97-15271. Wisconsin Electric Power Company; Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing  

  • [Federal Register Volume 62, Number 111 (Tuesday, June 10, 1997)]
    [Notices]
    [Pages 31636-31638]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 97-15271]
    
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-266 and 50-301]
    
    
    Wisconsin Electric Power Company; 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 amendments to Facility Operating License Nos. 
    DPR-24 and DPR-27 issued to Wisconsin Electric Power Company (the 
    licensee), for operation of the Point Beach Nuclear Power Plant, Units 
    1 and 2, located in Manitowoc County, Wisconsin.
        The proposed amendments would change Technical Specification 
    requirements related to the service water system, component cooling 
    water system, containment cooling and iodine removal systems, auxiliary 
    electrical systems, and the control room emergency filtration system. 
    The September 30, 1996, application was noticed in the Federal Register 
    on November 19, 1996 (61 FR 58905). The November 26, and December 12, 
    1996, February 13, and March 5, 1997, applications were noticed in the 
    Federal Register on April 9, 1997 (62 FR 17244). The supplemental 
    applications dated April 2, April 16, May 9, and June 3, 1997, would 
    eliminate separate requirements for the component cooling water system 
    for single-unit and two-unit operation, revise the acceptance criteria 
    for laboratory testing of the control room emergency filtration system 
    charcoal adsorber banks from 90 percent to 99 percent, and supplement 
    additional information on the basis for acceptability of equipment 
    qualification analyses and dose assessments resulting from a loss-of-
    coolant accident.
        The licensee's supplements of November 26, and December 12, 1996, 
    February 13, March 5, April 2, April 16, May 9, and June 3, 1997, 
    stated that the conclusions provided in the September 30, 1996, ``No 
    Significant Hazards Consideration'' were not altered by the additional 
    information provided.
        The June 3, 1997, submittal requested the proposed amendments be 
    handled on an exigent basis based on the current schedule which 
    indicates that Unit 2 restart is scheduled for June 25, 1997, and Unit 
    1 restart is scheduled for July 1, 1997, and failure of the issuance of 
    the amendments by these dates would result in prevention of Point 
    Beach's resumption of operation. The licensee states that the 
    circumstances of exigency were not avoidable, based on the need to 
    refine and revise the submittals due to emergent issues, principally 
    control room dose analyses. The NRC has determined that the licensee 
    used its best efforts to make a timely application for the proposed 
    changes and that exigent circumstances do exist and were not the result 
    of any intentional delay on the part of the licensee.
        Before issuance of the proposed license amendments, 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 
    requests involve 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 amendments 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. The NRC staff has 
    reviewed the licensee's analysis against the standards of 10 CFR 
    50.92(c). The NRC staff's review is presented below.
        (1) The proposed changes do not involve a significant increase in 
    the probability or consequences of an accident previously evaluated.
        The proposed changes would increase the acceptance criteria for the 
    efficiency of the control room emergency filtration system charcoal 
    adsorbers from 90 percent to 99 percent, eliminate the designation of 
    single-unit and two-unit operational requirements for the component 
    cooling water system since four component cooling water pumps (two per 
    unit) are required to be operable. The revised bases of the charcoal 
    adsorber testing would reference ASTM [American Society for Testing and 
    Materials] D3803-89. The revised operation of the containment cooling 
    and iodine removal system, component cooling water system, and the 
    service water system would be required because of changes in 
    assumptions factored into revised design bases accident analyses and 
    the resultant impact on containment heat removal analyses, dose 
    assessment, and operation of the control room ventilation system. The 
    proposed changes in system operations were evaluated to ensure 
    equipment qualification requirements, post-accident sampling 
    capability, and doses within dose limits specified in 10 CFR Part 50, 
    Appendix A, General Design Criterion 19 were maintained within 
    regulatory limits. The consequences or probability of a previously 
    evaluated accident would, therefore, not significantly be increased.
        (2) The proposed changes do not create the possibility of a new or 
    different kind of accident from any accident previously evaluated.
        The proposed changes as reflected in the technical specifications 
    are more conservative for the systems and component operation being 
    revised. The changes resulting from new analyses were evaluated, and no 
    new or different kind of accident is introduced since no modifications 
    to the actual design is postulated, only the manner in which the plant 
    is operated and accidents are analyzed. Therefore, a new or different 
    kind of accident would not be created.
        (3) The proposed changes do not result in a significant reduction 
    in the margin of safety.
        The proposed changes would increase the required number of operable 
    components for the component cooling water system and the service water 
    system and would increase the required efficiency of the control room 
    ventilation charcoal adsorbers and ensure equipment qualification 
    inside of the containment based on new containment pressure and 
    temperature analyses. Dose assessments for the exclusion area boundary, 
    low population zone, and control room are within regulatory 
    requirements for the most severe radiological event, a loss-of-coolant 
    accident. Therefore, these changes do not involve a significant 
    reduction in a margin of safety.
        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 requests involve no significant hazards 
    consideration.
        The Commission is seeking public comments on this proposed 
    determination. Any comments received by close of business within 14 
    days after the date of publication of this notice will be considered in 
    making any final determination.
        Normally, the Commission will not issue the amendments until the 
    expiration of the 14-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
    
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    amendments before the expiration of the 14-day notice period, provided 
    that its final determination is that the amendments involve 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. 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 
    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 July 10, 1997, the licensee may file a request for a hearing 
    with respect to issuance of the amendments to the subject facility 
    operating licenses 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 Joseph P. Mann Library, 1516 Sixteenth 
    Street, Two Rivers, Wisconsin. 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 a 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 amendments 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 the amendments are issued before the expiration of the 30-day 
    hearing period, the Commission will make a final determination on the 
    issue of no significant hazards consideration. If a hearing is 
    requested, the final determination will serve to decide when the 
    hearing is held.
        If the final determination is that the amendment requests involve 
    no significant hazards consideration, the Commission may issue the 
    amendments and make them immediately effective, notwithstanding the 
    request for a hearing. Any hearing held would take place after issuance 
    of the amendments.
        If the final determination is that the amendment requests involve a 
    significant hazards consideration, any hearing held would take place 
    before the issuance of any amendments.
        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. 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 Gerald Charnoff, Esq., Shaw, Pittman, 
    Potts, and Trowbridge, 2300 N Street, NW., Washington, DC 20037, 
    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 September 30, 1996, as supplemented on 
    November 26, and December 12, 1996, February 13, March 5, April 2, 
    April 16, May 9, and June 3, 1997, 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 Joseph P. Mann Library, 1516 Sixteenth 
    Street, Two Rivers, Wisconsin.
    
        Dated at Rockville, Maryland, this 5th day of June 1997.
    
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        For the Nuclear Regulatory Commission.
    Linda L. Gundrum,
    Project Manager, Project Directorate III-1, Division of Reactor 
    Projects--III/IV, Office of Nuclear Reactor Regulation.
    [FR Doc. 97-15271 Filed 6-9-97; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
06/10/1997
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
97-15271
Pages:
31636-31638 (3 pages)
Docket Numbers:
Docket Nos. 50-266 and 50-301
PDF File:
97-15271.pdf