94-21862. Georgia Power Company, et al.; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing  

  • [Federal Register Volume 59, Number 171 (Tuesday, September 6, 1994)]
    [Unknown Section]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-21862]
    
    
    [[Page Unknown]]
    
    [Federal Register: September 6, 1994]
    
    
    -----------------------------------------------------------------------
    
    NUCLEAR REGULATORY COMMISSION
    [Docket No. 50-424]
    
     
    
    Georgia Power Company, et al.; Notice of Consideration of 
    Issuance of Amendment to Facility Operating License, Proposed No 
    Significant Hazards Consideration Determination, and Opportunity for a 
    Hearing
    
        The U.S. Nuclear Regulatory Commission (the Commission) is 
    considering issuance of an amendment to Facility Operating License Nos. 
    NPF-68 issued to Georgia Power Company, Oglethorpe Power Corporation 
    Municipal Electric Authority of Georgia, City of Dalton, Georgia (the 
    licensee) for operation of the Vogtle Electric Generating Plant, Unit 
    1, located in Burke County, Georgia.
        The proposed amendment would eliminate article 2.C(6) and the 
    associated attachment 1 of the license. Article 2.C(6) references 
    attachment 1 which lists special diesel generator (DG) maintenance and 
    surveillance requirements.
        Before issuance of the proposed license amendment, the Commission 
    will have made findings required by the Atomic Energy Act of 1954, as 
    amended (the Act) and the Commission's regulations.
        The Commission has made a proposed determination that the amendment 
    request involves no significant hazards consideration. Under the 
    Commission's regulations in 10 CFR 50.92, this means that operation of 
    the facility in accordance with the proposed amendment would not (1) 
    involve a significant increase in the probability or consequences of an 
    accident previously evaluated; or (2) create the possibility of a new 
    or different kind of accident from any accident previously evaluated; 
    or (3) involve a significant reduction in a margin of safety. As 
    required by 10 CFR 50.91(a), the licensee has provided its analysis of 
    the issue of no significant hazards consideration, which is presented 
    below:
    
        The change to the license will delete license conditions related 
    to DG component inspections that were imposed based on the 
    recommendations in NUREG-1216. Therefore, the detailed steps of 
    preventive maintenance surveillance programs will become subject to 
    the same degree of NRC staff review and approval as for DGs provided 
    by other manufacturers. However, future revisions of the maintenance 
    surveillance program are subject to the provisions of 10 CFR 50.59. 
    The owners group in conjunction with the DG manufacturer is 
    developing a generic DG management program. The transition from the 
    current program to the generic program will be accomplished under 
    the provisions of 10 CFR 50.59.
        The requirements imposed by attachment 1 to the license were in 
    addition to the Technical Specifications surveillance and 
    maintenance requirements for DGs in nuclear service. The 
    requirements of attachment 1 were imposed due to the unresolved 
    concerns about the reliability of TDI DGs that existed at the time 
    of issuance of the VEGP Unit 1 license. Since that time the concerns 
    have been resolved by substantial operational data and inspection 
    results which have demonstrated that these DGs may be treated on a 
    par with other DGs within the nuclear industry and subjected to the 
    same standard regulations without the special requirements of NUREG-
    1216. The proposed change will result in continuing DG performance 
    in accordance with NRC requirements for this function, and it is 
    likely to result in improved availability. The current Technical 
    Specification surveillance requirements will continue to assure that 
    the DGs are proven at regular intervals to perform in accordance 
    with NRC requirements. These license conditions have been 
    technically justified on the basis of current reliability data and 
    inspection results of operating TDI DGs throughout the last several 
    years. The NRC staff has agreed with these conclusions as documented 
    in the SER for the topical report.
        The current DG maintenance and surveillance program for the VEGP 
    DGs is in agreement with the applicable portions of the surveillance 
    and maintenance programs described in the topical report and with 
    the requirements of the Technical Specifications. Any subsequent 
    changes to the surveillance and maintenance requirements currently 
    contained in attachment 1 to the license following the removal of 
    the attachment from the Operating License will be made in accordance 
    with 10 CFR 50.59.
        Based on the above considerations, GPC has concluded the 
    following concerning 10 CFR 50.92.
        1. The proposed change to the license does not involve a 
    significant increase in the probability or consequences of an 
    accident previously evaluated because the availability and 
    reliability of the DGs will remain within the limits previously 
    assumed in the safety analyses.
        2. The proposed change to the license does not create the 
    possibility of a new or different kind of accident from any accident 
    previously evaluated because it does not result in any physical 
    changes to the plant or in its modes of operation and the DGs have 
    been demonstrated to operate at a level of reliability that is 
    consistent with that which was previously determined to be 
    acceptable for this application.
        3. The proposed deletion from the license does not involve a 
    significant reduction in a margin of safety because the results of 
    the operational data and inspection reports have demonstrated that 
    the license conditions are not required to assure that the DGs will 
    be maintained in a state of reliability consistent with that assumed 
    for the safety analyses.
    
        The NRC staff has reviewed the licensee's analysis in conjunction 
    with its cover letter, and, based on this review, it appears that the 
    three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC 
    staff proposes to determine that the amendment request involves no 
    significant hazards consideration.
        The Commission is seeking public comments on this proposed 
    determination. Any comments received within 30 days after the date of 
    publication of this notice will be considered in making any final 
    determination.
        Normally, the Commission will not issue the amendment until the 
    expiration of the 30-day notice period. However, should circumstances 
    change during the notice period such that failure to act in a timely 
    way would result, for example, in derating or shutdown of the facility, 
    the Commission may issue the license amendment before the expiration of 
    the 30-day notice period, provided that its final determination is that 
    the amendment involves no significant hazards consideration. The final 
    determination will consider all public and State comments received. 
    Should the Commission take this action, it will publish in the Federal 
    Register a notice of issuance and provide for opportunity for a hearing 
    after issuance. The Commission expects that the need to take this 
    action will occur very infrequently.
        Written comments may be submitted by mail to the Rules Review and 
    Directives Branch, Division of Freedom of Information and Publications 
    Services, Office of Administration, U.S. Nuclear Regulatory Commission, 
    Washington, DC 20555, and should cite the publication date and page 
    number of this Federal Register notice. Written comments may also be 
    delivered to Room 6D22, Two White Flint North, 11545 Rockville Pike, 
    Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. 
    Copies of written comments received may be examined at the NRC Public 
    Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 
    20555.
        The filing of requests for hearing and petitions for leave to 
    intervene is discussed below.
        By October 6, 1994, the licensee may file a request for a hearing 
    with respect to issuance of the amendment to the subject facility 
    operating license and any person whose interest may be affected by this 
    proceeding and who wishes to participate as a party in the proceeding 
    must file a written request for a hearing and a petition for leave to 
    intervene. Requests for a hearing and a petition for leave to intervene 
    shall be filed in accordance with the Commission's ``Rules of Practice 
    for Domestic Licensing Proceedings'' in 10 CFR Part 2. Interested 
    persons should consult a current copy of 10 CFR 2.714 which is 
    available at the Commission's Public Document Room, the Gelman 
    Building, 2120 L Street NW., Washington, DC 20555 and at the local 
    public document room located at Burke County Public Library, 412 Fourth 
    St., Waynesboro, Georgia 30830. If a request for a hearing or petition 
    for leave to intervene is filed by the above date, the Commission or an 
    Atomic Safety and Licensing Board, designated by the Commission or by 
    the Chairman of the Atomic Safety and Licensing Board Panel, will rule 
    on the request and/or petition; and the Secretary or the designated 
    Atomic Safety and Licensing Board will issue a notice of hearing or an 
    appropriate order. As required by 10 CFR 2.714, a petition for leave to 
    intervene shall set forth with particularity the interest of the 
    petitioner in the proceeding, and how that interest may be affected by 
    the results of the proceeding. The petition should specifically explain 
    the reasons why intervention should be permitted with particular 
    reference to the following factors: (1) the nature of the petitioner's 
    right under the Act to be made party to the proceeding; (2) the nature 
    and extent of the petitioner's property, financial, or other interest 
    in the proceeding; and (3) the possible effect of any order which may 
    be entered in the proceeding on the petitioner's interest. The petition 
    should also identify the specific aspect(s) of the subject matter of 
    the proceeding as to which petitioner wishes to intervene. Any person 
    who has filed a petition for leave to intervene or who has been 
    admitted as a party may amend the petition without requesting leave of 
    the Board up to 15 days prior to the first prehearing conference 
    scheduled in the proceeding, but such an amended petition must satisfy 
    the specificity requirements described above. Not later than 15 days 
    prior to the first prehearing conference scheduled in the proceeding, a 
    petitioner shall file a supplement to the petition to intervene which 
    must include a list of the contentions which are sought to be litigated 
    in the matter. Each contention must consist of a specific statement of 
    the issue of law or fact to be raised or controverted. In addition, the 
    petitioner shall provide a brief explanation of the bases of the 
    contention and a concise statement of the alleged facts or expert 
    opinion which support the contention and on which the petitioner 
    intends to rely in proving the contention at the hearing. The 
    petitioner must also provide references to those specific sources and 
    documents of which the petitioner is aware and on which the petitioner 
    intends to rely to establish those facts or expert opinion. Petitioner 
    must provide sufficient information to show that a genuine dispute 
    exists with the applicant on a material issue of law or fact. 
    Contentions shall be limited to matters within the scope of the 
    amendment under consideration. The contention must be one which, if 
    proven, would entitle the petitioner to relief. A petitioner who fails 
    to file such a supplement which satisfies these requirements with 
    respect to at least one contention will not be permitted to participate 
    as a party.
        Those permitted to intervene become parties to the proceeding, 
    subject to any limitations in the order granting leave to intervene, 
    and have the opportunity to participate fully in the conduct of the 
    hearing, including the opportunity to present evidence and cross-
    examine witnesses.
        If a hearing is requested, the Commission will make a final 
    determination on the issue of no significant hazards consideration. The 
    final determination will serve to decide when the hearing is held.
        If the final determination is that the amendment request involves 
    no significant hazards consideration, the Commission may issue the 
    amendment and make it immediately effective, notwithstanding the 
    request for a hearing. Any hearing held would take place after issuance 
    of the amendment.
        If the final determination is that the amendment request involves a 
    significant hazards consideration, any hearing held would take place 
    before the issuance of any amendment.
        A request for a hearing or a petition for leave to intervene must 
    be filed with the Secretary of the Commission, U.S. Nuclear Regulatory 
    Commission, Washington, DC 20555, Attention: Docketing and Services 
    Branch, or may be delivered to the Commission's Public Document Room, 
    the Gelman Building, 2120 L Street, NW., Washington, DC 20555, by the 
    above date. Where petitions are filed during the last 10 days of the 
    notice period, it is requested that the petitioner promptly so inform 
    the Commission by a toll-free telephone call to Western Union at 1-
    (800) 248-5100 (in Missouri 1-(800) 342-6700). The Western Union 
    operator should be given Datagram Identification Number N1023 and the 
    following message addressed to Herbert N. Berkow: petitioner's name and 
    telephone number, date petition was mailed, plant name, and publication 
    date and page number of this Federal Register notice. A copy of the 
    petition should also be sent to the Office of the General Counsel, U.S. 
    Nuclear Regulatory Commission, Washington, DC 20555, and to Arthur H. 
    Domby, Troutman Sanders, Nations Bank Plaza, 600 Peachtree Street NE., 
    Atlanta, Georgia 30308, attorney for the licensee.
        Nontimely filings of petitions for leave to intervene, amended 
    petitions, supplemental petitions and/or requests for hearing will not 
    be entertained absent a determination by the Commission, the presiding 
    officer or the presiding Atomic Safety and Licensing Board that the 
    petition and/or request should be granted based upon a balancing of the 
    factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
        For further details with respect to this action, see the 
    application for amendment dated August 16, 1994, which is available for 
    public inspection at the Commission's Public Document Room, the Gelman 
    Building, 2120 L Street, NW., Washington, DC 20555, and at the local 
    public document room located at the Burke County Public Library, 412 
    Fourth Street, Waynesboro, Georgia 30830.
    
        Dated at Rockville, Maryland, this 30th day of August 1994.
    
        For the Nuclear Regulatory Commission.
    Louis Wheeler,
    Project Manager, Project Directorate II-3, Division of Reactor 
    Projects--I/II, Office of Nuclear Reactor Regulation.
    [FR Doc. 94-21862 Filed 9-2-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
09/06/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Uncategorized Document
Document Number:
94-21862
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: September 6, 1994, Docket No. 50-424