98-24458. Use of PRA in Plant-Specific Reactor Regulatory Activities: Final Regulatory Guide and Standard Review Plan Section; Availability  

  • [Federal Register Volume 63, Number 176 (Friday, September 11, 1998)]
    [Notices]
    [Pages 48771-48772]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-24458]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    
    Use of PRA in Plant-Specific Reactor Regulatory Activities: Final 
    Regulatory Guide and Standard Review Plan Section; Availability
    
        The Nuclear Regulatory Commission has issued three new guides in 
    its Regulatory Guide Series, along with two conforming sections of the 
    Standard Review Plan. The guides are Regulatory Guide 1.175, ``An 
    Approach for Plant-Specific, Risk-Informed, Decisionmaking: Inservice 
    Testing''; Regulatory Guide 1.176, ``An Approach for Plant-Specific, 
    Risk-Informed Decisionmaking: Graded Quality Assurance''; and 
    Regulatory Guide 1.177, ``An Approach for Plant-Specific, Risk-Informed 
    Decisionmaking: Technical Specifications.'' The revised sections of 
    NUREG-0800, ``Standard Review Plan,'' are Chapter 3.9.7, ``Standard 
    Review Plan for Risk-Informed Decisionmaking: Inservice Testing,'' and 
    Chapter 16.1, ``Standard Review Plan for Risk-Informed Decisionmaking: 
    Technical Specifications.'' Together with Regulatory Guide 1.174, ``An 
    Approach for Using Probabilistic Risk Assessment in Risk-Informed 
    Decisions on Plant-Specific Changes to the Licensing Basis,'' and the 
    accompanying Chapter 19 of the Standard Review Plan, ``Use of 
    Probabilistic Risk Assessment in Plant-Specific, Risk-Informed 
    Decisionmaking: General Guidance,'' these documents provide the basic 
    framework for an acceptable approach for use by power reactor licensees 
    in preparing proposals for plant-specific changes to their licensing 
    bases using risk information as a partial basis.
        Comments and suggestions in connection with items for inclusion in 
    guides currently being developed or improvements in all published 
    guides are encouraged at any time. Written comments may be submitted to 
    the Rules and Directives Branch, Division of Administrative Services, 
    Office of Administration, U.S. Nuclear Regulatory Commission, 
    Washington, DC 20555.
        Single copies of regulatory guides, both active and draft, may be 
    obtained free of charge by writing the Reproduction and Distribution 
    Services Section, OCIO, USNRC, Washington, DC
    
    [[Page 48772]]
    
    20555-0001; or by fax to (301) 415-2289; or by email to [email protected] 
    The SRP sections of NUREG-0800 may be purchased from the U.S. 
    Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328 
    (telephone (202) 512-2249). Active guides may be purchased from the 
    National Technical Information Service on a standing order basis. 
    Details on this service may be obtained by writing NTIS, 5285 Port 
    Royal Road, Springfield, VA 22161. NTIS also sells single copies of 
    NUREG-series documents. Copies of regulatory guides and the Standard 
    Review Plan sections are available for inspection or copying for a fee 
    from the NRC Public Document Room at 2120 L Street NW., Washington, DC; 
    the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; 
    telephone (202) 634-3273; fax (202) 634-3343. Regulatory guides are not 
    copyrighted, and Commission approval is not required to reproduce them.
    
    Background
    
        On August 16, 1995, the Commission published in the Federal 
    Register a final policy statement on the Use of Probabilistic Risk 
    Assessment Methods in Nuclear Regulatory Activities (60 FR 42622). The 
    policy statement included the following policy regarding expanded NRC 
    use of PRA:
         The use of PRA technology should be increased in all 
    regulatory matters to the extent supported by the state of the art in 
    PRA methods and data and in a manner that complements the NRC's 
    deterministic approach and supports the NRC's traditional defense-in-
    depth philosophy.
         PRA and associated analyses (e.g., sensitivity studies, 
    uncertainty analyses, and importance measures) should be used in 
    regulatory matters, where practical within the bounds of the state of 
    the art, to reduce unnecessary conservatism associated with current 
    regulatory requirements, regulatory guides, license commitments, and 
    staff practices. Where appropriate, PRA should be used to support 
    proposals for additional regulatory requirements in accordance with 10 
    CFR 50.109 (Backfit Rule). Appropriate procedures for including PRA in 
    the process for changing regulatory requirements should be developed 
    and followed. It is, of course, understood that the intent of this 
    policy is that existing rules and regulations shall be complied with 
    unless these rules and regulations are revised.
         PRA evaluations in support of regulatory decisions should 
    be as realistic as practicable and appropriate supporting data should 
    be publicly available for review.
         The Commission's safety goals for nuclear power plants and 
    subsidiary numerical objectives are to be used with appropriate 
    consideration of uncertainties in making regulatory judgments on the 
    need for proposing and backfitting new generic requirements on nuclear 
    power plant licensees.
        It was the Commission's intent that implementation of this policy 
    statement would improve the regulatory process in three areas:
        1. Enhancement of safety decisionmaking by the use of PRA insights,
        2. More efficient use of agency resources, and
        3. Reduction in unnecessary burdens on licensees.
        In parallel with the development of Commission policy on uses of 
    risk assessment methods, the NRC developed an agency-wide 
    implementation plan for application of probabilistic risk assessment 
    insights within the regulatory process (SECY-95-079). This 
    implementation plan included tasks to develop the series of regulatory 
    guides that is the subject of this notice. In June 1997, the regulatory 
    guides and SRP sections were issued in draft for public comment. A 
    discussion of the comments received and their disposition, as well as 
    SECY-95-079, may be obtained from the NRC Public Document Room at 2120 
    L Street NW., Washington, DC; the PDR's mailing address is Mail Stop 
    LL-6, Washington, DC 20555; telephone (202) 634-3273; fax (202) 634-
    3343. (5 U.S.C. 552(a))
    
        Dated at Rockville, Maryland, this 28th day of August 1998.
    
        For the Nuclear Regulatory Commission.
    Margaret V. Federline,
    Deputy Director, Office of Nuclear Regulatory Research.
    [FR Doc. 98-24458 Filed 9-10-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
09/11/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
98-24458
Pages:
48771-48772 (2 pages)
PDF File:
98-24458.pdf