99-22489. Indiana Michigan Power 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 64, Number 168 (Tuesday, August 31, 1999)]
    [Notices]
    [Pages 47533-47535]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 99-22489]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-315 AND 50-316]
    
    
    Indiana Michigan Power 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 amendments to Facility Operating License Nos. 
    DPR-58 and DPR-74 issued to Indiana Michigan Power Company (the 
    licensee) for operation of the Donald C. Cook Nuclear Power Plant, 
    Units 1 and 2, located in Berrien County, Michigan.
        The proposed amendments would change the runout limits for a safety 
    injection (SI) pump to 675 gallons per minute (gpm), unless the pump is 
    specifically tested to a higher flow rate, not exceeding 700 gpm for 
    both Units 1 and 2. This change was initiated upon reevaluation of 
    correspondence from Westinghouse sent to the licensee in 1991, which 
    indicated that the generic runout limits for Pacific 2'' JTCH pumps was 
    675 gpm unless each specific pump is tested to a higher flow rate. 
    Individual testing is necessary due to test variations between pumps 
    which may limit the applicability of testing of one pump to another 
    pump due to manufacturing tolerances in the sand cast impellers and 
    material changes in the pump casing.
        Furthermore, the bases section is being clarified to describe why 
    the injection rather than the recirculation mode during flow balancing 
    is the minimum resistance and, consequently, more conservative 
    configuration for runout considerations.
        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
    
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    analysis of the issue of no significant hazards consideration, which is 
    presented below:
    
        In accordance with 10 CFR 50.92, this proposed amendment does 
    not involve a significant hazard consideration if it does not:
        1. Involve a significant increase in the probability or 
    consequences of an accident previously evaluated.
        The proposed reduction in the SI pump runout flow does not 
    increase the probability of occurrence of any previously evaluated 
    accident because the SI pumps are not considered to be accident 
    initiators. In addition, flow balancing performed at Cook Nuclear 
    Plant has proven the ability to deliver the minimum T/S flow of 300 
    gpm to each pair of cold leg injection points without exceeding the 
    675 gpm (or 700 gpm) pump runout limits. Therefore, the emergency 
    core cooling system performance objectives of 10 CFR 50.46 are not 
    impacted and this change does not involve a significant increase in 
    the consequences of an accident previously evaluated.
        2. Create the possibility of a new or different kind of accident 
    from any accident previously evaluated.
        This proposed change imposes a generic limit on maximum 
    allowable flow for untested SI pumps. No physical system changes or 
    changes in operating modes are being made that could introduce new 
    or different kinds of accidents from those previously evaluated. As 
    discussed in (1) above, the SI pumps are not considered accident 
    initiators, and this status is not affected by the change to the SI 
    pump runout limits.
        3. Involve a significant reduction in a margin of safety.
        This change reflects a reduced maximum single pump flow to be 
    observed during flow balancing of the SI system. Flow balance 
    testing at Cook Nuclear Plant has demonstrated the ability to meet 
    the SI flow requirements while maintaining an adequate margin to the 
    revised lower runout limits being proposed by this submittal. 
    Because the minimum required SI flow delivered to the core has not 
    been reduced by this change, the change does not involve a reduction 
    in a margin of safety.
        Based on the preceding, the evaluation concluded that the 
    proposed change to the SI pump runout limits does not involve a 
    significant hazards consideration as defined in 10 CFR 50.92.
    
        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 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 Chief, Rules and 
    Directives Branch, Division of Administrative 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 6D59, 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 September 30, 1999, 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 Maud Preston Palenske Memorial Library, 
    500 Market Street, St. Joseph, MI 49085. 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
    
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    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: Rulemakings and 
    Adjudications Staff, or may be delivered to the Commission's Public 
    Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, 
    by the above date. 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 Jeremy J. Euto, Esquire, 500 Circle 
    Drive, Buchanan, MI 49107, 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 21, 1999, 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 Maud Preston Palenske Memorial Library, 
    500 Market Street, St. Joseph, MI 49085.
    
        Dated at Rockville, Maryland, this 25th day of August 1999.
    
        For the Nuclear Regulatory Commission.
    John F. Stang, Sr.,
    Project Manager, Section 1, Project Directorate III, Division of 
    Licensing Project Management, Office of Nuclear Reactor Regulation.
    [FR Doc. 99-22489 Filed 8-30-99; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
08/31/1999
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
99-22489
Pages:
47533-47535 (3 pages)
Docket Numbers:
Docket Nos. 50-315 AND 50-316
PDF File:
99-22489.pdf