PINS (Single Form)



|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.

|Designation of Proposed Standard: |ANS-57.11 |

|Title of Standard: |Integrated Safety Assessments for Fuel Fabrication Facilities |

|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| |standard(s)* affected or superseded.)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 | | |

|This standard contains excerpted text from an international standard,| |Check here if this standard includes excerpted text from an ISO or IEC standards but|

|but is not an ISO or IEC adoption. | |is not an identical or modified adoption of an international standard. |

|Provide an explanation of the need for the project: |Provide a standard methodology for Integrated Safety Assessments (ISAs) to support 10 CFR 70 |

|(If revision, note need for revision due to new reports, tests, data,|licensed fuel fabrication facilities, design, construction and operations and other facility |

|etc.) |licenses, as applicable. |

|Identify the stakeholders (e.g., telecom, consumer, medical, |10 CFR 70 licensees, U.S. Nuclear Regulatory Commission, Department of Energy, Owners, |

|environmental, etc.) likely to be directly impacted by the standard: |Designers and Constructors of Nuclear Fuel Cycle Facilities. |

|Scope Summary: |This standard provides an ISA method consistent with 10 CFR Part 70 regulations to identify |

|(Provide a one paragraph description, not to exceed 650 characters |credible accident sequences that can lead to "high" or "intermediate" consequences as outlined|

|including spaces. Should be written as it will appear in the |in 10 CFR 70.61 performance requirements. The ISA also specifies items relied on for safety |

|published standard (present tense verb). If necessary, scope in |(IROFS) to prevent or mitigate those potential accidents and assess the likelihood that the |

|standard may be longer provided that it is editorially the same. |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. |

| |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. |

|Consumer Product or Service: | |Check here if standard covers Consumer or Service Product |

|Units of Measurement Used: (check one) | |

|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@ |

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” (2nd 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.

5. Project Initiation Date:

September 1, 2012

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