98-30560. Duke Energy Corporation, Oconee Nuclear Station, Units 1, 2, and 3; Environmental Assessment and Finding of No Significant Impact  

  • [Federal Register Volume 63, Number 220 (Monday, November 16, 1998)]
    [Notices]
    [Pages 63754-63755]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-30560]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-269, 50-270, and 50-287]
    
    
    Duke Energy Corporation, Oconee Nuclear Station, Units 1, 2, and 
    3; Environmental Assessment and Finding of No Significant Impact
    
        The U.S. Nuclear Regulatory Commission (the Commission) is 
    considering issuance of an exemption from the requirements of Title 10 
    of the Code of Federal Regulations (10 CFR) Section 50.46(b) to the 
    Duke Energy Corporation (the licensee) for operation of the Oconee 
    Nuclear Station, Units 1, 2, and 3, located in Oconee County, South 
    Carolina.
    
    Environmental Assessment
    
    Identification of Proposed Action
    
        The proposed action would exempt the licensee from the provisions 
    in 10 CFR 50.46(b), with respect to the emergency core cooling 
    performance requirements during the performance of the proposed Keowee 
    Emergency Power and Engineered Safeguards Functional (KEP/ESF) Test on 
    Unit 3.
        The emergency core cooling system (ECCS) is designed to assure that 
    the consequences of the spectrum of loss of coolant accidents (LOCAs), 
    coincident with a loss of offsite power (LOOP), are within the 
    performance criteria specified in 10 CFR 50.46(b). As explained in the 
    licensee's letter dated October 21, 1998, the planned test on Unit 3 
    could challenge these performance criteria in the extremely unlikely 
    event that a LOCA and LOOP occurred coincident with the test. The 
    licensee has chosen to address this issue with an exemption request. 
    Therefore, pursuant to 10 CFR 50.12, the licensee applied for an 
    exemption from 10 CFR 50.46.
    
    The Need for the Proposed Action
    
        The proposed action is required to exempt the licensee from the 
    requirement to maintain an ECCS that is designed to conform to the 
    criteria in 10 CFR 50.46(b) during the 10-second time interval when the 
    test is actually being performed during the 24-hour test period. The 
    action is needed to allow the test to be performed.
        As stated in its September 17, 1998, letter, the licensee has 
    planned a modification that would add voltage and frequency protection 
    for Oconee loads when supplied from a Keowee hydro unit. The protection 
    would separate Oconee loads from a Keowee unit if that unit's voltage 
    or frequency becomes greater than 110 percent or less than 90 percent 
    of rated value at any time after loading. The planned design would 
    delay the loading of Oconee loads on the underground power path until 
    the Keowee unit reaches greater than 90 percent voltage and frequency. 
    The existing design allows early loading of the underground path Keowee 
    unit at approximately 60 percent voltage. As a result of considering 
    the frequency overshoot the Keowee units experience during an emergency 
    start, and to resolve questions that arose concerning whether the 
    preferred loading design for the emergency power system is 60 percent 
    loading or 90 percent loading,
    
    [[Page 63755]]
    
    the Keowee Emergency Power and Engineered Safeguards Functional Test is 
    planned.
    
    Environmental Impacts of the Proposed Action
    
        The Commission has completed its evaluation of the proposed action 
    and concludes that exemption from the requirements of 10 CFR 50.46(b) 
    to allow the licensee to perform the Keowee Emergency Power and 
    Engineered Safeguards Functional Test to increase the reliability of 
    the emergency electrical power system is appropriate.
        The planned test will be performed with Unit 3 at cold shutdown and 
    its engineered safeguards (ES) loads on the Standby Bus. The other two 
    Oconee units will be operating and should not be affected by the test. 
    However, in the unlikely event that a real LOCA/LOOP were to occur on 
    either of the operating units during the simulated LOCA/LOOP on Unit 3 
    (probability, according to the licensee, of approximately 2E-9), the 
    Oconee emergency power system (EPS) for Oconee Units 1, 2, and 3 could 
    be in a condition outside its design bases. The EPS may not be capable 
    of handling the electrical loading of two instantaneous LOCA/LOOP 
    events without some safety-related equipment being adversely affected. 
    However, the EPS would be able to handle the electrical loading if the 
    two events are offset in time by approximately 10 seconds to allow the 
    first unit's load to reach a steady-state condition prior to starting 
    of the second unit's emergency loads. Therefore, this 10-second window 
    of vulnerability causes an infinitesimally small, but non-zero, 
    increase in the probability of a malfunction of equipment important to 
    safety and the potential consequences of a LOCA/LOOP event during the 
    performance of the test.
        The exemption will not significantly 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 environmental impacts, the 
    proposed action does not affect nonradiological plant effluents and has 
    no other environmental impacts. Accordingly, the Commission concludes 
    that there are no significant nonradiological impacts associated with 
    the proposed action.
    
    Alternatives to the Proposed Action
    
        Since the Commission has concluded there is no significant 
    environmental impact associated with the proposed action, any 
    alternatives with equal or greater environmental impact need not be 
    evaluated. As an alternative to the proposed action, the staff 
    considered denial of the proposed action (the no-action alternative). 
    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 does not involve the use of resources not previously 
    considered in the ``Final Environmental Statement Related to the 
    Operation of the Oconee Nuclear Station, Units 1, 2, and 3,'' dated 
    March 1972.
    
    Agencies and Persons Consulted
    
        In accordance with its stated policy, on November 4, 1998, the 
    staff consulted with the South Carolina State official, Virgil R. Autry 
    of the Division of Radioactive Waste Management, Bureau of Land and 
    Waste Management, Department of Health and Environmental Control, 
    regarding the environmental impact of the proposed action. The State 
    official had no comments.
    
    Finding of No Significant Impact
    
        Based on the environmental assessment, the Commission concludes 
    that the proposed action will not have a significant effect on the 
    quality of the human environment. Accordingly, the Commission has 
    determined not to prepare an environmental impact statement for the 
    proposed action.
        For further details with respect to the proposed action, see the 
    licensee's letters dated October 21 and September 17, 1998, which are 
    available for public inspection at the Commission's Public Document 
    Room, The Gelman Building, 2120 L Street, NW., Washington, DC, and at 
    the local public document room located at the Oconee County Library, 
    501 West South Broad Street, Walhalla, South Carolina.
    
        Dated at Rockville, Maryland, this 9th of November 1998.
    
        For the Nuclear Regulatory Commission.
    Herbert N. Berkow,
    Director, Project Directorate II-2, Division of Reactor Projects--I/II, 
    Office of Nuclear Reactor Regulation.
    [FR Doc. 98-30560 Filed 11-13-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
11/16/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
98-30560
Pages:
63754-63755 (2 pages)
Docket Numbers:
Docket Nos. 50-269, 50-270, and 50-287
PDF File:
98-30560.pdf