99-26942. Consolidated Edison Company of New York, Inc; Facility Operating License No. DPR 26; Receipt of Petition for Director's Decision Under 10 CFR 2.206  

  • [Federal Register Volume 64, Number 199 (Friday, October 15, 1999)]
    [Notices]
    [Pages 55993-55994]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 99-26942]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 50-247]
    
    
    Consolidated Edison Company of New York, Inc; Facility Operating 
    License No. DPR 26; Receipt of Petition for Director's Decision Under 
    10 CFR 2.206
    
        Notice is hereby given that by petition dated September 15, 1999, 
    Mr. David A. Lochbaum, on behalf of the Union of Concerned Scientists 
    (Petitioner), has requested that the U.S. Nuclear Regulatory Commission 
    (NRC) take action with regard to the Indian Point Nuclear Generating 
    Unit No. 2, owned and operated by the Consolidated Edison Company of 
    New York, Inc. The Petitioner requests that the NRC take enforcement 
    action to modify or suspend the operating license for the Indian Point 
    Nuclear Generating Unit No. 2, operated by the Consolidated Edison 
    Company of New York, Inc. (the licensee), to prevent the reactor from 
    resuming operation until the five issues identified in the attachment 
    to the Petition have been fully resolved. As an acceptable alternative 
    in lieu of a suspension or modification of the license, the Petitioner 
    requested that the NRC issue a confirmatory action letter or an order 
    requiring these issues to be fully resolved before unit restart. The 
    five issues that were raised in the Petition are (1) the apparent 
    violation of station battery design and licensing bases, (2) the 
    apparent failure to adequately correct circuit breaker problems, (3) 
    the apparent unreliability of emergency diesel generators, (4) the 
    potentially unjustified license amendment for undervoltage and degraded 
    voltage relay surveillance intervals, and (5) the apparent errors and 
    nonconservatisms in individual plant examinations (IPEs). Along with
    
    [[Page 55994]]
    
    the last issue, the Petitioner stated that the event on August 31, 
    1999, at Indian Point Unit 2 revealed potential problems with the 
    plant-specific risk assessment developed by the licensee and now used 
    to establish priorities for maintenance and inspections. Additionally, 
    the Petitioner requested that a public hearing on this Petition be 
    conducted in the vicinity of the plant before its restart is authorized 
    by the NRC. In a transcribed telephone conversation between the 
    Petitioner and the members of the NRC's Petition Review Board on 
    September 22, 1999, the Petitioner clarified two of the issues in the 
    Petition. First, the Petitioner stated that because of an apparent 
    failure to accomplish the commitment in the NRC's safety evaluation for 
    the license amendment mentioned in the Petition, the Petitioner was 
    concerned that past licensing commitments may not have been 
    implemented. Second, the Petitioner questioned whether the amount of 
    time the licensee took to perform certain actions during the August 31 
    event was consistent with the times expected if a station blackout 
    (SBO) had occurred since many of the procedures and processes in 
    response to an SBO event were used.
        As the basis for this request, the Petitioner states that the 
    issues, if valid, have clear and direct safety implications because 
    they involve equipment explicitly required to function to mitigate 
    accidents. With regard to your IPE issue, the Petitioner states that, 
    if valid, it has indirect safety implications because it involves 
    information used by the plant's owner to schedule maintenance and 
    inspections on equipment implicitly required to function to mitigate an 
    accident. The Petitioner also stated that the specific problems 
    revealed by the August 31 event were caused by systematic process 
    breakdowns, including inadequate procedures, inadequate training, and 
    plant configuration errors, and that the licensee's plan does not 
    contain sufficient activities that provide reasonable assurance that 
    problems in other safety systems are identified and corrected.
        The request is being treated pursuant to 10 CFR 2.206 of the 
    Commission's regulations. The request has been referred to the Director 
    of the Office of Nuclear Reactor Regulation. As provided by Section 
    2.206, appropriate action will be taken on this Petition within a 
    reasonable time.
        By letter dated October 8, 1999, the Director denied the 
    Petitioner's request for immediate action at Indian Point Unit 2.
        A copy of the petition is available for 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 White Plains Public Library, 100 Martine Avenue, White Plains, New 
    York 10610.
    
        Dated at Rockville, Maryland, this 8th day of October 1999.
    
        For the Nuclear Regulatory Commission.
    Samuel J. Collins,
    Director, Office of Nuclear Reactor Regulation.
    [FR Doc. 99-26942 Filed 10-14-99; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
10/15/1999
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
99-26942
Pages:
55993-55994 (2 pages)
Docket Numbers:
Docket No. 50-247
PDF File:
99-26942.pdf