97-28619. Florida Power Corporation; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 62, Number 209 (Wednesday, October 29, 1997)]
    [Notices]
    [Pages 56207-56208]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 97-28619]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 50-302]
    
    
    Florida Power Corporation; Environmental Assessment and Finding 
    of No Significant Impact
    
        The U.S. Nuclear Regulatory Commission (the Commission or NRC) is 
    considering issuance of an exemption from certain requirements of its 
    regulations to Florida Power Corporation (the licensee), holder of 
    Facility Operating License No. DPR-72 for operation of the Crystal 
    River Unit 3 Nuclear Generating Plant (CR3) located in Citrus County, 
    Florida.
    
    Environmental Assessment
    
    Identification of Proposed Action
    
        The proposed action is in accordance with the licensee's 
    application dated June 21, 1996 as supplemented November 22, 1996, for 
    exemption from certain requirements of Section III, Paragraph G, ``Fire 
    protection of safe shutdown capability,'' of Appendix R, ``Fire 
    Protection Program for Nuclear Power Facilities Operating Prior to 
    January 1, 1979,'' to Title 10 of the Code of Federal Regulations part 
    50 (10 CFR part 50). Specifically, the licensee requests an exemption 
    from the requirements of Section III.G.2.c of Appendix R, to allow the 
    use of the existing fire barrier material, Thermo-Lag, with less than 
    1-hour fire rating, for protecting one train of certain redundant safe 
    shutdown cables located in the auxiliary building elevations 95 and 
    119, and intermediate building elevation 119.
        This environmental assessment does not address the licensee's 
    request relating to the requirements for battery powered lighting in 
    areas for the operation of safe shutdown equipment.
    
    The Need for the Proposed Action
    
        10 CFR part 50, Appendix A, ``General Design Criteria for Nuclear 
    Power Plants,'' Criterion 3 ``Fire Protection,'' specifies that 
    ``Structures, systems, and components important to safety shall be 
    designed and located to minimize, consistent with other safety 
    requirements, the probability and effect of fires and explosions.'' 10 
    CFR part 50, Appendix R, sets forth the fire protection features 
    required to satisfy the General Design Criterion 3 of the Commission's 
    regulations. Pursuant to 10 CFR part 50, Appendix R, Section III, 
    Paragraph G, design features shall be established that are capable of 
    limiting fire damage so that one train of systems necessary to achieve 
    and maintain hot shutdown conditions is free of fire damage. 
    Specifically, 10 CFR part 50, Appendix R, Paragraph III. G.2.c, in 
    part, requires (if Paragraphs III.G.2.a or b are not applicable) 
    enclosure of cable and equipment and associated non-safety circuits of 
    one redundant train in a fire barrier having a 1-hour rating; in 
    addition, fire detectors and an automatic
    
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    fire suppression system shall be installed in the fire area.
        The current CR3 design includes Thermo-Lag fire barriers which do 
    not provide the level of fire endurance required by NRC regulations. As 
    part of its program for resolving Thermo-Lag issues, the licensee has 
    determined that the Thermo-Lag material used as a fire barrier for the 
    protection of certain safe shutdown cables located in certain 
    elevations of the auxiliary and intermediate buildings does not qualify 
    as 1-hour fire rated barriers. In lieu of upgrading the existing 
    Thermo-Lag fire barriers to satisfy the 1-hour fire rating requirement, 
    the licensee proposed to implement an enhanced automatic fire 
    suppression system coverage for these specific fire zones. The licensee 
    indicates that its proposed enhanced automatic fire suppression system 
    coverage coupled with the existing Thermo-Lag barriers and other 
    defense-in-depth features will ensure that one train of equipment 
    necessary to achieve hot shutdown remains free of fire damage. An 
    exemption from 10 CFR part 50, Appendix R, Section III, Paragraph G. 2. 
    c. is required to allow the use of existing Thermo-Lag material that 
    has less than a 1-hour fire rating, for the specific cables and 
    equipment located in certain elevations of the auxiliary and 
    intermediate buildings. By letter dated June 21, as supplemented 
    November 22, 1996, the licensee submitted the exemption request.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has completed its evaluation of the licensee's 
    application.
        The exemption request is for the following fire zones: auxiliary 
    building elevations 95 and 119 (fire area AB-95-3B and G, AB-119-6A) 
    and the intermediate building elevation 119 (fire area IB-119-201A). A 
    fire in the 95 or 119 elevations of the auxiliary building could cause 
    the loss of the redundant divisions of the makeup system, heating 
    ventilation and air conditioning (HVAC), instrumentation, battery 
    charging or essential power supplies. A fire on the 119 elevation of 
    the intermediate building could cause the loss of redundant divisions 
    of instrumentation needed to achieve and maintain safe shutdown 
    following a fire.
        These four fire zones contain fire detectors and an automatic fire 
    suppression system. To enhance the sprinkler coverage in these zones, 
    the licensee proposes to upgrade the existing sprinkler protection in 
    the vicinity of the Thermo-Lag fire barriers. The additional sprinkler 
    protection, coupled with the existing automatic detection, manual fire 
    suppression capability and the administrative controls provided in 
    these fire zones, would provide reasonable assurance that an exposure 
    fire from in-situ or transient combustible materials in the vicinity of 
    the existing Thermo-Lag fire barriers will not challenge the barriers, 
    such that damage to redundant divisions of systems and instrumentation 
    needed to achieve and maintain safe shutdown following a fire will not 
    occur. Based on data obtained from industry sponsored fire test 
    programs, the staff estimates that the existing Thermo-Lag barriers 
    would provide a minimum of 20 minutes of fire resistance. The licensee 
    is also committed to maintain the Thermo-Lag fire barriers that are the 
    subject of this request in place. Automatic wet pipe sprinkler 
    protection that is designed, installed and maintained in accordance 
    with NFPA 13, ``Installation of Sprinkler Systems,'' have historically 
    demonstrated a high reliability in controlling fires during the 
    incipient stage, thereby limiting fire damage and propagation until 
    extinguishment can be achieved through manual actions. Further, the 
    licensee has administrative controls that are designed to control the 
    type, amount, use and location of combustibles. Proper control of 
    combustibles minimizes the possibility of starting, spreading, or 
    contributing to a fire.
    
    4.0  Conclusion
    
        On the basis of this evaluation, the NRC staff concluded that 
    protection provided for the fire zones, auxiliary building elevations 
    95 and 119 (fire area AB-95-3B and G, AB-119-6A) and the intermediate 
    building elevation 119 (fire area IB-119-201A) would provide reasonable 
    assurance that a level of safety equivalent to that specified by the 
    regulation would be met, and, therefore, is acceptable.
        The change will not increase the probability or consequences of 
    accidents, no changes are being made in the types of any effluents that 
    may be released offsite, and there is no significant increase in the 
    allowable individual or cumulative occupational radiation exposure. 
    Accordingly, the Commission concludes that there are no significant 
    radiological environmental impacts associated with the proposed action.
        With regard to potential nonradiological impacts, the proposed 
    action does involve features located entirely within the restricted 
    area as defined in 10 CFR part 20. It does not affect nonradiological 
    plant effluents and has no other environmental impact. Accordingly, the 
    Commission concludes that there are no significant nonradiological 
    environmental impacts associated with the proposed action.
    
    Alternative to the Proposed Action
    
        As an alternative to the proposed action, the staff considered 
    denial of the proposed action. Denial of the application would result 
    in no change in current environmental impacts. The environmental 
    impacts of the proposed action and the alternative action are similar.
    
    Alternative Use of Resources
    
        This action did not involve the use of any resources not previously 
    considered in the Final Environmental Statements related to operation 
    of CR3, dated May 1973.
    
    Agencies and Persons Consulted
    
        In accordance with its stated policy, on October , 1997 the staff 
    consulted with the Florida State Official, Mr. Bill Passetti of the 
    Florida Department of Health and Rehabilitative Services, regarding the 
    environmental impact of the proposed action. The State official had no 
    comments.
    
    Finding of No Significant Impact
    
        The Commission has determined not to prepare an environmental 
    impact statement for the proposed exemption. Based upon the foregoing 
    environmental assessment, the Commission concludes that the proposed 
    action will not have a significant effect on the quality of the human 
    environment.
        For further details with respect to this action, see the request 
    for exemption dated June 21, as supplemented November 22, 1996, which 
    are available for public inspection at the Commission's Public Document 
    Room, 2120 L Street, NW., Washington, DC and at the local public 
    document room located at Coastal Region Library, 8619 W. Crystal 
    Street, Crystal River, Florida.
    
        Dated at Rockville, Maryland, this 22nd day of October 1997.
    
        For the Nuclear Regulatory Commission.
    Frederick J. Hebdon,
    Director, Project Directorate II-3, Division of Reactor Projects--I/II, 
    Office of Nuclear Reactor Regulation.
    [FR Doc. 97-28619 Filed 10-28-97; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
10/29/1997
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
97-28619
Pages:
56207-56208 (2 pages)
Docket Numbers:
Docket No. 50-302
PDF File:
97-28619.pdf