99-8027. FirstEnergy Nuclear Operating Company (Perry Nuclear Power Plant, Unit 1); Exemption  

  • [Federal Register Volume 64, Number 62 (Thursday, April 1, 1999)]
    [Notices]
    [Page 15831]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 99-8027]
    
    
    
    [[Page 15831]]
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 50-440]
    
    
    FirstEnergy Nuclear Operating Company (Perry Nuclear Power Plant, 
    Unit 1); Exemption
    
    I
    
        The FirstEnergy Nuclear Operating Company (FENOC, the licensee) is 
    the holder of Facility Operating License No. NPF-58, which authorizes 
    operation of the Perry Nuclear Power Plant, Unit 1. 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 Perry Nuclear Power Plant is a boiling-water reactor facility 
    located at the licensee's site in Lake County, Ohio.
    
    II
    
        By letter dated December 3, 1998, FENOC submitted an exemption 
    request to the control room dose acceptance criteria of 10 CFR part 50, 
    Appendix A, General Design Criterion (GDC) 19. The exemption request 
    would permit use of a total effective dose equivalent (TEDE) acceptance 
    criterion of 5-rem in place of the ``5 rem whole body, or its 
    equivalent to any part of the body'' dose acceptance criterion that is 
    currently specified in GDC 19.
        The NRC has established control room dose acceptance criteria in 10 
    CFR part 50, Appendix A, GDC 19, for all light-water power reactors. 
    GDC 19 requires, in part, that ``Adequate radiation protection shall be 
    provided to permit access and occupancy of the control room under 
    accident conditions without personnel receiving radiation exposures in 
    excess of 5 rem whole body, or its equivalent to any part of the body, 
    for the duration of the accident.'' As described in SECY-96-242, ``Use 
    of the NUREG-1465 Source Term at Operating Reactors,'' the staff 
    informed the Commission of its approach to allow the use of the revised 
    accident source term described in NUREG-1465, ``Accident Source Terms 
    for Light-Water Nuclear Power Plants,'' at operating plants. In the 
    SECY paper, the staff described its plans to review plant applications 
    implementing this source term and indicated that the TEDE methodology 
    would be incorporated in these reviews. The Commission approved these 
    plans and directed the staff to commence rulemaking and requested the 
    use of the TEDE methodology in the implementation of the revised 
    accident source term. The TEDE guidelines, which are needed to support 
    revised accident source term applications, are not currently provided 
    in regulations governing operating reactors.
        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 the licensee's 
    rationale to support the exemption request and concluded that the use 
    of the TEDE acceptance criteria for the control room would 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 control room dose 
    acceptance criteria of GDC 19 is not necessary to achieve the 
    underlying purpose of the rule because, as stated in the staff safety 
    evaluation, dated March 26, 1999, the staff considers the TEDE 
    methodology as an acceptable means of meeting the current regulatory 
    requirement. Therefore, the staff has concluded that an exemption to 
    the requirements of 10 CFR part 50, Appendix A, GDC 19, should be 
    granted to allow FENOC to adopt the TEDE methodology for the purpose of 
    implementing the revised accident source term of NUREG-1465.
    
    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 part 50, Appendix A, GDC 19 to allow FENOC to 
    adopt the TEDE methodology for the purpose of implementing the revised 
    accident source term of NUREG-1465.
        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 (64 FR 4906).
        This exemption is effective upon issuance.
    
        Dated at Rockville, Maryland, this 26th day of March 1999.
    
        For the Nuclear Regulatory Commission.
    Samuel J. Collins,
    Director, Office of Nuclear Reactor Regulation.
    [FR Doc. 99-8027 Filed 3-31-99; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
04/01/1999
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
99-8027
Pages:
15831-15831 (1 pages)
Docket Numbers:
Docket No. 50-440
PDF File:
99-8027.pdf