96-12616. Rochester Gas and Electric Corporation; 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 61, Number 97 (Friday, May 17, 1996)]
    [Notices]
    [Pages 24965-24967]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 96-12616]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket No. 50-244]
    
    
    Rochester Gas and Electric Corporation; 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 No. 
    DRP-18 issued to Rochester Gas & Electric Corporation (RG&E) for 
    operation of the R. E. Ginna Nuclear Power Plant located in Wayne 
    County, New York. The proposed amendment would modify the Technical 
    Specifications to correct several typographical errors that were 
    implemented in the Ginna Station Improved Technical Specifications 
    (ITS) at Ginna Station per Amendment No 61.
        On February 24, 1996, RG&E implemented the ITS. Currently, Ginna 
    Station is in a defueled condition while in the performance of a steam 
    generator replacement project. While in this condition, several 
    typographical errors have been discovered within the ITS by various 
    plant staff personnel. In general, these errors are minor and are 
    readily apparent. However, several errors could lead to confusion and a 
    potential incorrect application of a requirement. The correction of 
    these more limiting errors is required prior to entering MODE 2 which 
    is scheduled to occur on June 2, 1996. Failure to correct these known 
    errors would therefore prevent a scheduled resumption in power 
    operation. The proposed changes would permit the Ginna Station to enter 
    MODE 2 as planned. Exigent action is justified in order to avoid an 
    unnecessary delay in reactor startup.
        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.
        Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under 
    exigent circumstances, the NRC staff must determine that the amendment 
    request involves no significant hazards
    
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    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:
    
        1. Operation of Ginna Station in accordance with the proposed 
    changes does not involve a significant increase in the probability 
    or consequences of an accident previously evaluated. The proposed 
    changes only correct various typographical errors within the 
    technical specifications. The errors were discovered during use of 
    the new improved technical specifications and do not involve any 
    technical issues when compared to NUREG-1431 or the ``old'' 
    technical specifications. As such, these changes are administrative 
    in nature and do not impact initiators or analyzed events or assumed 
    mitigation of accident or transient events. Therefore, these changes 
    do not involve a significant increase in the probability or 
    consequences of an accident previously analyzed.
        2. Operation of Ginna Station in accordance with the proposed 
    changes does not create the possibility of a new or different kind 
    of accident from any accident previously evaluated. The proposed 
    changes do not involve a physical alteration of the plant (i.e., no 
    new or different type of equipment will be installed) or changes in 
    the methods governing normal plant operation. The proposed changes 
    will not impose any new or different requirements. Thus, this change 
    does not create the possibility of a new or different kind of 
    accident from any accident previously evaluated.
        3. Operation of Ginna Station in accordance with the proposed 
    changes does not involve a significant reduction in a margin of 
    safety. The proposed changes will not reduce a margin of plant 
    safety because the changes are administrative in nature. As such, no 
    question of safety is involved, and the change does not involve a 
    significant reduction in a margin of safety.
    
        The NRC staff has reviewed the licensee's analysis 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 15 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 15-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 15-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 20555-0001, 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.
        The filing of requests for hearing and petitions for leave to 
    intervene is discussed below.
        By June 17, 1996, 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, and at the local public 
    document room located at the Rochester Public Library, 115 South 
    Avenue, Rochester, New York 14610. 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
    
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    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 20555-0001, 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, 
    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 Jocelyn A. Mitchell, Acting Director, 
    Project Directorate I-1, 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 20555-0001, and to Nicholas S. Reynolds, 
    Winston & Strawn, 1400 L Street, NW., Washington, DC 20005, 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 May 8, 1996, as supplemented May 10, 
    1996, which is 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 
    Rochester Public Library, 115 South Avenue, Rochester, New York.
    
        Dated at Rockville, Maryland, this fourteenth day of May 1996.
    
        For the Nuclear Regulatory Commission.
    Guy S. Vissing,
    Senior Project Manager, Project Directorate I-1, Division of Reactor 
    Projects--I/II, Office of Nuclear Reactor Regulation.
    [FR Doc. 96-12616 Filed 5-16-96; 8:45 am]
    BILLING CODE 7590-01-P
    
    

Document Information

Published:
05/17/1996
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
96-12616
Pages:
24965-24967 (3 pages)
Docket Numbers:
Docket No. 50-244
PDF File:
96-12616.pdf