 grays (Gy)
1 rad (rad)
=
10 milligrays (mGy)
1 millirad (mrad)
=
10 micrograys (μGy)
1 microrad (μrad)
=
10 nanograys (nGy)
1 gray (Gy)
=
100 rad (rad)
1 milligray (mGy)
=
100 millirad (mrad)
1 microgray (μGy)
=
100 microrad (μrad)
1 nanogray (nGy)
=
100 nanorad (nrad)
The rem (rem) is replaced by the sievert (Sv)
1 kilorem (krem)
=
10 sieverts (Sv)
1 rem (rem)
=
10 millisieverts (mSv)
1 millirem (mrem)
=
10 microsieverts (μSv)
1 microrem (μrem)
=
10 nanosieverts (nSv)
1 sievert (Sv)
=
100 rem (rem)
1 millisievert (mSv)
=
100 millirem (mrem)
1 microsievert (μSv)
=
100 microrem (μrem)
1 nanosievert (nSv)
=
100 nanorem (nrem)
The curie (Ci) is replaced by the becquerel (Bq) *)
1 kilocurie (kCi)
=
37 terabecquerels (TBq)
1 curie (Ci)
=
37 gigabecquerels (GBq)
1 millicurie (mCi)
=
37 megabecquerels (MBq)
1 microcurie (μCi)
=
37 kilobecquerels (kBq)
1 nanocurie (nCi)
=
37 becquerels (Bq)
1 terabecquerel (TBq)
=
27 curies (Ci)
1 gigabecquerel (GBq)
=
27 millicuries (mCi)
1 megabecquerel (MBq)
=
27 microcuries (μCi)
1 kilobecquerel (kBq)
=
27 nanocuries (nCi)
1 becquerel (Bq)
=
27 picocuries (pCi)
*)
1 Bq = 1 disintegration / second = 1
1)
From: AECB Publication R-52, Revision 1
Radiation Safety Manual of the
MNI/H
s-1
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 20th, 2006
Appendix 2
Appendix 2
Radiotoxicity and Half-Life of Selected Radionuclides
Very High Radiotoxicity
Moderate Radiotoxicity
Radium-223 (223Ra)
11.7 days
Carbon-14 (14C )
5730 years
Radium-226 (226Ra)
1620 years
Fluorine-18 (18F)
111 minutes
Radium-228 (228Ra)
6.7 years
Phosphorous-32 (32P)
14.3 days
Sulphur-35 (35S)
87.4 days
High Radiotoxicity
Sodium-22 (22Na)
2.61 years
Chromium-51 (51Cr)
27.8 days
Calcium-45 (45Ca)
165 days
Iron-52 (52Fe)
8.3 hours
Cobalt-56 (56Co)
77 days
Krypton-85m (85Krm)
4.4 hours
Cobalt-60 (60Co)
5.3 years
Krypton-87 (87Kr)
76 minutes
Strontium-90 (90Sr)
28 years
Molybdenum-99 (99Mo)
66 hours
Iodine-131 (131I)
8 days
Iodine-135 (135I)
6.7 hours
Cesium-137 (137Cs)
30 years
Rubidium-86 (86Rb)
18.6 days
Europium-152 (152Eu)
9.2 hours
Low Radiotoxicity
Hydrogen-3 (3H)
12.3 years
Oxygen-15 (15O)
2 minutes
Xenon-131m (131Xem)
12 days
Technetium-99m (99Tcm)
6 hours
Xenon-135 (135Xe)
5.3 days
Iodine-125 (125I)
60 days
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 3
Appendix 3
Request to Use New Radio-Chemical
Montreal Neurological Hospital and Institute
Date: _________________
Laboratory Director: ___________________ Internal Permit No.:_________________
1) Name of Radio-Chemical: _______________________Open:_____ Sealed: ______
2) Chemical Form: ______________________________________________________
3) Radioactivity Manipulated per Experiment (MBq or mCi):______________________
4) Frequency of Experiments: _____________________________________________
5) Maximum Estimated Activity Requested per Year (MBq or mCi):_________________
6) Major Use of the New Radio-Pharmaceutical (short description of planned
experiment):
For more Information Call the RSO at Local: 8927
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 4a
Appendix 4a
Declaration by Employees Handling Radioactive
Materials and Radiation - Emitting Devices
The purchase and use of radioisotopes and of radiation-emitting devices at the Montreal Neurological
Institute and Hospital are governed by the license(s) issued to the Institute and Hospital by the Canadian
Nuclear Safety Commission (CNSC). It is an implicit condition of these licenses that every person
handling radioisotopes or radiation-emitting devices shall read and understand the relevant sections of
the MNI/MNH Radiation Safety Manual.
Declaration
Name of Employee: __________________________________________________________________
Department or Laboratory: _____________________________________________________________
Responsible Rad. User (RRU) or Supervisor: _________________________ (Int. Permit #: __________)
I hereby declare that I have read those sections of the MNI/MNH Radiation Safety Manual that are
relevant to my work (as listed below) and that I understand the meaning and implications of these
sections. I further declare that, before signing my name, I have been given adequate opportunity to
discuss and clarify the contents of the Radiation Safety Manual and other documents listed below with my
supervisor and/or other authorized person(s) in the field of radiation safety.
Relevant sections:
1. Technologists, Radiologists, Nursing and Medical Personnel:
1-11, 13, 14
2. Laboratory Technologists and Researchers:
1-7, 10, 11, 13, 14
Cyclotron Personnel shall read chapter 12 as well.
3. Secretaries, Security, Receiving and Maintenance Personnel:
1-3, 5, 6, 13
4. Nuclear Medicine Technologists:
1-7, 10-13
N.B.: If I-125 or I-131are used, CNSC regulatory document R-58, available from the RSO, must also be
consulted.
Signature of Employee: _______________________________ Date: ___________________________
Signature of RRU or Supervisor: _________________________ Date: ___________________________
This form must be filed by the RRU of the laboratory or by the departmental supervisor concerned, and a
copy sent to the Radiation Safety Officer at the MNH/I.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 4b
Appendix 4b
Application for Radiation Monitor
(A) Personal Information / Information personnelle
Family name / Nom de famille;
First Name / Prénom:
Sex / Sexe:
(circle, cercler)
M
F
Yes
No
Date of birth / Date de naissance:
Place of birth / Lieu de naissance:
Social insurance number / No.d’assurance sociale:
Previous badge ? / Moniteur précédent ?
(B) Work-related Information / Information concernant le travail
Department / Département:
Room Number / Numéro de la salle:
Internal Permit # / Numéro de permis interne:
Work telephone number / No. de téléphone au
travail :
Duration of stay / Durée de séjour:
Job classification / Classification d’emploi:
(C) Signatures
Signature
Date
Applicant / Demandeur:
RRU or Supervisor / Superviseur:
Radiation Safety Officer / Agent de
Radioprotection:
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 4c
Appendix 4c
Radiation Worker Registration Form
To be filled out and returned to the Radiation Safety Office (room WB-211) by all new personnel/ staff/
students who plan to use radioactive materials. New users may also be asked to pass a test (power point
presentation quiz) for assessment of their knowledge of basic rules for working with radioisotopes.
Questions on the test will be based upon information provided in the “Radiation Safety Manual” as well as
the “Primer for New Users”.
Personal Information:
Name:
Lab. Phone #:
Supervisor:
Department:
Start date:
Room #:
Previous Radiation Safety Training:
Have you ever worked with radioactive materials?
If yes, specify radioisotopes handled :
Yes
No
Radioisotopes:
Place:
Year:
Have you had any formal radiation safety
training?
Yes
No
Yes
No
If yes, specify the following:
Place:
Year:
As a part of this training, did you receive a
certificate? If yes, please provide a copy of
the certificate to the RSO’s office.
Declaration by Worker
I, ________________________, agree to attend the next available Radiation Safety Training Course,
offered by McGill University. I also agree to take the exam associated with this course (exam fee to be
paid by the MNI). In the interim, I acknowledge that I have read, understood, and will comply with, the
policies outlined in the Radiation Safety Manual of the Montreal Neurological Institute and Hospital.
Signature: __________________________________________ Date: ________________
RSO: ___________________________________________Date: _______________
Training may be waived if you are able to demonstrate that you have received appropriate training at
another institution.
Training waived:
Yes / No
Radiation Safety Manual of the
MNI/H
RSO’s Signature: __________________________
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 5
Appendix 5
Declaration of Pregnancy by Nuclear Energy Workers
In accordance with the Canadian Nuclear Safety Commission Radiation Protection
Regulations (paragraph 11), June, 2000:
I hereby inform my employer that I am pregnant.
Name of Employee: __________________________________________ Phone: ___________________
Stage of Pregnancy (months): ___________________________________________________________
Signature of Employee: _______________________________________ Date: ____________________
Name of Head of Laboratory or Department: ________________________________________________
Signature of Head of Laboratory or Department: ___________________________ Date:_____________
Pregnancy Monitoring
The Radiation Protection Bureau (Health Canada) offers a Pregnancy Radiation Monitoring Service for
pregnant workers handling radioactive substances or devices and for any other Nuclear Energy
Workers. If you decide to make use of this service, your radiation exposure will be reported every two
weeks as opposed to every three months for the remaining duration of your pregnancy.
Do you wish to be on the semi-monthly service for pregnant workers?
Yes
No
Signature of Employee: ___________________________________ Date: ____________________
This form must be filed with the records kept by the head of the laboratory or department, and a copy sent
to the RSO.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
Appendix 6
Internal Permit Application Form
(Updated: March, 2005)
Montreal Neurological Institute and Hospital
3801 University Street
Montreal, Quebec
H3A 2B4
(Please type or print legibly)
NAME OF APPLICANT: _______________________________________
Office Use Only
Internal Permit Number:
CNSC Radioisotope License Number:
Expiry Date:
This form must be filled out by all MNI/MNH researchers who propose to use radioisotopes in their
laboratories. Completed forms must be returned to the RSO (room WB 211, ext. 8927).
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
Internal Permit Application Form
1. PERSONNEL
(A)
RESPONSIBLE RADIATION USER INFORMATION
Name:
Position:
Location (Room #):
Office
LAB
Telephone Number:
LAB
Office
Home
E-mail Address:
(B)
DEPARTMENTAL RADIATION SUPERVISOR INFORMATION
Name:
Position:
Location:
Office
LAB
Telephone Number:
Office
LAB
Home
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
(C)
PERSONNEL INVOLVED (use additional sheets if necessary.)
Category I:
Category II:
Those directly working with radioactive material(s)
Those having regular access to a room containing radioactive material(s)
NAME
CATEGORY
(I or II)
POSITION
ROOM
NUMBER
2. Locations
(A)
LOCATION(S) WHERE RADIOISOTOPES WILL BE PROCESSED OR USED:
Room #:
(B)
RADIOISOTOPE STORAGE INFORMATION FOR THE NEXT TWO (2) YEARS:
Radioisotope
(C)
Maximum Activity
Storage Location
IF STORAGE CONTAINER IS A REFRIGERATOR, IS IT ALSO USED FOR STORAGE OF NONRADIOACTIVE MATERIAL?
Yes
Radiation Safety Manual of the
MNI/H
No
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
(D)
IF LAB SPACE IS SHARED BETWEEN MORE THAN ONE GROUP, A SIGNED STATEMENT
OF CONSENT (see Appendix) MUST BE PROVIDED WITH THE APPLICATION.
3. Radioisotopes
(A)
UNSEALED SOURCES
Will unsealed radioisotopes be used for:
Use type:
Yes
No
Yes
No
In-vivo administration to patients?
In-vivo administration to healthy volunteers?
In-vivo administration to animals?
In-vitro clinical or research?
(B)
SEALED SOURCES
PLEASE ATTACH STATEMENT OF INTENDED USE ON SEPARATE SHEET
Will sealed radioisotopes be used for:
Use Type:
External and/or internal irradiation of patients?
(If yes, attach/send copy of appropriate Institute/Hospital Ethics Report)
External and/or internal irradiation of animals?
(If yes, attach/send copy of appropriate Institute/Hospital Ethics Report)
In vitro irradiation?
Other purposes, e.g., instrument calibration etc.?
(C )
List all unsealed radioisotopes to be used and/or all sealed radioisotopes to be used
or possessed in the next 2 years. (Use additional sheets if necessary).
Activities should be expressed in S.I. units (Becquerels).
Consult table at the end of this application form for conversion from Curies to Becquerels.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
Maximum activities to be used:
Radioisotope
Chemical form
1 year
In single delivery
Handled at one
time
4. Monitoring and Disposal
(A)
Please include make and type of any monitoring equipment for the weekly
monitoring of contamination of benches, floors, equipment, personnel, and
information on the twice yearly leak tests of sealed sources.
Instrument
(B)
Please indicate the model and location of the liquid scintillation counter which will be used
for monitoring surface contamination and weekly wipe tests:
Instrument Model
(C)
Make/ Model
Location (Room #)
WASTE DISPOSAL: If waste is not collected by the McGill Waste Management Program
using RTS, please describe your method of disposal. (See section 7 of the Radiation
Safety Manual).
McGill (RTS):_________________________________________________________________
Other (give details): ___________________________________________________________
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
5. Radiation Safety Training
The applicant agrees to comply with radiation safety training requirements in effect at the MNH/I
as specified in the Radiation Safety Manual and modified as needed from time to time by the
Radiation Safety Committee of the MNH/I.
Signature of Responsible Radiation User :
Date :
Office Use
Checked by:
Radiation Safety Committee Approval Date:
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
Quick Reference Table
The following table gives the conversion factors from the old units to the
Système International (SI) units.
The curie (Ci) is replaced by the Becquerel (Bq)
1 Ci = 37 Giga-Bq (GBq)
1Bq=27 pico-Ci (pCi)
Radiation Safety Manual of the
MNI/H
Curies
Becquerels
1 µCi
37 kBq
5 µCi
185 kBq
10 µCi
370 kBq
30 µCi
1.11 MBq
100 µCi
3.7 MBq
0.5 mCi
18.5 MBq
1 mCi
37 MBq
5 mCi
185 MBq
10 mCi
370 MBq
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 6
Appendix (to App. 6)
To be filled out and signed by all users of an area designated as shared or common space
which will be used to store or use radioactive materials.
STATEMENT OF CONSENT
I / We, the undersigned, have been informed by: ___________________________
that the following area(s):_______________________________________________
will be used to store, or work with, radioisotopes.
We hereby state that we have no objection to radioisotopes being manipulated in
the above area(s).
Name
Radiation Safety Manual of the
MNI/H
Signature
Date
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 7
Appendix 7
Internal Radioisotope User Permit (example)
Issued by:
The Radiation Safety Committee of the Montreal Neurological Institute and Hospital
Authorized by the Canadian Nuclear Safety Commission
CNSC Radioisotope License Number: 01187-2-08.0 (and all revisions thereof)
1.
Radioisotope User Permit Number
Classification
Date of Issue
Revision Date
Expiry Date
:
:
:
:
:
MNI_001 (Revision No. x)
BASIC (e.g.)
May 1, 2003
March 20, 2004
April 30, 2008
2.
Name of Principal Investigator
:
USER, Xyz
3.
Department
:
Neuro-Something
4.
Location(s) approved by this permit
:
WB010, 945, etc.
5.
Radioisotopes approved by this permit
:
See non-shaded cells in table
below.
Note: The permit holder needs written authorization by the CNSC for projects requiring
more than 10,000 exemption quantities (E. Q.) of a radioactive substance.
3H
approved for use of:
10'000 exemption
quantities
(E. Q)
your possession limit
is:
14C
35S
32P
45
Ca
51Cr
10 TBq
or
270 Ci
100 MBq
or
2.7 mCi
10 GBq
or
270 mCi
10 GBq
or
270 mCi
1 GBq
or
27mCi
81 MBq
or
2.2 mCi
18.5 MBq
or
0.5 mCi
370 MBq
or
10 mCi
125I
6.
Personal Dosimeters Required
7.
Method of Disposal: All radioactive waste (solid and liquid) must be disposed of in
compliance with the Radioactivity Tracking System (RTS) requirements set out by the
McIntyre Waste Management Program (McGill) using their containers that have to be
brought to the central waste storage cage in the basement of the MNH/I (room 045 B).
Radiation Safety Manual of the
MNI/H
: YES
Version No.: 2
September 1st, 2007
Appendix 7
8.
Last revision of this Appendix on: February 28th, 2006
Special Conditions:
Gloves and lab coats mandatory.
Weekly wipe tests required in areas where radioisotopes are used.
Ring badges required for staff using > 50 MBq of
32
P.
Monitoring of all work surfaces where 32P is used at the end of the work day.
Radio-iodinations: Must be carried out in a working fume hood. Schedule thyroid monitoring.
Use of proper survey equipment during radio-iodine manipulations.
The Radiation Safety Officer, MNH/I: ___________________________ (E. Meyer, RSO, ext. 8927)
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 8
Appendix 8
Radioisotope Inventory Sheet (1 vial per sheet)
Location
Source
Shipment
Lab:
Isotope:
Supplier:
Supervisor:
Product:
Batch/Lot number:
Contact person:
Activity:
Received:
Volume:
Reference date:
Date
User
Procedure
Activity
used
Activity in
stock
Waste Form
L
O
S
A
G
B
A
=
=
=
=
=
=
=
Aqueous Liquid
Organic Solvent
Solid
Absorbent Material
Glass/Sharps
Biohazard /infectious
Animal Carcass
Waste Form
Disposal
Method
Amount of
Activity in
waste
Disposal Method
1
.
2
3
4
5
6

=
=
=
=
=
=
=
Send to waste storage (use McIntyre
RTS System)
Municipal Garbage 
Municipal Sewer (sink) 
Incinerator
Return to supplier
Transfer to another lab
Check with RSO
NB. : Since the introduction of the McGill (McIntyre Waste Management Program) Radioactivity
Tracking System (RTS) in March of 2004, the computer printout of the RTS summary is an
acceptable replacement for the above Inventory Sheet.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 9
Appendix 9
Minor Spill Incident Form
(Maintain a copy for your records and send another copy to the RSO (Room WB 211)
For spills involving a few drops only of an isotope and no personnel contamination, such
that you feel comfortable to be able to handle the situation to the best of your
knowledge (i.e., a spill of less than ~ 100 EQ).
Minor Spill Incident Report
Date
Location
of Spill
RadioNuclide
Radiation Safety Manual of the
MNI/H
Monitor Readings
Activity
Before
After
Incident/ Cleanup
Details
Technician
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 10
Appendix 10
MNI/H Contamination Control Protocol
(Updated: April 26th, 2002)
This document outlines and updates the protocol which all users of open sources of radioactivity MUST
follow in order to comply with the license condition entitled “Contamination Criteria” (see e.g. condition 15
in CNSC license 01187-2- 08.3, LABORATORY STUDIES).
1.
Person-in-charge:
While there is no restriction on who performs the contamination or wipe test, it is important to
have one person in the lab/group that is ultimately in-charge of the process. This ensures
continuity in the maintenance of records in the lab. It is also essential that the person performing
the wipe test be fully aware of the protocol and rules outlined in this document.
2.
What constitutes a contamination?
The criteria for non-fixed contamination have been modified in the process of the transformation
of the AECB into a new entity called CNSC (Canadian Nuclear Safety Commission) which
officially came into existence on May 31st, 2000. The new criteria fall into three groups, each
group representing a Class of radio-nuclides. The classification of radio-nuclides is given in the
Table attached to the present document. Essentially, the radio-nuclides in Class A are the most
“harmful” ones while those in Class C are the least “harmful”. Note: All the open source radionuclides presently being purchased under the above license belong to Class C (the only radionuclides listed on the license that belong to Class B are I-131, F-18, Ga-68, Kr-85 and Fe-55, but,
except for the PET tracer F-18, these are only sporadically being used, if at all).
The new contamination criteria are summarized below :
Type of area
all areas, rooms or enclosures where unsealed
radioisotopes are used or stored
all other areas
CNSC limits for non-fixed contamination
Class A
3 Bq/cm2
Class B
30 Bq/cm2
Class C
300 Bq/cm2
Class A
0.3 Bq/cm2
Class B
3 Bq/cm2
Class C
30 Bq/cm2
Assuming an instrument efficiency of 50%, a wipe efficiency of 10% and a wiped area of 100 cm 2, this
translates into a cpm-value of 90,000 and 9,000 for radioactive and “clean” areas, respectively, for Class
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 10
C radionuclides. These values are considerably higher than the previously acceptable limits (action
levels) at this Institute.
The Radiation Safety Committee and the MNI/H Radiation Safety Office are committed to keeping
radiation levels ALARA (as low as reasonably achievable). Therefore, the acceptable limits for
contamination for practical purposes (action levels) are set, as before, at considerably lower values than
those derived from the new CNSC contamination criteria:
Areas where detected counts are more than 3 times the background level will be considered
contaminated and cleanup will be required.
3.
Background wipe: The background wipe is an unused or blank wipe which is treated the same
way as a regular wipe. In other words, take a clean swipe, place it in a vial, add the scintillation
cocktail and count.
4.
If a routine wipe test indicates the presence of contamination at a specific location:
a. Clean up the area.
b. Perform additional wipe tests on the contaminated area after cleanup is completed and
document the results (including the LSC printout) in the wipe test book as proof that the
contaminated area was cleaned up appropriately.
5.
Frequency of wipe testing:
Frequency of radioisotope use
Wipe testing requirement
once a week or more
at least weekly
less than once a week
upon completion of manipulation involving radioisotope use, or at
the end of the work week during which the isotope was used.
The Weekly Contamination Survey Log (see Appendix 17) must be filled out in either case. If no
radioisotopes were used in a particular week, this must be indicated on the log.
6.
Record Keeping: Weekly wipe test results must be maintained in a clearly marked separate
folder.
A complete contamination survey record consists of the following:
a.
A labeled lab-layout diagram;
b.
A table with the counts recorded at the locations indicated on the layout;
c.
A copy of the printout obtained from the liquid scintillation counter
d.
A weekly entry in the Contamination Survey Log.
7.
Records: Wipe test / inventory records must be kept in the lab for three years.
a.
b.
Prior to disposing of any records related to the use of radioisotopes, permission must be
obtained from the CNSC. If you have records dating back more than 3 years and wish to
discard them, call the MNI/H radiation safety office at 8927.
Records (wipe test as well as inventory) must be kept in the laboratory and available for
inspection at any time.
The Radiation Safety Officer
MNI/H Radiation Safety Office, Room WB211
Phone: 398-8927
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 10
Table (to Appendix 10)
Classification of Radio-Nuclides
The most commonly licensed radionuclides have been grouped into Class A, Class B and Class
C, based upon their radiological properties.
Class
Class A
Class B
Class C
Radio-Nuclide
All alpha emitters and their daughter isotopes.
Na-22
N-24
Co-60
Ir-192
Sb-124
Ta-182
Zn-65
As-74
Au-198
Br-82
Co-58
F-18
Fe-59
Ga-67
Gd-153
Hg-203
I-131
In-111
In-114m
Nb-95
Rb-84
Rb-86
Sc-46
Se-75
Sm-153
Sn-113
Sn-123
Sr-85
Sr-90
Au-195m
C-14
Ca-45
Cd-109
Ce-144
Cl-36
Co-57
Cr-51
H-3
I-123
I-125
Ni-63
P-32
P-33
Re-186
Re-188
Ru-103
S-35
Sr-89
Tc-99
Tc-99m
Tl-201
Y-90
Yb-169
When using more than one radio-nuclide in a room, the radio-nuclide with the lowest (most
restrictive) contamination limit must be used to determine the limit (Class A, Class B or Class C)
that applies to the room.
If a radio-nuclide is not listed in the table, contact your CNSC licensing officer at 1-888-2292672.
Radiation Safety Manual of the
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Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 11
Appendix 11
Converting Liquid Scintillation Counter (LSC) Readings to New CNSC
Regulatory Criteria for Radioactive Contamination
- or
How to convert CPM measurements to Bq/cm2
MNI/H Radiation Safety Office
(Updated: April 29th, 2002)
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 11
Converting LSC Readings to New CNSC Regulatory Criteria for
Radioactive Contamination
- or
How to convert CPM measurements to Bq/cm2
INTRODUCTION
Removable contamination is typically monitored with wipes assayed in a liquid scintillation counter (LSC)
and reported in cpm (counts per minute). As a rule, surfaces with cpm readings of more than three times
the background are presently considered as contaminated at our Institute.
The CNSC requires that contamination be reported in terms of Becquerels/cm2 (Bq/cm2). The new CNSC
criteria for non-fixed or removable radioactive contamination (see for instance condition 15 of Lab.
License 01187-2-08.3) are as follows:
Table 1
Type of Area
All areas, rooms or enclosures where unsealed
radioisotope are used or stored.
All other areas
CNSC limits for non-fixed contamination
Class A
3 Bq/cm2
Class B
30 Bq/cm2
Class C
300 Bq/cm2
Class A
0.3 Bq/cm2
Class B
3 Bq/cm2
Class C
30 Bq/cm2
N.B : The CNSC has « replaced » the AECB as of May 31, 2000, and a number of regulations have changed in the
process of this transition. Please refer to the preceding document (Appendix 10) entitled “MNI/H Contamination
Control Protocol” for more details on the changes regarding the contamination criteria.
The present document will guide you through the steps involved in converting cpm readings to
Bq/cm2 as in the past, but taking into account the new CNSC contamination criteria.
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Appendix 11
AREA CLASSIFICATION
As an example, for Class C Radionuclides (most of the radionuclides on your license fall into this
category), the limit of 300 Bq/cm 2 applies only to those areas which are exclusively reserved for
radioisotope use. Areas where radioisotopes are used only occasionally should be treated as nonradioactive areas, and the stricter limit of 30 Bq/cm 2 should be used.
Background Information
The following equation is given in AECB document INFO-0545 to convert cpm to Bq/cm 2 :
Arem [Bq/cm2] = N (cpm) / [Efficiency x 60(sec/min) x Area(cm2) x F]
where:
Arem
N
Area
Efficiency
F
60
(1)
is the removable activity in Bq/cm 2
is the net count rate in counts per minute and equals: (total count rate - background count
rate), both in cpm
= Ntotal - Nbackground
is the area wiped (not to exceed 100 cm2)
is the efficiency of the LSC for the radioisotope in question
is the collection factor for the wipe that takes into account the fact that only a small
amount of removable activity is collected on a wipe. This factor is taken as:
0.01 (1%) for dry wipe
0.1 (10%) for wet wipe
sec/min conversion factor
In order to use equation (1), the efficiency of the LSC for all isotopes which will be assayed in it must
be known. The efficiencies of LSCs vary and depend upon the energy of the radiation emitted (or in other
words, on the radioisotope). Typical efficiencies of a LSC (Rackbeta 1219) are given in the Table below:
Isotope
Efficiency
(as per instruction manual)
3H
60 %
14C
95 %
32P
99 %
35S
95 %
The problem with using these efficiency figures for contamination control type of measurements
are:
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Appendix 11
Last revision of this Appendix on: February 28th, 2006
(1) The number of counts detected can vary considerably with the quality of the sample. For
instance, a swipe from a dirty area would typically yield counts lower than that from an identical
swipe collected from an area which is clean because the dirt dispersed in the scintillation cocktail
would not allow all the light to pass through it.
(2) The counting efficiency of LSCs depends upon the radioisotope (specifically on the energy of
the  or  emission). Therefore, when several radioisotopes are used in a specific working area,
how should one account for different efficiencies?
(3) Counting efficiency measurements given in the instrument manuals are made under very
specific and controlled conditions.
The bottom line is that the use of counting efficiencies of LSCs for cpm to Bq/cm 2 conversion in
wipe test measurements is imprecise. It can lead to considerable errors in the estimation of the
actual contamination.
To minimize the confusion and to eliminate the guesswork associated with this type of conversion, we at
the MNI/H radiation safety office have decided to adopt a universal efficiency factor of 50% for all
radioisotopes and all liquid scintillation counters. By doing this, we will be overestimating the
contamination in some cases, but the error will always be on the side of caution, so that there will be
no risk of overlooking any contamination whatsoever.
Method
ASSUMING the wiped area is 100 cm2, and your instrument (LSC) gives results in CPM, Table A
contains the necessary information to determine the presence of unacceptable levels of contamination by
answering the following questions:
First: Determine what class the radioisotope you are wipe-testing for belongs to by consulting Appendix
3. If you have been using radioisotopes that belong to more than one class, use the row in Table A that
shows the lower CPM values.
Example: You have used P-32 (Class C) and I-131 (Class B) during the same experiment on the same
bench. In this case, you have to use the row belonging to Class B in order to determine whether
contamination levels are within CNSC limits.
The remaining steps are as before:
1.
Area TYPE: Is the area wiped classified as an area where radioisotopes are used?
a.
YES
USE Column (3)
b.
NO
USE Column (4)
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Appendix 11
2.
Swipe TYPE: Did you wipe the area with a wet wipe?
a.
YES
USE Column labeled (A)
b.
NO
USE Column labeled (B)
3.
What is the net count rate for your sample IN CPM?
Sample count rate (CPM) = total count rate from sample (CPM) - background count rate
(CPM) = Ntotal - Nbackground
N.B.: The background count, Nbackground , is obtained by using a blank wipe and assaying it the
same way as a regular wipe. In other words, take a clean swipe, place it in a vial, add the
scintillation cocktail and “count” it.
4.
Is the net count rate in CPM of your sample greater than the count rate given in the table?
a.
b.
YES
NO
Contamination exists, cleanup is required. See box below.
No contamination. Cleanup may still be required. See box below.
REMEMBER: TABLE A MAY ONLY BE USED IF ALL OF THE FOLLOWING CONDITIONS
ARE SATISFIED:
(A)
(B)
THE WIPED AREA MEASURES ~100 cm2. (It is not necessary to wipe a 10 x 10 cm2
square area. Swipes covering an irregular area roughly 100 cm2 in extent are
acceptable).
THE LSC GIVES RESULTS IN CPM.
The numbers in Table A were obtained by performing a “back-calculation” and estimating the net counts
per minute, N, using equation (1).
How Do these New Regulations Affect You?
Routine contamination monitoring is done to ensure safe working conditions for all personnel. Having
explicit limits (Table A) for different working areas eliminates guesswork from the process of
contamination control so that one standard method is used for all labs at any institution.
A copy of Table A must be kept in your wipe test folder. At the MNI/H, a copy of the most recent wipe
test is required before radioactive materials are approved for purchase by the radiation safety office.
Please notice the importance of assessing compliance with contamination criteria in the
light of the following 3 important determinants:
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Appendix 11
(a)
(b)
(c)
The type of swipe (wet or dry).
The classification of the area (whether used for radioisotope work or not). Areas where
radioisotopes are used should be clearly indicated on the swipe test results. Remember there are
areas which are used only for work involving radioisotopes and nothing else. Identify these areas
either on the lab layout diagram itself or on the table used to report the count rates in different
areas. All other areas including “safe” work benches, desks etc. fall under the stricter
contamination criteria (column 4
The type (Class) of radioisotopes that have been used.
WHAT CONSTITUTES CONTAMINATION?
The Radiation Safety Committee and the MNI/H radiation safety office are committed to keeping
radiation levels ALARA (as low as reasonably achievable). Therefore, the acceptable limits for
contamination in effect at the MNI/H have been set at a much lower level than those prescribed by
the CNSC contamination criteria (Table 1).
Rule: Areas where detected total counts are more than 3 times
the background level will be considered as contaminated and
a clean-up will be required.
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Last revision of this Appendix on: February 28th, 2006
Appendix 11
Table A
CPM - to - Bq /cm2 Conversion Rules for all
Liquid Scintillation Counters at the MNI/H
(1)
(2)
(3)
(4)
Radio- Efficiency Net Counts in CPM indicating
Isotope
(%)
the presence of contamination
in areas
where radioactivity is used
(A)
(B)
Wet Wipe
Dry Wipe
Net Counts in CPM indicating the
presence of contamination in areas
where radioactivity is NOT used
(A)
Wet Wipe
(B)
Dry Wipe
Class C
50
90,000
9,000
9,000
900
Class B
50
9,000
900
900
90
Class A
50
900
90
90
9
THE INFORMATION GIVEN IN COLUMNS (3) and (4) OF TABLE A MAY BE USED ONLY IF ALL OF
THE FOLLOWING CONDITIONS ARE SATISFIED:
(A)
THE WIPED AREA MEASURES 100 CM 2. (It is not necessary to wipe a 10 x 10 cm2
square area. Swipes covering an irregular area roughly 100 cm2 in extent are
acceptable).
(B)
THE LSC GIVES RESULTS IN CPM.

Only valid for those areas reserved exclusively for work involving radioisotopes. For all
other areas, the data in column (4) apply.
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Appendix 12
Appendix 12
Internal Inspection Checklist
(Last update: July 25th, 2004)
Lab Director: ________________________ Lab Room Numbers: _______________________
Survey Performed with: __________________________________ Phone: _______________
CHECKLIST
O.K.
NOT
O.K.
COMMENTS
N/A
general lab conditions
number of occupants
lab lockable
fume hoods, air flow
int. permit posted
safety rules posted
no food & drink in lab
chair & bench covers
lab-coats & gloves
TLD badge worn if req.
r.i. inventory updated
working area labeled
r.i. labeled & locked
disposal area labeled
warning signs posted
radiation log book etc.
meter: cal., battery O.K.
Rad. Saf. Man. available
wipe tests updated
eye wash(test) / shower
rad. safety education
sealed sources used
Overall Rating
A (excellent) B (acceptable)
C (can improve) D (fail)
Lab Representative: _____________________________________Date:_________________
Radiation Safety Officer: __________________________________Date:_________________
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Appendix 13
Appendix 13
Request for Decommissioning of Radioisotope Laboratory
This form must be filled out by the Primary Investigator / Lab Director when a lab licensed for radioisotope
use is either vacated or use of radioactive materials is stopped. The CNSC requires that a record of
inventory disposition as well as the final wipe test results be forwarded to the Radiation Safety Office.
RADIOISOTOPE USER PERMIT INFORMATION:
Internal Permit Number:
Primary Investigator / Lab Director:
Department:
Room number of lab to be
decommissioned:
This is to certify that I do not intend to continue the use of radioisotope in the above mentioned
room.
INVENTORY INFORMATION:
(check all applicable)
I have no radioactive material currently at this location.
All radioactive material obtained on the permit has been disposed of as per
guidelines.
All radioisotope inventory stored at the above location has been transferred to
Room: ______________ which is licensed for the use/storage of radioisotope.
All radioisotope inventory stored in the above location has been transferred to
the lab of
_____________________________________ who holds a valid MNI/H internal
license.
The location of this lab is:__________________
All radiation warning signs and labels have been removed.
Other(specify):
SIGNATURES:
Primary Investigator:
Date:
RSO:
Date:
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Appendix 14a
Appendix 14a
(From: Radiation Safety Officer’s Handbook)
Physical Characteristics for Commonly Used Radionuclides
Major Radiation Energies a, b or c in
MeV (abundance in %)
Radionuclide
HalfLife
Beta
3
H
12.3 y
R h-1
mCi-1
at 1 cmab
Gamma
0.018 (100)
+ 0.97(100)
Specific Gamma-Ray
Constant
Shielding Data
mGy h-1
MBq-1
at 1 cm
Half-Value
Layer in Pb
(mm) a, c
Maximum
Range of
Beta
Particles
in Water
(mm)d
Tenth
Value
Layer in
Pb
(mm)d
-
-
-
-
-
0.007
0.511(200)
5.91
1.6
4
-
-
11
20.3 m
14
5730 y
0.16
-
-
-
-
-
0.3
13
10.0 m
+ 1.20(100)
0.511(200)
5.91
1.6
4
-
-
15
2.0 m
+
.74(100)
0.511(200)
5.91
1.6
4
-
-
18
1.8 h
+ 0.65(97)
0.511(194)
5.73
1.5
4
-
-
22
2.6 y
+ .546(90)d
1.275(100)d
12
3.2
10
37
(2.0)d
24
15.0 h
1.4(100)
1.369(100)
18.4
4.96
15
59
6.4
32
14.3 d
1.7(100)
-
-
-
-
-
8.2
33
25.4 d
0.249(100)
-
-
-
-
-
0.7
35
88.0 d
0.17 (100)
-
-
-
-
-
0.33
0.709(98)
-
-
-
-
-
2.8
C
C
N
O
F
Na
Na
P
P
S
36
CI
301000
y
45
165 d
0.25(100)
-
-
-
-
-
0.7
47
4.56 d
0.67(82)
1.98(18)
0.490(5)
0.815(5)
1.398(74)
5.7
1.541
-
-
9.7
51
27.8 d
-
0.320(9)
0.164
0.04
2
7
-
Ca
Ca
Cr
Radiation Safety Manual of the
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Last revision of this Appendix on: February 27th, 2006
Appendix 14a
Appendix 14a (continued)
Major Radiation Energies a, b or c in
MeV (abundance in %)
Radionuclide
HalfLife
Beta
55
Fe
59
Fe
Gamma
mGy h-1
MBq-1
at 1 cm
Half-Value
Layer in Pb
(mm) a, c
Maximum
Range of
Beta
Particles
in Water
(mm)d
Tenth
Value
Layer in
Pb
(mm)d
-
0.0059(23)
-
-
-
-
-
-
0.27(46)
0.46(53)
1.56(0.3)
0.19(2.4)
1.1(43)
6.19
1.7
11
44
-
0.09(15)
0.93(40)
0.185(24)
0.296(22)
0.388(7)
0.95
0.26
0.7
-
-
0.511(176)
5.37
1.45
4
-
-
0.93
0.25
0.3
~0.7
-
78 h
68
1.13 h
Ga
R h-1
mCi-1
at 1 cmab
Shielding Data
2.7 7
67
Ga
Specific Gamma-Ray
Constant
+ 1.90(87)
57
267 d
-
0.014(9)
0.122(87)
60
5.26 y
0.31(99 +)
0.173(100)
13.2
3.568
12
40
-
83
100.1 y
0.066
-
-
-
-
-
-
0.511(38)
1.16
0.31
4
-
-
1.150(49)
2.7
0.73
10
42
-
2
0.541
2
5.1
Co
Co
Ni
64
12.9 h
65
245 d
Cu
Zn
0.057(39)
+ 0.64(19)
1.1
0.33(2)
120 d
0.08-0.25 e
0.121(16)
0.136(57)
0.265(60)
0.280(25)
0.401(13)
192
74.2 d
-
-
-
-
-
-
-
198
2.7 d
0.97(99)
0.412(96)
2.34
0.632
0.3
-
-
203
47 d
0.214(100)
0.279(82)
1.33
0.359
-
-
-
-
0.135(2.6)
0.167(10)
x-rays 0.068
- 0.08(95)
0.44
-
0.2
0.9
-
75
Se
Ir
Au
Hg
201
Ti
73 h
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Version No.: 2
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Last revision of this Appendix on: February 27th, 2006
Appendix 14a
Appendix 14a (continued)
Explanation of Subscripts
a
Padikal TN & Fivozinsky SP, Medical Physics Data Book, National Bureau of Standards
(1982)
b
ICRP Publication 25: The Handling, Storage, Use and Disposal of Unsealed
Radionuclides in Hospitals and Medical Research Establishments (1971)
c
Gordon K, Shields R and Kovarov El :Manual on Radiation Protection in Hospitals and
General Practice: Volume 4 Unsealed Sources, jointly sponsored by IAEA / ILO / WHO /
PAHO / CEC
d
Institute of Physical Sciences in Medicine Report 63: Radiation Protection in Nuclear
Medicine and Pathology (1991)
e
To describe the clearance of inhaled radioactive materials from the lung, materials are
classified as D, W or Y which refer to their retention in the pulmonary region. This
classification applies to a range of half-times for D of less than 10 days, for W from 10 to
100 days and for Y greater than 100 days. In the interest of simplicity when creating the
above table, the most restrictive inhalation ALI was selected. The same strategy was
applied for different values of ingestion ALIs in ICRP 61. Note that besides applying a
lower annual dose limit, ICRP-61 uses a new system of tissue weighting factors. Please
refer back to the original ICRP publications (see f and g below) for more detailed
information.
f
ICRP Publication 30: Limits for Intakes of Radionuclides by Workers, Part 1 (1979), Part
2 (1980) and Part 3 (1981)
g
ICRP Publication 61: Annual Limits on Intake of Radionuclides by Workers Based on the
1990 Recommendations (1991)
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Appendix 14b
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Version No.: 2
September 1st, 2007
Appendix 14c
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Appendix 14d
Appendix 14 (d)
INFO-O700 (E)
DOSE LIMITS FOR PREGNANT WORKERS
RATIONALE FOR THE LIMITS IN THE
RADIATION PROTECTION REGULATIONS
by
Radiation and Environmental Protection Division
Atomic Energy Control Board Ottawa, Ontario
January 1999
Radiation Safety Manual of the
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Version No.: 2
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Appendix 14d
Last revision of this Appendix on: February 27th, 2006
Dose Limits for Pregnant Workers--Rationale for the Limits in the Radiation Protection Regulations
Published by the Atomic Energy Control Board
AECB Catalogue number INFO-O700 (E)
@ Minister of Public Work and Government Services Canada 1999
Extracts from this document may be reproduced for individual use without permission provided
the source is fully acknowledged. However, reproduction in whole or in part for purposes of
resale or redistribution requires prior written permission from the Atomic Energy Control Board.
This publication is distributed free of charge upon request. For additional copies, or for further
information about the AECB, please write or call:
Communications Division
Atomic Energy Control Board
P.O. Box 1046, Station B
Ottawa, Ontario KIP 5S9
Telephone: (613) 995-5894 or 1-800-668-5284
Fax.: (613) 992-2915
E-mail: info@atomcon.gc.ca
Web site: www.gc.ca/aecb
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Appendix 14d
Table of Contents
SUMMARY
HISTORICAL BACKGROUND
OTHER INFORMATION ON RISK TO THE EMBRYO AND FOETUS
TABLE 1:
Estimates of the effects of low doses of radiation on the human
embryo and foetus
TABLE 2:
Comparison of risks to the foetus during pregnancy
TABLE 3:
Risk of childhood cancer per 10 000 exposed from 4 mSv of
radiation dose to embryo and foetus, from other publications
REFERENCES
Radiation Safety Manual of the
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Version No.: 2
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Appendix 14d
Last revision of this Appendix on: February 27th, 2006
SUMMARY
When a nuclear energy worker (NEW *) becomes pregnant, she is required by the new
Radiation Protection Regulations to declare her pregnancy to the licensee associated with her
workplace. The licensee may not be her employer (she may work for a contractor), but it is the
licensee who is obliged by the regulations to inform all NEWs of the health risks due to
radiation, including the particular risks to the foetus, and it is the licensee who must be notified
in writing of the pregnancy. The licensee is required by the same regulations to ensure that the
woman's dose does not exceed the more restrictive limit for pregnant NEWs, i.e., 4mSv
effective dose to the abdomen or an intake of 0.2 ALl. This combination of limits on external and
internal radiation is intended to limit the effective dose to the foetus to 4mSv during the
remainder of the pregnancy following declaration. The limit is lower than the regular NEW limits
of 50mSv in a single year and 100 mSv in five years because of the greater sensitivity of the
embryo and foetus to radiation.
This document discusses the AECB' s rationale for proposing the 4mSv dose limit for pregnant
workers in the new Radiation Protection Regulations. This dose limit is higher than the limit of
2mSv which was recommended by the ICRP in its Publication of 60 and proposed by the AECB
in its Consultative Document C-122 (1991).
The reasons for proposing a dose limit of 4mSv are based mainly on an assessment of the risks
of detriment to the embryo and foetus. They can be enumerated as follows:
i)
fundamentally, 4mSv is a low dose, and measuring it with precision is difficult;
ii)
the risk to the embryo and the foetus associated with a dose of 4mSv to the mother is
very small;
iii)
the risk to the embryo and the foetus from a dose of 4mSv is certainly very small when
compared to the risks from other sources;
iv)
during consultations leading to the adoption of the new limit, workers affected by it
indicated to the AECB that the risk implications were acceptable;
v)
adoption of the ICRP 60's recommended limit of 2mSv could lead to discrimination
against women, because some employers might conclude that the only effective method
of compliance with the very low dose limit would be to remove a pregnant worker from
work with radiation, or not hire women at all.
*)
[NEW: Nuclear energy worker is defined in the Nuclear Safety and Control Act as a
person who is required, in the course of the person's business or occupation in
connection with a nuclear substance or nuclear facility, to perform duties in such
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Appendix 14d
Last revision of this Appendix on: February 27th, 2006
circumstances that there is a reasonable possibility that the person may receive a dose
of radiation that is greater than the prescribed limit for the general public.]
HISTORICAL BACKGROUND
i)
Publication C-122: Proposed Amendments to the Atomic Energy Control Regulations for
Reduced Radiation Dose Limits Based on the 1991 Recommendations of the ICRP.
The Consultative Document C-122 was published in July 1991, announcing the AECB's
intention to incorporate the ICRP 60 recommendation into the regulations. A dose limit of 2mSv
to the surface of the abdomen and an intake of 0.05 AU were proposed for pregnant workers.
The ICRP had stated that protection of the foetus should be "broadly comparable" to that of the
general public. However, in ICRP 60 it was not clear whether the external dose limit was to be in
addition to the internal limit. The AECB has interpreted the recommended dose limit of 2 mSv as
a combination of a 1mSv limit for external radiation and a 1 mSv limit for the effect of intakes of
radioactive material by the mother during her pregnancy. A dose limit of 2 mSv during
pregnancy was interpreted by the AECB as "broadly comparable" to the annual 1 mSv dose
limit for the public.
ii)
Public consultations on C-122
During the public consultations of C-122, the proposed 2mSv dose limit was criticized by some
interested parties as being unnecessarily low. The critics noted that doses at this level,
especially those from the internal component, would be difficult to measure and compliance
would be difficult to demonstrate. It was feared by workers who submitted comments that some
employers might conclude that the only effective method of compliance with the dose limit of
2mSv would be to remove a pregnant worker from work with radiation. If other work were not
available, this could result in a lay-off, and eventually might lead to discrimination against the
hiring of women for some types of radiation work.
iii)
Public meetings and the technical presentations on the risk to the embryo and foetus
from prenatal exposure
The AECB felt that it was necessary to give those radiation workers who were most likely to be
affected an opportunity to present their views directly to AECB staff. Therefore, a series of eight
public meetings was held in seven cities across Canada, and at a mine site, to obtain further
comments. The main objective of these meetings, attended by a total of 338 people, was to
discuss the proposed limit of 2mSv with the female workers and to include them in the decision
making process. During the meetings, an AECB consultant (Dr. D. Myers) presented the risks to
the embryo and foetus from 2mSv as well as the risk from natural causes. A report entitled
Comments on ICRP 60 Rationale for Dose Limits for the Pregnant Worker (INFO-0421) was
used for this purpose. It indicated that a dose of 2 mSv to the embryo and foetus would carry a
risk of 1:10,000 for childhood cancer. For fatal cancer in later life, 2mSv to the embryo and
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Appendix 14d
Last revision of this Appendix on: February 27th, 2006
foetus carries a risk of 3:10,000. These risks were compared to the risks which the foetus faces
from natural causes, which are much higher. Table 1 shows the comparison of the risks from
10mSv, 4mSv and 2mSv with the natural occurrence of fatal and non-fatal cancers. Table 2
Women who work in the uranium mining industry receive some exposure from inhaled radon
progeny. Calculations based on the latest ICRP lung model (LUDEP) show that since most of
the inhaled radioactive material is deposited in the mother's lung, the dose to the foetus is about
1/1000 of the lung dose. Therefore, the normal occupational limit for radon progeny affords
adequate protection for the foetus.
The meeting participants were presented with data from the National Dose Registry (NDR) for
doses received by pregnant workers. Since 198 contains a list of a number of natural risks to a
foetus. Because choosing a dose limit is mainly a risk-based decision, it is important to note that
the quantitative risk estimates for very small doses have many uncertainties. Therefore, the
numbers presented in Table 1 should not be interpreted as exact figures but as approximate
values.
6, 300 to 400 pregnant workers have been monitored for external radiation doses each year.
The maximum dose to any individual, recorded for the remainder of the pregnancy following
declaration, varied from 1.3mSv to 2mSv. The dose limit at the time was 10mSv to the abdomen
of the worker.
The NDR data for the category of nuclear medicine technologist (not those who are pregnant)
indicate that 50% of these workers receive less than 2mSv per year, and only 5% receive more
than 5mSv per year. These doses are well below the occupational limits and should not be a
source of concern to the majority of workers in this field. Female workers in other sectors of the
nuclear industry may receive higher average doses but it is expected that in most of these
cases the licensee would be able to transfer them to jobs with lower doses if they became
pregnant.
The NDR data cited above do not include any contribution from internal contamination.
Information that is available at present suggests that this does not make a major contribution to
total dose in most cases.
The participants at the meetings were of the general opinion that slightly higher risks, i.e., about
double that from 2mSv, would be acceptable when compared to the risks to the foetus from
natural causes. Following the technical presentations, a majority of the workers* who would be
most affected by the proposed limit suggested a dose limit of4 or 5mSv during pregnancy; a
value between the previous limit of 10mSv and the ICRP's recommendation of 2mSv. (* One
group of workers did not support the higher limit. This group was subject to general labor code
regulations in their province which were seen as more advantageous to workers who became
pregnant.)
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14d
OTHER INFORMATION ON RISK TO THE EMBRYO AND FOETUS
Table 3 summarizes additional information obtained from other publications on the effects of
radiation exposure to the embryo and foetus.
BEIR V, 1990: For childhood cancer, the risk estimate quoted in ICRP 60 is 2.8 x
10-5 per mSv (or 1:10000 for 4mSv). The same data were analyzed earlier by
Gilman et at. (1989) showing a risk estimate of 13 x 10-5 per mSv (or 5:10,000 for
4mSv).
UNSCEAR 1994: UNSCEAR concluded that studies of uterine exposure gave a
wide range of risk estimates from relatively high to essentially undetectable risk,
including (possibly) none at all. It was stated in the report that there was no
biological reason to assume that the embryo or foetus is radiation resistant, but
the exact quantification of effects was subject to much uncertainty. Based on the
more recent analysis of the Oxford survey of childhood cancer, risk for mortality
of all childhood cancers is about 5 x 10-5 per mSv. This value corresponds to a
mortality risk of 2: 10 000 for 4mSv prenatal exposure.
NCRP 1994: A Commentary by the NCRP entitled Considerations Regarding the
Unintended Radiation Exposure of the Embryo, Foetus or Nursing Child, May
1994, which is the most recent NCRP publication on the subject, includes a
section on radiation risks which reviews information from other NCRP
publications. For childhood cancer induction following prenatal exposure, the
Commentary concludes that the risk is numerically about the same as for the
irradiation of young children, i.e., 10 x 10-5 per mSv (or 4: 10000 for 4mSv). For
heritable effects, i.e., effects in the foetal genetic material that will be expressed
in foetus' descendants, the risk is given as 10-5 per mSv. This figure is derived
from animal experiments and no human study has shown such risks.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14d
TABLE 1:
Estimates of the effects of low doses of radiation on the human embryo and
foetus
Risk for foetus
following 10mSv
exposure over the
8 months of
pregnancy (per
10,000)
Risk for the foetus
following 4mSv
exposure over the
8 months of
pregnancy (per
10,000)
Childhood
cancers
5*
2
1
200
Life-time cancers
15
6
3
2500
Health detriment
Risk for the
foetus following
2mSv exposure
over the 8
months of
pregnancy (per
10,000)
Spontaneous
incidence per
10,000 live
births
Source:
Modified from Myers O.K. Comments on ICRP 60: Rationale for Dose Limits for
the Pregnant Worker (INFO-0421), June 1992.
*
This risk estimate is derived from a risk coefficient = 5 x 10-2 per Sv (95% Cl, 0.8
x 10-2 -9.5 x 10-2 per Sv) from Mole R.H. (1990).
Radiation Safety Manual of the
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Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14d
TABLE 2:
Comparison of risks to the foetus during pregnancy
Pregnancy Outcome
(Effect)
Risk of Occurrence
(% of foetus exposed to
risk factor that develop the
effect)
Maternal German Measles
Defects of heart, lens of the eye,
skeletal muscle, inner ear, teeth
67%
Maternal cigarette smoking
Low birth weight
20%
Maternal alcohol
consumption:
2 drinks/day
Low birth weight
10%
Signs of foetal alcohol syndrome
(growth
deficiency, brain
dysfunction, characteristic facial
signs)
10%
Risk Factor
2-4 drinks/day
4 drinks/day
chronically alcoholic
Maternal age:
<20 years
35-39 yrs.
Living at high altitude:
5000 ft.
Unknown
Unknown
Genetic
Down’s syndrome (mental and
physical growth retardation)
Low birth weight
20%
50%
0.04%
1.5%
10%
Developmental anomaly
2-4%
Intrauterine growth retardation
2-3%
ABO haemolytic disease
1%
Chromosomal abnormalities
Unknown
0.5%
(natural incidence)
Major malformation rate at
Unknown
2.75%
delivery
Malformation and genetic
Unknown
6-10%
diseases at 1-2 yrs. Of age
Spontaneous abortion during
Unknown
30-50%
pregnancy
Childhood leukaemia deaths
0.03%
Embryo or foetal irradiation:
before age 12
10 mSv
Deaths from other childhood
0.03%
cancers before age 10
Source: Medical Effects of Ionizing Radiation, Mettler, F.A. and Moseley, R.D.; Grune and
Stratton Inc. 1985.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14d
TABLE 3:
Risk of childhood cancer per 10 000 exposed from 4 mSv of radiation dose to
embryo and foetus, from other publications
Health detriment
Gilman et al.
(1989)
BEIR V (1990)
UNSCEAR
(1994)
NCRP
(1994)
5*
1**
2@
4#
Childhood
cancers
The risk estimates in the table are derived from the following risk coefficients:
*
Risk estimate = 13 x 10-2 per Sv (95% CI, 8.4 x 10-2 -19.2 x 10-2 per Sv)
**
Risk estimate = 2.8 x 10-2 per Sv (upper bound risk estimate)
@
Risk estimate = 5 x 10-2 per Sv (95% CI, 0.8 x 10-2 -9.5 x 10-2 per Sv)
(from Mole R.H. et al. 1990)
#
Risk estimate = 10 x 10--2 per Sv
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14d
REFERENCES
1.
2.
3.
4.
5.
6.
7.
8.
Consideration regarding the unintended radiation exposure of the embryo foetus
or nursing child (1994). NCRP Commentary No.9, National Council on Radiation
Protection and Measurements, Bethesda, Maryland.
Gilman E.A., Kneale, G.W., Knox, E.G. et al. (1989) Recent estimates of the risk
of childhood cancer following the irradiation of the foetus in: Low Dose Radiation
Biological Basis of Assessment (K.F. Baverstock and J. W. Stather eds), Taylor
and Francis, London.
Health Effects of Exposure to Low Levels of Ionizing Radiation (1990).
Committee on the Biological Effects of Ionizing Radiations. National Research
Council, National Academy Press, Washington D.C.
International Commission on Radiological Protection, ICRP Publication 60
(1991), Pergamon Press.
Mettler, F.A. and Moseley, R.D.: Medical Effects of Ionizing Radiation, Grune &
Stratton Inc., 1985.
Mole, R.H.: Fetal dosimetry by UNSCEAR and risk coefficients for childhood
cancer following diagnostic radiology in pregnancy (1990). J. Radiol. Prot. 10, pp.
199-203.
Mole, R.H.: Childhood cancer after prenatal exposure to diagnostic x-ray
examinations in Britain (1990). Brit. J. Cancer 62, pp. 152-168.
Sources and Effects of Ionizing radiation. United Nations Scientific Committee on
the Effects of Atomic Radiation. 1994 Report to the General Assembly.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Appendix 14e
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MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
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Appendix 14f
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MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
September 1st, 2007
Appendix 14g
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MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
September 1st, 2007
Appendix 14h
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MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
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Appendix 14i
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MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
September 1st, 2007
Appendix 14k
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MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
September 1st, 2007
Appendix 14l
Radiation Safety Manual of the
MNI/H
Last revision of this Appendix on: February 27th, 2006
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14m
Appendix (14m)
Canadian Nuclear Safety Commission
Radiation Safety Data Sheet
This data sheet presents information on radioisotopes only.
For information on chemical compounds incorporating this radionuclide, see the relevant Material Safety Data Sheet.
Part 1 - RADIOACTIVE MATERIAL IDENTIFICATION
Chemical Symbol:
P
Common Names:
Phosphorus
Atomic Weight:
32
Atomic Number:
15
Part 2 – RADIATION CHARACTERISTICS
Physical Half-Life:
14.3 days
CNSC Exemption Quantity (in Bq):
10 kBq
A CNSC license is not required if the amount of radioactive nuclides possessed is less than one
Exemption Quantity.
Average
Energy
(MeV)**
Maximum
Energy
(MeV)***
Dose Rate at 1m
(mSv/h) / (GBq)
Recommended
Shielding
Neutrons
-
-
-
-
Gamma & X-rays
-
-
-
-
Beta*
0.6947
1.710
9.17
1 cm Plexiglas
Alpha
-
-
-
-
Principal Emissions
*
Where beta radiation is present, Bremsstrahlung radiation will be produced. Shielding may therefore be
required.
**
***
Average energy of most abundant emission.
Maximum of most abundant emission.
Progeny
Radiation Safety Manual of the
MNI/H
n/a
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 14m
Part 3 – DETECTION AND MEASUREMENT
Method of Detection:
Geiger-Mueller detector, gamma survey meters with sodium iodide crystal detectors
Dosimetry:
External:
TLD (whole body & skin ______
Internal:
Whole body __X__
Thorax ____
Extremity ________
Neutron
_________
Urine analysis ___X____ Other (specify) ____
Part 4 - PREVENTIVE MEASURES
Chromic acid and its salts have a corrosive action on the skin and mucous membranes. Sodium
phosphate is a mild irritant. Phosphocol and Sodium Phosphate (P-32) solutions may emit radioactive
fumes containing P-32 when heated to decomposition.
Recommended protective clothing: Disposable plastic, latex, or rubber gloves. Lab coat. Safety glasses.
Keep handling time to minimum. Use syringe shields (aluminum or lead foil) and tongs to avoid direct
skin contact. When possible work behind a Plexiglas screen. Finger dosimeters should be worn if using
quantities greater than a few tens of MBq (~a mCi). Vial should be encased in Lucite.
Always use the principles of time, distance and shielding to minimize dose. Consult CNSC license for
requirements concerning engineering controls, protective equipment, and special storage requirements.
Part 5 - ANNUAL LIMIT ON INTAKE
Ingestion
Inhalation
Compound Type
All compounds
All compounds
Annual Limit on
Intake (MBq)
8
8
EMERGENCY PROCEDURES
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Appendix 14m
Last revision of this Appendix on: February 27th, 2006
The following is a guide for first responders. The following actions, including remediation, should be
carried out by qualified individuals. In cases where life threatening injury has resulted, first treat the
injury, second deal with personal decontamination.
Personal Decontamination Techniques
Wash well with soap and water and monitor skin
Do Not abrade skin, only blot dry
Decontamination of clothing and surfaces are covered under operating and emergency procedures
Spill and Leak Control
Alert everyone in the area
Confine the problem or emergency (includes the use of absorbent material)
Clear area
Summon Aid
Emergency Protective Equipment, Minimum Requirements
Gloves
Footwear Covers
Safety Glasses
Outer layer or easily removed protective clothing
Suitable respirator selected
Revision number: 0
Radiation Safety Manual of the
MNI/H
Date of revision: 5 April 2004
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: Feb ruary 27th, 2006
Appendix 15
Appendix 15
Exemption Quantities (EQ) for Radioactive Nuclear Substances
appearing on CNSC licenses issued to the
Montreal Neurological Institute
(Last update: November 22, 2005)
From: Schedule in Nuclear Substances and Radiation Devices Regulations (May 31, 2000) and Appendix
C to License Application Guide C-237, and e-mail message from CNSC (Cu-64, I-124).
Useful Multiples of Exemption Quantities (EQs) in Bq (mCi)
Radioisotope
1 EQ
100 EQs
10'000 EQs
C-11
0.1 MBq
2.7 µCi
10 MBq
270 µC i
1 GBq
27mCi
C-14
100 MBq
2.7mCi
10 GBq
270mCi
1TBq
27Ci
O-15
1 MBq
27 µCi
100 MBq
2.7mCi
10 GBq
270mCi
Ca-45
1 MBq
27 µCi
100 MBq
2.7mCi
10 GBq
270mCi
Cr-51
1 MBq
27 µCi
100 MBq
2.7mCi
10 GBq
270mCi
F-18
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
-
-
Fe-55
-
-
-
-
Cu-64
0.1 MBq
2.7 µCi
10 MBq
270 µC i
1 GBq
27mCi
Ga-68
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
H-3
1 GBq
27mCi
100 GBq
2.7Ci
10 TBq
270Ci
I-124
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
I-125
1 MBq
27 µCi
100 MBq
2.7mCi
10 GBq
270mCi
I-131
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
P-32
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
P-33
1 MBq
27 µCi
100 MBq
2.7mCi
10 GBq
270mCi
S-35
100 MBq
2.7mCi
10 GBq
270mCi
1TBq
27Ci
Tc-99m
10 MBq
0.27mCi
1 GBq
27mCi
100 GBq
2.7Ci
Ge-68
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
Cs-137
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
Na-22
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
Ra-226
10 kBq
0.27µCi
1 MBq
27µCi
100 MBq
2.7mCi
Eu-152
-
-
-
Co-57
0.1 MBq
Radiation Safety Manual of the
MNI/H
2.7µCi
10 MBq
270 µC
-
-
1 GBq
27mCi
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 16
Appendix 16
Area Classification Requirement as per CNSC License
Application Guide C-237, Appendix C
For labs where more than one Exemption Quantity of an
unsealed nuclear substance is used at a single time.
ALI stands for Annual Limit on Intake (ingestion if not otherwise specified; see also e-mails from CNSC)
(Last update: February 27th, 2006)
Radioisotope
Activity Limits in Bq (mCi)
Basic- Level
Interm.-Level
High-Level
Cont.- Level
(Act. < 5 ALI)*
(Act. < 50 ALI)*
(Act. < 500 ALI)*
(Act. > 500 ALI)*
C-11
30 GBq
810mCi
300 GBq
8.1Ci
3 TBq
81Ci
3 TBq
81Ci
C-14
170 MBq
4.5mCi
1.7 GBq
45mCi
17 GBq
450mCi
17 GBq
450mCi
O-15water*)
0.107 TBq
2.9Ci
1.07TBq
29Ci
10.7 TBq
290Ci
10.7TBq
290Ci
Ca-45
30 MBq
0.8mCi
300 MBq
8mCi
3 GBq
80mCi
3 GBq
80mCi
Cr-51
2.65GBq
70mCi
26.5GBq
700mCi
265GBq
7Ci
265GBq
7Ci
F-18
2.00 GBq
55mCi
20 GBq
550mCi
200 GBq
5.5Ci
200 GBq
5.5Ci
Fe-55
500 MBq
14mCi
5 GBq
140mCi
50 GBq
1.4Ci
50 GBq
1.4Ci
Cu-64
500 MBq
13.5mCi
5 GBq
135mCi
50 GBq
1.35Ci
50 GBq
1.35Ci
Ga-68
1 GBq
27mCi
10 GBq
270mCi
100 GBq
2.7Ci
100 GBq
2.7Ci
H-3
5 GBq
140mCi
50 GBq
1.4Ci
500 GBq
14Ci
500 GBq
14Ci
I-124
7.5 MBq
0.2mCi
75 MBq
2mCi
750 MBq
20mCi
750 MBq
20mCi
I-125
5 MBq
0.13mCi
50 MBq
1.4mCi
500 MBq
14mCi
500 MBq
14mCi
I-131
5 MBq
0.13mCi
50 MBq
1.4mCi
500 MBq
14mCi
500 MBq
14mCi
P-32
40 MBq
1.1mCi
400 MBq
11mCi
4 GBq
110mCi
4 GBq
110mCi
P-33
400 MBq
11mCi
4 GBq
110mCi
40 GBq
1.1Ci
40 GBq
1.1Ci
S-35
130 MBq
3.5mCi
1.3 GBq
35mCi
13 GBq
350mCi
13 GBq
350mCi
Tc-99m
4.5 GBq
125mCi
45 GBq
1.25Ci
450 GBq
12.5Ci
450 GBq
12.5Ci
Ge-68
350 MBq
10mCi
3.5 GBq
100mCi
35 GBq
1Ci
35 GBq
1Ci
Cs-137
5 MBq
0.13mCi
50 MBq
1.4mCi
500 MBq
14mCi
500 MBq
14mCi
Na-22
30 MBq
0.8mCi
300 MBq
8mCi
3 GBq
80mCi
3 GBq
80mCi
N.B.: License condition 2108-2 states: Except for the Basic-Level classification, the licensee shall not
use unsealed nuclear substances in these rooms, areas or enclosures without written approval from the
CNSC.
*) value for intravenous O-15 water administration
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 17
Appendix 17
Weekly Contamination Survey Log
PERMIT HOLDER:
YEAR:
LAB. RADIATION
SUPERVISOR:
LAB. LOCATION:
WEEK
NO.
ISOTOPE
USE
NO ISOTOPE
USE
INITIALS
WEEK
NO.
1
27
2
28
3
29
4
30
5
31
6
32
7
33
8
34
9
35
10
36
11
37
12
38
13
39
14
40
15
41
16
42
17
43
18
44
19
45
20
46
21
47
22
48
23
49
24
50
25
51
26
52
Radiation Safety Manual of the
MNI/H
ISOTOPE
USE
NO ISOTOPE
USE
INITIALS
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 18
Appendix 18
PET Investigators Radiation Safety Information
(last revised: February 28th, 2006)
This form lists some simple rules and instructions on how to avoid unnecessary exposure
to radiation and is intended for investigators and associates who carry out research projects
that require their presence in the PET-Suite, but who do not handle radioactive substances
themselves.
Radiation Safety Rules
To be read by the PET Investigator in the presence of the RSO or an authorized delegate.
Please read carefully the following basic Radiation Safety items and other
Item
Check item
No. information which you should know to keep radiation exposure to yourself
when read and
understood.
and to your co-workers as low as reasonably achievable (ALARA).
I have read and understood the warning signs and posters displayed in
1
the PET-Suite.
I am not handling any radioactive substance or withdrawing blood
2
samples in the PET-Suite.
3
I am wearing my radiation monitor (TLD) and a lab. coat.
4
I am not eating, drinking or applying any make-up while in the PET-Suite.
5
I will wash my hands upon leaving the PET-Suite.
6
7
The radiation levels in the PET-Suite are highest around the subject being
scanned and close to the pneumatic system port and dose calibrator.
Also, I will not enter the scanning room while the transmission scan is in
progress.
Three ways to reduce radiation exposure to my body are summarized in the
principle of: Time, Distance and Shielding.
N.B.: I understand that non-compliance with the above rules may lead to the suspension of our
human PET research license issued by the CNSC.
PERSONAL INFORMATION
Name of PET investigator/associate:
Phone at work:
SIGNATURES
PET investigator/associate:
Date:
RSO or authorized delegate:
Date:
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Appendix 19
Last revision of this Appendix on: February 28th, 2006
Appendix 19
microPET Investigators Radiation Safety Information
(last revised: February 28th, 2006)
This form lists some simple rules and instructions on how to avoid unnecessary
exposure to radiation and is intended for investigators and associates who carry out
research projects that require their presence in the microPET-Suite (rooms 694 and
694A), but who do not handle radioactive substances themselves.
Radiation Safety Rules
To be read by the microPET Investigator in the presence of the RSO or an authorized delegate.
Please read carefully the following basic Radiation Safety items and other
Item
Check item
No. information which you should know to keep radiation exposure to yourself
when read and
understood.
and to your co-workers as low as reasonably achievable (ALARA).
I have read and understood the warning signs and posters displayed in
1
the microPET-Suite.
I am not handling any radioactive substance or withdrawing blood
2
samples in the microPET-Suite.
3
I am wearing my radiation monitor (TLD) and a lab. coat.
4
I am not eating, drinking or applying any make-up in the microPET-Suite.
5
I will wash my hands upon leaving the microPET-Suite.
6
7
The radiation levels in the microPET-Suite are highest around the object
being scanned, close to open or sealed radiation sources or the calibration
sources in room 694A.
Three ways to reduce radiation exposure to my body are summarized in the
principle of: Time, Distance and Shielding.
N.B.: I understand that non-compliance with the above rules may lead to the suspension of our
consolidated labs license issued by the CNSC.
PERSONAL INFORMATION
Name of investigator/associate:
Phone at work:
SIGNATURES
Investigator/associate:
Date:
RSO or authorized delegate:
Date:
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 28th, 2006
Appendix 19
Radioisotope Transfer Protocol from Cyclotron to Cone Lab (691, 693, 694)
or Animal Care Facility (8th floor)
This protocol concerns radio-pharmaceuticals labeled with the following positron
emitting tracers:
C-11
O-15
F-18
(T1/2 ~ 20 min)
(T1/2 ~ 2 min)
(T1/2 ~ 110 min)
1 EQ = 2.7 µCi
1 EQ = 27 µCi
1 EQ = 0.27 µCi
1
Always wear TLD radiation badge.
2
Use designated trolley and lead container.
3
Never transport more than 15mCi (370 MBq).
4
Properly label vial containing the radioactive substance (tracer,
pick-up).
5
6
(EQ is “Exemption Quantity”)
hem.. Form, activity, date of
Fill in licence transfer form (cyclotron license to labs license 01187-2-08.2 with Internal Permit
MNI_035_694 issued to Dr. Jean-Paul Soucy)
The route for transport is:
Cyclotron unit, sub-basement (by carpenters shop), elevator (93 or 94) from sub-basement to 6th
(Cone Lab) or 8th floor (Animal Care Facility). (Only if elevators 93 and 94 are out of order should
the route through the PET-Suite to the first (main) floor and elevators 67 or 68 (X-ray) be used.
7
Never use a crowded elevator (e.g., more than half a dozen passengers).
8
If elevator breaks down, ask passengers to stand along one wall and keep trolley on opposite
wall (in this way, the radiation exposure to all passengers is well within acceptable limits).
9
Upon arrival in microPET room, deposit radioactive substance with its inner container in
designated storage area in room 694A.
10
Keep an inventory in the microPET lab of radioactivity received and used.
N.B: The transport unit (Pb container and trolley) is designed such that the radiation field at the
circumference of the trolley is less than 25 micro-R/hr (0.25 micro-Sv/hr). This together with
an occupancy factor of 1/16th for the corridors and elevators used for the transfer results in an
additional radiation exposure for the public on the premises as well as for the operator of less
than 1/10th of the 1mSv/y limit for the general public.
Radiation Safety Manual of the
MNI/H
Version No.: 2
September 1st, 2007
Last revision of this Appendix on: February 27th, 2006
Appendix 20
Appendix 20
Regulatory quantities for some typical radio-nuclides
From: License Application Guide C-237 (Nuclear Medicine and Human Research)
Radionuclide
EQ
[MBq]
ALI
estim.
(ingestion)
[MBq /
year]
Intermediate
Level
[MBq]
Basic
Level
[MBq]
Wipes
Controlled
Area
[Bq /
cm2]
High
Level
[MBq]
Wipes
Public
Area
[Bq /
cm2]
Waste Disposal
Pub.
Pub.
Air
Garb. Sewer [kBq
[MBq / [MBq / / m3]
kg]
yr]
3
Br-82
0.1
37
185
1850
18’500
30
C-14
100
34
170
1700
17’000
300
30
3.7
10’000
-
Co-57
0.1
95
475
4750
47’500
300
30
0.37
1000
-
Co-58
0.1
27
135
1350
13’500
30
3
0.37
100
-
Co-60
0.1
6
30
300
3000
3
0.3
0.01
0.1
-
Cr-51
1
530
2650
26’500
265’000
300
30
3.7
100
-
F-18
0.01
400
2000
20’000
200’000
30
3
0.01
-
-
Fe-59
0.1
10
50
500
5000
30
3
0.01
1
-
Ga-67
1
100
500
5000
50’000
30
3
0.037
-
1000
1000
5000
50’000
500’000
300
30
37
100
1 Mio.
37
I-123
10
95
475
4750
47’500
300
30
3.7
1000
3
I-125
1
1
5
50
500
300
30
0.03
I-131
0.01
1
5
50
500
30
3
0.037 1'000’0
100
00
0.037
10
In-111
0.1
70
350
3500
35’000
30
3
0.037
100
-
Na-22
0.01
6
30
300
3000
3
0.3
0.01
0.1
-
P-32
0.01
8
40
400
4000
300
30
0.37
1
-
P-33
1
80
400
4000
40’000
300
30
1
10
-
Ra-226
0.01
0.07
0.35
3.5
35
3
0.3
0.01
1
-
S-35
100
26
130
1300
13’000
300
30
0.37
1000
-
Sb-127
0.01
8
40
400
4000
3
0.3
0.37
-
-
Sr-85
0.1
36
180
1800
18’000
30
3
0.37
Tc-99m
10
900
4500
45´000
450’000
300
30
3.7
1000
-
Tl-201
1
210
1050
10’500
105’000
300
30
0.037
100
-
100
GBq
-
-
-
-
300
30
1
-
3.7
H-3
Xe-133
Radiation Safety Manual of the
MNI/H
.175
10 .175
Version No.: 2
September 1st, 2007