94-3849. Wisconsin Public Service Corp., et. al.; Kewaunee Nuclear Power Plant  

  • [Federal Register Volume 59, Number 35 (Tuesday, February 22, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-3849]
    
    
    [[Page Unknown]]
    
    [Federal Register: February 22, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket No. 50-305]
    
     
    
    Wisconsin Public Service Corp., et. al.; Kewaunee Nuclear Power 
    Plant
    
    Exemption
    
    I
    
        The Wisconsin Public Service Corporation, Wisconsin Power and Light 
    Company, and Madison Gas and Electric Company (the licensee), are the 
    holders of Facility Operating License No. DPR-43 which authorizes 
    operation of the Kewaunee Nuclear Power Plant (KNPP). The licensee 
    provides, among other things, that it is subject to all rules, 
    regulations, and orders of the Nuclear Regulatory Commission (the 
    Commission) now and hereafter in effect.
        The facility consists of a pressurized water reactor located at the 
    licensee's site in Kewaunee County, Wisconsin.
    
    II
    
        In a letter dated November 16, 1993, the licensee applied for a 
    partial exemption from the Commission's regulations. The subject 
    exemption is from the requirements of 10 CFR part 50, Appendix J, 
    Section III.D.1.(a). This Section requires, in part, that ``. . . a set 
    of three Type A tests shall be performed at approximately equal 
    intervals during each 10-year service period. The third test of each 
    set shall be conducted when the plant is shutdown for the 10-year plant 
    inservice inspection.'' The licensee proposes to perform the three Type 
    A tests at approximately equal intervals within each 10-year period, 
    with the third test of each set conducted as close as practical to the 
    end of the 10-year period. However, there would be no required 
    connection between the Appendix J 10-year interval and the inservice 
    inspection 10-year interval. Kewaunee's 10-year Appendix J interval 
    ends in 1994 and the third Type A test is scheduled for the 1994 
    refueling outage.
        The 10-year plant inservice inspection (ISI) is the series of 
    inspections performed every 10 years in accordance with Section XI of 
    the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 
    CFR 50.55a. The licensee performs the ISI volumetric, surface and 
    visual examinations of components and system pressure tests in 
    accordance with 10 CFR 50.55a(g)(4) throughout the 10-year inspection 
    interval. The major portion of this effort is presently being performed 
    every 12 months during the refueling outages. Kewaunee's second 10-year 
    ISI interval ends in June 1994. Kewaunee is scheduled to complete the 
    second 10-year ISI program during the spring of 1995, as allowed by 
    section XI IWA 2400(c). The reactor vessel inspection during the 1995 
    refueling outage will complete the second 10-year ISI program. Kewaunee 
    is also scheduled to begin the third 10-year program during the 1995 
    refueling outage. As a result, the completion of the second 10-year ISI 
    program will occur in 1995 and the 10-year Appendix J interval will end 
    in the spring of 1994.
        There is no benefit to be gained by the coupling requirement cited 
    above in that elements of the ISI program are conducted throughout each 
    10-year cycle rather than during a refueling outage at the end of the 
    10-year cycle. Consequently, the subject coupling requirement offers no 
    benefit either to safety or to the economical operation of the 
    facility.
        Moreover, each of these two surveillance tests (i.e., the Type A 
    tests and the 10-year ISI program) is independent of the other and 
    provides assurances of different plant characteristics. The Type A test 
    assures the required leak-tightness to demonstrate compliance with the 
    guidelines of 10 CFR part 100. The 10-year ISI program provides 
    assurance of the integrity of the structures, systems, and components 
    in compliance with 10 CFR 50.55a. There is no safety-related concern 
    necessitating their coupling in the same refueling outage. Accordingly, 
    the staff finds that application of the regulation is not necessary to 
    achieve the underlying purpose of the rule.
        On this basis, the staff finds that the licensee has demonstrated 
    that there are special circumstances present as required by 10 CFR 
    50.12(a)(2). Further, the staff also finds that the uncoupling of the 
    Type A tests from the 10-year ISI program will not present an undue 
    risk to the public health and safety.
    
    III
    
        Accordingly, the Commission has determined that, pursuant to 10 CFR 
    50.12, this exemption as described in Section II is authorized by law 
    and will not endanger life or property or the common defense and 
    security and is otherwise in the public interest and hereby grants the 
    exemption with respect to the requirements of 10 CFR part 50, Appendix 
    J, Paragraph III.D.1.(a). Pursuant to 10 CFR 51.32, the Commission has 
    determined that the granting of this exemption will have no significant 
    impact on the environment (59 FR 1037).
    
        Dated at Rockville, Maryland, this 14th day of February 1994.
    
        For the Nuclear Regulatory Commission.
    Jack W. Roe,
    Director, Division of Reactor Projects--III/IV/V, Office of Nuclear 
    Reactor Regulation.
    [FR Doc. 94-3849 Filed 2-18-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
02/22/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-3849
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: February 22, 1994, Docket No. 50-305