96-2701. Houston Lighting and Power Company, City Public Service Board of San Antonio, Central Power and Light Company, City of Austin, Texas; Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant ...  

  • [Federal Register Volume 61, Number 27 (Thursday, February 8, 1996)]
    [Notices]
    [Pages 4805-4807]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 96-2701]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    [Docket Nos. 50-498 AND 50-499]
    
    
    Houston Lighting and Power Company, City Public Service Board of 
    San Antonio, Central Power and Light Company, City of Austin, Texas; 
    Notice of Consideration of Issuance of Amendments to Facility Operating 
    Licenses, 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-76 and NPF-80, issued to Houston Lighting & Power Company, et. al., 
    (the licensee) for operation of the South Texas Project, located in 
    Matagorda County, Texas. The original application dated May 1, 1995, 
    was previously published in the Federal Register on June 6, 1995 (60 FR 
    29876). That application was supplemented by letters dated June 22, 
    August 28, November 22, December 19, 1995, January 4, January 8 (two 
    letters), and January 23, 1996.
        The proposed amendment would provide a special test exception that 
    would allow an extension of the standby diesel generator (SDG) allowed 
    outage time for a cumulative 21 days on each SDG once per fuel cycle, 
    and it would also allow an extension of the essential cooling water 
    (ECW) loop allowed outage time for a cumulative 7 days on each ECW loop 
    once per fuel cycle. These extended allowed outage times will be used 
    to perform required inspections and maintenance on the SDGs and the ECW 
    system during power operation.
        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:
    
        1. The proposed change does not involve a significant increase 
    in the probability or consequences of an accident previously 
    evaluated.
        The Standby Diesel Generators are not accident initiators, 
    therefore the increase in Allowed Outage Times for this system does 
    not increase the probability of an accident previously evaluated. 
    The three train design of the South Texas Project ensures that even 
    during the seven days the Essential Cooling Water loop is inoperable 
    there are still two complete trains available to mitigate the 
    consequences of any accident. If the Essential Cooling Water loop is 
    not inoperable during the 21 days the Standby Diesel Generator is 
    inoperable, the Standby Diesel Generator's Engineered Safety 
    Features bus and equipment in the train will be operable. This 
    ensures that all three redundant safety trains of the South Texas 
    Project design are operable. In addition the Emergency Transformer 
    will be available to supply the Engineered Safety Features bus 
    normally supplied by the inoperable Standby Diesel Generator. These 
    actions will ensure that the changes do not involve a significant 
    increase in the consequences of previously evaluated accidents.
        2. The proposed change does not create the possibility of a new 
    or different kind of accident from any accident previously 
    evaluated.
        The proposed changes affect only the magnitude of the Standby 
    Diesel Generator and Essential Cooling Water Allowed Outage Times 
    once per fuel cycle as identified by the marked-up Technical 
    Specification. As indicated above, the proposed change does not 
    involve the alteration of any equipment nor does it allow modes of 
    operation beyond those currently allowed. Therefore, implementation 
    of these proposed changes does not create the possibility of a new 
    or different kind of accident from any accident previously 
    evaluated.
        3. The proposed change does not involve a significant reduction 
    in a margin of safety.
        The proposed changes result in no significant increase in core 
    damage or large early release frequencies.
        Three sets of PSA [probabilistic safety assessment] results have 
    been presented to the NRC for the South Texas Project. One submitted 
    in 1989 from the initial Level 1 
    
    [[Page 4806]]
    PSA of internal and external events with a mean annual average CDF 
    [core damage frequency] estimate of 1.7  x  10(-4), a second one 
    submitted in 1992 to meet the IPE requirements from the Level 2 PSA/
    IPE with a CDF estimate of 4.4  x  10(-5), and an update of the PSA 
    that was reported in the August 1993 Technical Specifications 
    submittal with a variety of CDF estimates for different assumptions 
    regarding the rolling maintenance profile and different combinations 
    of modified Technical Specifications. The South Texas Project PSA 
    was updated in March of 1995 to include the NRC approved Risk-Based 
    Technical Specifications, Plant Specific Data and incorporate the 
    Emergency Transformer into the model. This update resulted in a CDF 
    estimate of 2.07  x  10(-5). When the requested changes are modeled 
    along with the compensatory actions, the resulting CDF estimate is 
    2.30  x  10(-5). While this is slightly higher (approx. 11%) than 
    the updated results, it is still significantly lower (approx. 46%) 
    than the previous Risk-Based Evaluation of Technical Specification 
    submitted in 1993. Therefore, it is concluded that there is no 
    significant reduction in the margin of safety.
        Based on the above evaluation, Houston Lighting & Power has 
    concluded that these changes do not involve any significant hazards 
    considerations.
    
        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 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.
        The filing of requests for hearing and petitions for leave to 
    intervene is discussed below.
        By March 11, 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 Wharton County Junior College, J.M. Hodges 
    Learning Center, 911 Boling Highway, Wharton, Texas 77488. 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 
    
    [[Page 4807]]
    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, 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 William D. Beckner, Director, Project Directorate 
    IV-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, and to Jack R. Newman, Esq., Newman & Holtzinger, 
    P.C., 1615 L Street, NW., Washington, DC 20036, 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 1, 1995, as supplemented by letters 
    dated June 22, August 28, November 22, December 19, 1995, January 4, 
    January 8 (two letters), and January 23, 1996, 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 Wharton County Junior College, J.M. Hodges 
    Learning Center, 911 Boling Highway, Wharton, Texas 77488.
    
        Dated at Rockville, Maryland, this 2nd day of February 1996.
    
        For the Nuclear Regulatory Commission.
    George Kalman,
    Project Manager, Project Directorate IV-1, Division of Reactor Projects 
    III/IV, Office of Nuclear Reactor Regulation.
    [FR Doc. 96-2701 Filed 2-8-96; 8:45 am]
    BILLING CODE 7590-01-P
    
    

Document Information

Published:
02/08/1996
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
96-2701
Pages:
4805-4807 (3 pages)
Docket Numbers:
Docket Nos. 50-498 AND 50-499
PDF File:
96-2701.pdf