96-17653. Northeast Utilities Service Company; 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 134 (Thursday, July 11, 1996)]
    [Notices]
    [Pages 36583-36585]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 96-17653]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 50-336]
    
    
    Northeast Utilities Service Company; 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. 
    DPR-65 issued to Northeast Nuclear Energy Company, et al. (the 
    licensee) for operation of the Millstone Nuclear Power Station, Unit 
    No. 2, located in New London, Connecticut.
        The proposed amendment was requested on July 3, 1996, and would 
    provide a one-time change to Millstone Unit 2 (MP2) Technical 
    Specification 3.9.1, ``Refueling Operations, Boron Concentration.'' The 
    proposed change would remove the requirement that the boron 
    concentration in all filled portions of the Reactor Coolant System be 
    ``uniform.'' This change would only be applicable during the MP2 Cycle 
    13 mid-cycle core offload. The requested change supersedes the June 3, 
    1996, request.
        On March 14, 1996, during surveillance testing, it was discovered 
    that a Low Pressure Safety Injection (LPSI) valve could not be closed. 
    In order to repair the valve, the Shutdown Cooling System will have to 
    be removed from service since it is not possible to isolate flow 
    through a stuck open LPSI valve with Shutdown Cooling in operation. The 
    repair requires an offload of the core to the Spent Fuel Pool which 
    will permit removal of the Shutdown Cooling System from service.
        Since the core offload could not have been anticipated at the time 
    of shutdown, the Reactor Coolant System was not borated to the 
    refueling concentration required by the Technical Specifications (TSs).
        The proposed one-time TS change would strike the words ``of all 
    filled portions'' and ``uniform and'' and add a footnote indicating 
    that, for the Cycle 13 mid-cycle core offload activities, it is 
    acceptable for the boron concentrations of the water volumes in the 
    steam generators and the connecting piping to be as low as 1300 ppm.
        The Bases for 3.9.1 would be modified to explain that the boron 
    concentration of the water volumes in the Pressurizer, Shutdown Cooling 
    System, Reactor Vessel, Refueling Pool, and the associated connecting 
    piping will be maintained at 1950 ppm boron concentration. This 
    concentration will be high enough to ensure that, even in the unlikely 
    event that all of the lower boron concentration water from the Steam 
    Generators and connecting piping were to mix with the Shutdown Cooling 
    System water, the resulting Shutdown Cooling System boron concentration 
    will remain greater than the minimum required refueling boron 
    concentration.
        The initial June 3, 1996, request would have required that the 
    Reactor Coolant System (RCS) inventory be reduced to mid-loop and 
    borate the RCS to greater than 1820 ppm boron to maintain the core at 
    least 5% subcritical during refueling. The current request will reduce 
    the RCS inventory to a level above mid-loop and borate the RCS to 1950 
    ppm to achieve the subcritical conditions.
        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 proposed changes do not involve [a significant hazards 
    consideration] because the changes would not:
        1. Involve a significant increase in the probability or 
    consequence of an accident previously evaluated.
        Refueling Operations Technical Specification 3.9.1 requires 
    that, with the reactor vessel head unbolted or removed, the boron 
    concentration of all filled portions of the Reactor Coolant System 
    and the refueling canal shall be maintained uniform and sufficient 
    to ensure that the more restrictive of the following conditions is 
    met:
        a. Either a Keff of 0.95 or less, or
        b. A boron concentration of greater than or equal to 1720 ppm
        The proposed technical specification change would strike the 
    words ``of all filled portions'' and ``uniform and'' and add a 
    footnote indicating that for the Cycle 13 mid-cycle core offload 
    activities, it is acceptable for the boron concentrations of the 
    water volumes in the steam generators and connecting piping to be as 
    low as 1300 ppm. In addition, a surveillance will be added to 
    determine that the boron concentration in the steam generators is 
    greater than or equal to 1300 ppm prior to entry into Mode 6.
        The impact of the change on the boron dilution accident and the 
    loss of shutdown cooling flow has been evaluated. Based upon this 
    evaluation, the proposed change to Technical Specification 3.9.1 
    does not involve a significant increase in the probability or 
    consequences of these accidents. The probability of a boron dilution 
    accident or a loss of shutdown cooling event is not increased by 
    allowing the RCS [reactor coolant system] boron concentration in the 
    stagnant regions of the RCS to be less than the previously required 
    concentration since this is compensated by increasing the boron 
    concentration requirement of the shutdown cooling loop in Mode 6. 
    The consequences of a boron dilution accident would not be 
    increased. In fact, the compensatory measure of increasing the RCS 
    boron concentration in the shutdown cooling loops and reactor vessel 
    core regions will result in a higher initial boron concentration for 
    the boron dilution accident, which would actually increase the time 
    to core criticality, ensuring that the operator has at least 30 
    minutes to intervene. The consequences of a loss of shutdown cooling 
    flow are not increased as the core would continue to remain greater 
    than 5% subcritical (assuming all the control element assemblies 
    remain inserted) without operator intervention even if the less 
    borated water in the stagnant regions of the RCS reached the core 
    regions without mixing.
        2. Create the possibility of a new or different kind of accident 
    from any previously evaluated.
        By maintaining 1950 ppm in the active region of the RCS, the 
    required shutdown margin is assured, even in the unlikely event that 
    the stagnant [regions] of the RCS mix with the active regions. Thus, 
    the proposed technical specification change would not create the 
    possibility of a new or different type of accident than previously 
    evaluated. Further, the proposed change has no impact on the 
    mitigation of a boron dilution accident or a loss of shutdown 
    cooling event.
    
    [[Page 36584]]
    
        3. Involve a significant reduction in the margin of safety.
        The proposed technical specification change will not result in a 
    significant reduction in the margin of safety. The results of the 
    boron dilution accident, and the loss of shutdown cooling event are 
    not adversely impacted by the modification to the RCS boration 
    technical specification. In the event of a boron dilution accident, 
    the operator will continue to have at least 30 minutes to prevent 
    core criticality. Without crediting operator intervention, the 
    potential core boron reduction associated with a loss of shutdown 
    cooling event will not result in core criticality. As such, there is 
    no reduction in the 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 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 20555-0001, 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 August 12, 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 Learning Resources Center, Three Rivers 
    Community-Technical College, 574 New London Turnpike, Norwich, 
    Connecticut, and the Waterford Library, ATTN: Vince Juliano, 49 Rope 
    Ferry Road, Waterford Connecticut. 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
    
    [[Page 36585]]
    
    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 Phillip F. McKee: 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 Ms. L. M. 
    Cuoco, Senior Nuclear Counsel, Northeast Utilities Services Company, 
    Post Office Box 270, Hartford, Connecticut 06141-0270, 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 July 3, 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 Learning Resources Center, Three Rivers 
    Community-Technical College, 574 New London Turnpike, Norwich, 
    Connecticut, and the Waterford Library, ATTN: Vince Juliano, 49 Rope 
    Ferry Road, Waterford, Connecticut.
    
        Dated at Rockville, Maryland, this 3rd day of July 1996.
    
        For the Nuclear Regulatory Commission.
    Daniel G. McDonald,
    Sr. Project Manager, Northeast Utilities Project Directorate, Division 
    of Reactor Projects--I/II, Office of Nuclear Reactor Regulation.
    [FR Doc. 96-17653 Filed 7-10-96; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
07/11/1996
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
96-17653
Pages:
36583-36585 (3 pages)
Docket Numbers:
Docket No. 50-336
PDF File:
96-17653.pdf