98-16745. Tennessee Valley Authority (Sequoyah Nuclear Plant, Units 1 and 2); Confirmatory Order Modifying License Effective Immediately  

  • [Federal Register Volume 63, Number 121 (Wednesday, June 24, 1998)]
    [Notices]
    [Pages 34490-34491]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-16745]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-327 and 50-328]
    
    
    Tennessee Valley Authority (Sequoyah Nuclear Plant, Units 1 and 
    2); Confirmatory Order Modifying License Effective Immediately
    
    I
    
        Tennessee Valley Authority (TVA, or the Licensee) is the holder of 
    Facility Operating License Nos. DPR-77 and DPR-79, which authorizes 
    operation of Sequoyah Nuclear Plant, Units 1 and 2 located in Hamilton 
    County, Tennessee.
    
    II
    
        The staff of the U.S. Nuclear Regulatory Commission (NRC) has been 
    concerned that Thermo-Lag 330-1 fire barrier systems installed by 
    licensees may not provide the level of fire endurance intended and that 
    licensees that use Thermo-Lag 330-1 fire barriers may not be meeting 
    regulatory requirements. During the 1992 to 1994 timeframe, the NRC 
    staff issued Generic Letter (GL) 92-08, ``Thermo-Lag 330-1 Fire 
    Barriers'' and subsequent requests for additional information that 
    requested licensees to submit plans and schedules for resolving the 
    Thermo-Lag issue. The NRC staff has obtained and reviewed all 
    licensees' corrective plans and schedules. The staff is concerned that 
    some licensees may not be making adequate progress toward resolving the 
    plant-specific issues, and that some implementation schedules may be 
    either too tenuous or too protracted. For example, several licensees 
    informed the NRC staff that their completion dates had slipped by 6 
    months to as much as 3 years. For plants that have completion action 
    scheduled beyond 1997, including Sequoyah Nuclear Plant, Units 1 and 2, 
    the NRC staff has met with the licensees to discuss the progress of the 
    licensees' corrective actions and the extent of licensee management 
    attention regarding completion of Thermo-Lag corrective actions. In 
    addition, the NRC staff discussed with licensees the possibility of 
    accelerating their completion schedules.
        TVA was one of the licensees with which the NRC staff held 
    meetings. At the May 30, 1997, meeting, the NRC staff reviewed with TVA 
    the schedule of Thermo-Lag corrective actions for the Sequoyah units 
    described in the handout presented to the NRC during that meeting. 
    Based on the information provided during the meeting, as well as a 
    subsequent letter dated June 25, 1997, the NRC staff has concluded that 
    the schedules presented by TVA are reasonable. This conclusion is based 
    on (1) the amount of installed Thermo-Lag, (2) the complexity of the 
    plant-specific fire barrier configurations and issues, (3) the need to 
    perform certain plant modifications during outages as opposed to those 
    that can be performed while the plant is at power, and (4) integration 
    with other significant, but unrelated issues that TVA is addressing at 
    its plant. In order to remove compensatory measures such as fire 
    watches, it has been determined that resolution of the Thermo-Lag 
    corrective actions by TVA must be completed in accordance with current 
    schedules. By letter dated April 29, 1998, the NRC staff notified TVA 
    of its plan to incorporate TVA's schedule commitment into a requirement 
    by issuance of an order and requested consent from the Licensee. By 
    letter dated May 13, 1998, TVA provided its consent to issuance of a 
    Confirmatory Order.
    
    III
    
        The Licensee's commitment as set forth in its letter of May 13, 
    1998, is acceptable and is necessary for the NRC to conclude that 
    public health and safety are reasonably assured.
        To preclude any schedule slippage and to assure public health and 
    safety, the NRC staff has determined that the Licensee's commitment in 
    its May 13, 1998, letter be confirmed by this Order. The Licensee has 
    agreed to this action. Based on the above, and the Licensee's consent, 
    this Order is immediately effective upon issuance.
    
    IV
    
        Accordingly, pursuant to sections 103, 161b, 161i, 161o, 182, and 
    186 of the Atomic Energy Act of 1954, as amended, and the Commission's 
    regulations in 10 CFR 2.202 and 10 CFR Part 50, It Is Hereby Ordered, 
    effective immediately, that:
    
        The Tennessee Valley Authority (TVA) shall complete final 
    implementation of Thermo-Lag 330-1 fire barrier corrective actions 
    at the Sequoyah Nuclear Plant, Units 1 and 2 as described in the TVA 
    submittal dated June 25, 1997. Walkdowns, evaluations, and upgrades 
    will be completed by June 30, 1999.
    
    The Director, Office of Nuclear Reactor Regulation, may relax or 
    rescind, in writing, any provisions of this Confirmatory Order upon a 
    showing by the Licensee of good cause.
    
    V
    
        Any person adversely affected by this Confirmatory Order, other 
    than the Licensee, may request a hearing within 20 days of its 
    issuance. Where good cause is shown, consideration will be given to 
    extending the time to request a hearing. A request for extension of 
    time must be made in writing to the Director, Office of Nuclear Reactor 
    Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, 
    and include a statement of good cause for the extension. Any request 
    for a hearing shall be submitted to the Secretary, U.S. Nuclear 
    Regulatory Commission, Attention: Rulemaking and Adjudications Staff, 
    Washington, D.C. 20555. Copies of the hearing request shall also be 
    sent to the Director, Office of Nuclear Reactor Regulation, U. S. 
    Nuclear Regulatory Commission, Washington, D.C. 20555, to the Deputy 
    Assistant General Counsel for Enforcement at the same address, to the 
    Regional Administrator, NRC Region II at the Atlanta Federal Center, 23 
    T85, 61 Forsyth Street, SW., Atlanta, Georgia 30303-3415, and to the 
    Licensee. If such a person requests a hearing, that person shall set 
    forth with particularity the manner in which his/her interest is 
    adversely affected by this Order and shall address criteria set forth 
    in 10 CFR 2.714(d).
        If a hearing is requested by a person whose interest is adversely 
    affected, the Commission will issue an Order designating the time and 
    place of any such hearing. If a hearing is held, the issue to be 
    considered at such hearing shall be whether this Confirmatory Order 
    should be sustained.
        In the absence of any request for hearing, or written approval of 
    an extension of time in which to request a hearing, the provisions 
    specified in Section IV above shall be final 20 days from the date of 
    this Order without further order or proceedings. If an extension of 
    time for requesting a hearing has been approved, the provisions 
    specified in Section IV shall be final when the extension expires if a 
    hearing request has not been received. An answer or a request for 
    hearing shall not stay the immediate effectiveness of this Order.
    
        Dated at Rockville, Maryland this 18th day of June 1998.
    
    
    [[Page 34491]]
    
    
        For the Nuclear Regulatory Commission.
    Samuel J. Collins,
    Director Office of Nuclear Reactor Regulation.
    [FR Doc. 98-16745 Filed 6-23-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
06/24/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
98-16745
Pages:
34490-34491 (2 pages)
Docket Numbers:
Docket Nos. 50-327 and 50-328
PDF File:
98-16745.pdf