97-20452. In the Matter of Duke Power Company, et al. (Catawba Nuclear Station, Units 1 and 2)  

  • [Federal Register Volume 62, Number 149 (Monday, August 4, 1997)]
    [Notices]
    [Page 41981]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 97-20452]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-413 and 50-414]
    
    
    In the Matter of Duke Power Company, et al. (Catawba Nuclear 
    Station, Units 1 and 2)
    
    Exemption
    
    I
    
        The Duke Power Company, et al. (the licensee) is the holder of 
    Facility Operating License Nos. NPF-35 and NPF-52, for the Catawba 
    Nuclear Station, Units 1 and 2. The licenses provide, among other 
    things, that the licensee is subject to all rules, regulations, and 
    orders of the Commission now or hereafter in effect.
        These facilities consist of two pressurized water reactors located 
    at the licensee's site in York County, South Carolina.
    
    II
    
        Title 10 of the Code of Federal Regulations (10 CFR) at subsection 
    (a) of 10 CFR 70.24, ``Criticality Accident Requirements,'' requires 
    that each licensee authorized to possess special nuclear material shall 
    maintain in each area where such material is handled, used, or stored, 
    a criticality accident monitoring system ``using gamma- or neutron-
    sensitive radiation detectors which will energize clearly audible alarm 
    signals if accidental criticality occurs.'' Subsections (a)(1) and 
    (a)(2) of 10 CFR 70.24 specify the detection, sensitivity, and coverage 
    capabilities of the monitors required by 10 CFR 70.24(a). Subsection 
    (a)(3) of 10 CFR 70.24 requires that the licensee shall maintain 
    emergency procedures for each area in which this licensed special 
    nuclear material is handled, used, or stored and provides (1) that the 
    procedures ensure that all personnel withdraw to an area of safety upon 
    the sounding of a criticality monitor alarm, (2) that the procedures 
    must include drills to familiarize personnel with the evacuation plan, 
    and (3) that the procedures designate responsible individuals for 
    determining the cause of the alarm and placement of radiation survey 
    instruments in accessible locations for use in such an emergency. 
    Subsection (b)(1) requires licensees to have a means to quickly 
    identify personnel who have received a dose of 10 rads or more. 
    Subsection (b)(2) requires licensees to maintain personnel 
    decontamination facilities, to maintain arrangements for a physician 
    and other medical personnel qualified to handle radiation emergencies, 
    and to maintain arrangements for the transportation of contaminated 
    individuals to treatment facilities outside the site boundary. 
    Subsection (c) exempts Part 50 licensees (such as Catawba) from the 
    requirements of paragraph (b). Subsection (d) states that any licensee 
    who believes that there is good cause why he should be granted an 
    exemption from all or part of 10 CFR 70.24 may apply to the Commission 
    for such an exemption and shall specify the reasons for the relief 
    requested.
        By letter dated February 4, 1997, as supplemented March 19, 1997, 
    Duke Power Company requested an exemption for its two nuclear plants 
    from the requirements of 10 CFR 70.24. The staff has reviewed the 
    submittal in regard to Catawba, and documented its detailed review in a 
    Safety Evaluation. The staff found that Catawba's existing procedures 
    and design features make an inadvertent criticality in special nuclear 
    materials handling or storage at Catawba unlikely. The licensee has 
    thus met the intent of 10 CFR 70.24(a) (1), (2), and (3) by the low 
    probability of an inadvertent criticality in areas where fresh fuel 
    could be present, by the licensee's adherence to General Design 
    Criterion 63 regarding radiation monitoring, and by provisions for 
    personnel training and evacuation.
    
    III
    
        Section 70.14 of 10 CFR, ``Specific exemptions,'' states that
    
        The Commission may, upon application by any interested person or 
    upon its own initiative, grant such exemptions from the requirements 
    of the regulations in this part as it determines are authorized by 
    law and will not endanger life or property or the common defense and 
    security and are otherwise in the public interest.
    
        Section 70.24(d) of 10 CFR states that
    
        Any licensee who believes that good cause exists why he should 
    be granted an exemption in whole or in part from the requirements of 
    this section may apply to the Commission for such exemption.
    
        Accordingly, the Commission has determined that good cause is 
    present as defined in 10 CFR 70.24(d). The Commission has further 
    determined that, pursuant to 10 CFR 70.14, the exemption is authorized 
    by law and will not endanger life or property or the common defense and 
    security and is otherwise in the public interest. Therefore, the 
    Commission hereby grants Duke Power Company an exemption from the 
    requirements of 10 CFR 70.24(a) (1), (2), and (3) for Catawba, Units 1 
    and 2, on the bases as stated in Section II above.
        Pursuant to 10 CFR 51.32, the Commission has determined that 
    granting of this exemption will have no significant effect on the 
    quality of the human environment (62 FR 40553).
    
        This exemption is effective upon issuance.
    
        Dated at Rockville, Maryland, this 29th day of July 1997.
    
        For the Nuclear Regulatory Commission.
    Samuel J. Collins,
    Director, Office of Nuclear Reactor Regulation.
    
    [FR Doc. 97-20452 Filed 8-1-97; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
08/04/1997
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
97-20452
Pages:
41981-41981 (1 pages)
Docket Numbers:
Docket Nos. 50-413 and 50-414
PDF File:
97-20452.pdf