98-32112. Wisconsin Public Service Co. (Kewaunee Nuclear Power Plant); Exemption  

  • [Federal Register Volume 63, Number 231 (Wednesday, December 2, 1998)]
    [Notices]
    [Page 66587]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-32112]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 50-305]
    
    
    Wisconsin Public Service Co. (Kewaunee Nuclear Power Plant); 
    Exemption
    
    I
    
        The Wisconsin Public Service Company (WPSC, the licensee) is the 
    holder of Facility Operating License No. DPR-43, which authorizes 
    operation of the Kewaunee Nuclear Power Plant. The operating license 
    states, among other things, that the licensee is subject to all rules, 
    regulations, and orders of the U.S. Nuclear Regulatory Commission (the 
    Commission) now or hereafter in effect.
        The Kewaunee Nuclear Power Plant is a pressurized-water reactor 
    facility located at the licensee's site in Kewaunee County, Wisconsin.
    
    II
    
        By letter dated August 6, 1998, WPSC submitted an exemption request 
    to certain requirements in Title 10 of the Code of Federal Regulations, 
    Part 50, Appendix G, ``Fracture Toughness Requirements,'' which invokes 
    ASME, Section XI, Appendix G pressure-temperature limits for reactor 
    pressure vessels (RPVs).
    
    III
    
        The NRC has established requirements in 10 CFR part 50 to protect 
    the integrity of the reactor coolant system pressure boundary. 10 CFR 
    50.60(a) and 10 CFR part 50, appendix G.IV.2. require (via reference to 
    10 CFR 50.55a) that pressure-temperature (P-T) limits be established 
    for RPVs during normal operation and vessel hydrostatic testing based 
    on the methodology provided in the 1989 Edition of ASME Section XI, 
    Appendix G. Pursuant to 10 CFR 50.60(b), alternatives to the 
    requirements of 10 CFR part 50, appendix G.IV.2 may be used when an 
    exemption is granted by the Commission. The underlying purpose of 10 
    CFR 50.60(a) and 10 CFR Part 50, Appendix G, is to establish fracture 
    toughness requirements for the reactor coolant system pressure boundary 
    to provide adequate margins of safety during normal operation, 
    including anticipated operational occurrences and system hydrostatic 
    tests, to which the pressure boundary may be subjected over its service 
    lifetime.
        Pursuant to 10 CFR 50.12, the Commission may, upon application by 
    any interested person or upon its own initiative, grant exemptions from 
    the requirements of 10 CFR part 50 when (1) the exemptions are 
    authorized by law, will not present an undue risk to public health or 
    safety, and are consistent with the common defense and security, and 
    (2) when special circumstances are present. Special circumstances are 
    present whenever, according to 10 CFR 50.12(a)(2)(ii), ``Application of 
    the regulation in the particular circumstances would not serve the 
    underlying purpose of the rule or is not necessary to achieve the 
    underlying purpose of the rule.''
        The NRC staff examined WPSC's rationale to support the exemption 
    request and concluded that the use of Code Case N-588 would also meet 
    the underlying intent of the regulations. The licensee's request for 
    the exemption under the special circumstances of 10 CFR 50.12(a)(2)(ii) 
    was found to be appropriate. Application of the regulation is not 
    necessary to achieve the underlying purpose of the rule because, as 
    stated in the staff Safety Evaluation, dated November 25, 1998, 
    adequate margins of safety on the structural integrity of the reactor 
    coolant pressure boundary are maintained with the application of Code 
    Case N-588. Therefore, the NRC staff has concluded that an exemption to 
    the requirements of 10 CFR 50.60 and 10 CFR part 50, appendix G.IV.2 
    should be granted to allow WPSC to apply the methodology in ASME Code 
    Case N-588 for the purpose of developing P-T limits for the KNPP RPV.
    
    IV
    
        Accordingly, the Commission has determined that, pursuant to 10 CFR 
    50.12(a), an exemption is authorized by law, will not endanger life or 
    property or common defense and security, and is otherwise in the public 
    interest. Therefore, the Commission hereby grants an exemption from the 
    requirements of 10 CFR 50.60(a) and 10 CFR part 50, appendix G.IV.2 to 
    allow WPSC to apply the methods in ASME Code Case N-588 for the 
    evaluation of KNPP pressure-temperature limits.
        Pursuant to 10 CFR 51.32, the Commission has determined that the 
    granting of this exemption will not have a significant effect on the 
    quality of the human environment (63 FR 65265).
        This exemption is effective upon issuance.
    
        Dated at Rockville, Maryland, this 25th day of November 1998.
    
        For the Nuclear Regulatory Commission.
    Frank J. Miraglia,
    Acting Director, Office of Nuclear Reactor Regulation.
    [FR Doc. 98-32112 Filed 12-1-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
12/02/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
98-32112
Pages:
66587-66587 (1 pages)
Docket Numbers:
Docket No. 50-305
PDF File:
98-32112.pdf