Date: 08/08/12
PINS: PROJECT INITIATION NOTIFICATION SYSTEM FORM (Rev. 2009-ps)
*NOTE: Adoptions of international standards require compliance with ANSI’s Sales & Exploitation Policy.
1.
Designation of Proposed Standard:
ANS-57.11
2.
Title of Standard:
Integrated Safety Assessments for Fuel Fabrication Facilities
3.
Project Intent: (Check the applicable box below)
Supersedes or Affects: (Specify designation of approved ANSI standard(s) or international
standard(s)* affected or superseded.)
Create new standard
X
*Adopt identical international standard (see Expedited Procedures,
Section 1.2.9.2, Annex H: IDT and Annex I)
*Adopt modified international standard (see Requirements
Associated, Section 1.2.9.1, Annex H: MOD and Annex I)
*AND this adoption revises this current ANS
Revise current standard
Revise and Re-designate current standard
Revise, Re-designate and Consolidate current standard
Revise and Partition current standard
Reaffirm current standard
Reaffirm and Re-designate current standard
Supplement to a current standard
Withdraw current standard
4. This standard contains excerpted text from an
international standard, but is not an ISO or IEC adoption.
5.
Provide an explanation of the need for the project:
(If revision, note need for revision due to new reports,
tests, data, etc.)
Check here if this standard includes excerpted text from an ISO or IEC standards
but is not an identical or modified adoption of an international standard.
Provide a standard methodology for Integrated Safety Assessments (ISAs) to
support 10 CFR 70 licensed fuel fabrication facilities, design, construction
and operations and other facility licenses, as applicable.
6.
Identify the stakeholders (e.g., telecom, consumer, medical,
environmental, etc.) likely to be directly impacted by the
standard:
10 CFR 70 licensees, U.S. Nuclear Regulatory Commission, Department of
Energy, Owners, Designers and Constructors of Nuclear Fuel Cycle
Facilities.
7.
Scope Summary:
This standard provides an ISA method consistent with 10 CFR Part 70
regulations to identify credible accident sequences that can lead to "high" or
"intermediate" consequences as outlined in 10 CFR 70.61 performance
requirements. The ISA also specifies items relied on for safety (IROFS) to
prevent or mitigate those potential accidents and assess the likelihood that
the facilities would meet the 10 CFR 70.61 performance requirements, and
management measures a licensee will rely on to ensure IROFS are available
to perform their function. ISAs look not just at radiological and nuclear
criticality hazards, but chemical and fire risks as well.
(Provide a one paragraph description, not to exceed 650
characters including spaces. Should be written as it will
appear in the published standard (present tense verb). If
necessary, scope in standard may be longer provided
that it is editorially the same.
The emphasis of this standard is aimed at making fuel cycle safety
requirements more risk-informed, performance-based, predictable and
objective. Areas of focus will be on the development of guidance to minimize
the impact of common cause failures and human error and expansion of
requirements as defined in 10 CFR 70.4 and NUREG-1520.
8.
Consumer Product or Service:
9.
Units of Measurement Used: (check one)
Check here if standard covers Consumer or Service Product
Metric
US
X
Both
10. Accredited Standards Developer Acronym:
ANS
11. Submitter
Patricia Schroeder, ANS Standards Administrator
American Nuclear Society
555 North Kensington Avenue
La Grange Park, IL 60526
Phone: 708-579-8269 Fax: 708-579-8248
Email: pschroeder@ans.org
Q:\ANSI-Forms\PINS\Blank PINS form\ANSI-PINS-2009 Revised.doc
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The information on this page is not an official part of the ANSI PINS form. It was designed for ANS
Standards Committee purposes to provide more background information about the standard. It is not
required that this section be approved. Only the ANSI PINS form on page 1 requires approval.
Project #: ANS-57.11
1. Purpose:
Provide a standard methodology for integrated safety assessments that can be used to support 10 CFR 70 licensed fuel
fabrication facility design, construction and operations and other nuclear facilities.
2. Benefit to Users:
The standard will provide a consistent application of safety design and operating criteria to meet the requirements of 10 CFR 70
and other federal regulations.
3. Will this standard use risk-informed insights, performance-based requirements, or a graded approach:
This standard will use risk-informed insights to identify likelihood of initiating events, prevention and mitigating
controls to ensure that intermediate consequence events are unlikely and high consequence events are highly
unlikely in compliance with 10CFR70.61. A graded approach is applied to design criteria and QA controls.
4. Consensus Body:
Nuclear Facilities Standards Committee (NFSC).
5. Subcommittee under which it is assigned:
ANS-27, Nuclear Fuel Cycle.
6. Working Group Chair(s):
Bob Eble, Areva, MOX
7. Working Group Members (including organizations):
Preliminary list of candidates:
Bob Pierson, Talisman
Sven Bader, Areva MOX
Steve Schilthelm, B&W
Calvin Manning, Areva NP Richland
Gary Kaplan, RSL Safety
Jonathon De Jesus, NRC
Jennifer Wheeler, NFS
Jerry Couture, Westinghouse Fuel Fabrication
George Harper, Eagle Rock Enrichment, AREVA
Janet Schlueter- NEI
Greg Corzine, USEC
Julie Olivier, Global Laser Enrichment
Steve Cowne, URENCO National Enrichment Facility
Mosi Dayani, NNSA-Savannah River
8. Interests Represented in Development of Standard (in addition to members’ organizations, other affiliations
that may be represented important to the development of this standard):
Nuclear fuel fabrication facility owners, designers, constructors, operators, consultants, regulators and academia.
9. Coordination and Interfaces (Liaison):
NRC, NEI.
10 Related Standards or References, or Both:
1. NUREG-1513, “Integrated Safety Analysis Guidance Document (May 2001)
2. Guidelines for Hazard Evaluation Procedures” (2 nd Edition) developed by the American Institute of Chemical Engineers (AIChE)
3. NUREG-1520, “Standard Review Plan for the Review of a License Application for a Fuel Cycle
Facility (Rev. 1 May 2010)
4. NUREG/CR-6410, “Nuclear Fuel Cycle Facility Accident Analysis Handbook (March 1998)
5. FCSS-ISG-01, “Methods for Qualitative Evaluation of Likelihood”.
6. DOE–STD-1020-94, Natural Phenomena Hazards Design and Evaluation Criteria for Department of Energy Facilities”,
7. DOE-STD-1027-92, “Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order 5480.23,
Nuclear Safety Analysis Reports”
8. SECY-12-0091, COMPLETENESS AND QUALITY OF INTEGRATED SAFETY ANALYSES, R. W. Borchardt to NRC Commissioners,
June 30, 2012.
12. Project Initiation Date:
September 1, 2012
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