98-24303. Illinois 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 63, Number 175 (Thursday, September 10, 1998)]
    [Notices]
    [Pages 48529-48531]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-24303]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket No. 50-461]
    
    
    Illinois 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 an amendment to Facility Operating License No. 
    NPF-62 issued to Illinois Power Company (IP, or the licensee) for 
    operation of the Clinton Power Station (CPS), located in DeWitt County, 
    Illinois.
        The proposed amendment concerns the ``ready-to-load'' requirement 
    for the Division 3 diesel generator (DG). The Division 3 DG requires 
    operator action to reset the mechanical governor to meet the ``ready-
    to-load'' requirement.
        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 proposed change revises the acceptance criteria for meeting 
    the ``ready-to-load'' requirement denoted by TS Surveillance 
    Requirement (SR) 3.8.1.17 for the Division 3 Diesel Generator (DG). 
    The proposed change also adds a discussion of this acceptance 
    criterion to the USAR [updated safety analysis report] to clarify 
    the intent of the requirement. The proposed change allows manual 
    operator action to reset the governor upon receipt of an ECCS 
    [emergency core cooling system] signal. Analyzed events are 
    considered to be initiated by the failure of plant structures, 
    systems, or components. The DGs are not considered as initiators of 
    any analyzed event. The proposed change does not have a detrimental 
    impact on the condition or performance of any plant structure, 
    system, or component that initiates an analyzed event. The proposed 
    change will not alter the operation of or otherwise increase the 
    failure probability of any plant equipment that initiates an 
    analyzed event. As such, the probability of occurrence for a 
    previously analyzed accident is not significantly increased.
        The consequences of a previously analyzed event are dependent on 
    the initial conditions assumed for the analysis, the availability 
    and successful functioning of the equipment assumed to operate in 
    response to the analyzed event, and the setpoints at which these 
    actions are initiated. The Division 3 DG continues to override the 
    test mode and return the DG to a standby operation. The manual 
    operator action to reset the governor following the receipt of an 
    ECCS signal, continues to ensure that the equipment being powered by 
    the DG will perform its intended function. The proposed change 
    continues to ensure that the Division 3 DG will adequately support 
    its design basis performance and mitigative function during an 
    accident. Since the manual operator action performed during the test 
    mode ensures that the governor is reset upon receipt of an ECCS 
    signal, no analyses assumptions are violated and there are no 
    adverse effects on the factors that contribute to offsite or onsite 
    dose as the result of an accident. The proposed change does not 
    affect setpoints that initiate protective or mitigative actions. The 
    proposed change ensures that plant structures, systems, or 
    components are maintained consistent with the safety analysis and 
    licensing bases. Based on this evaluation, there is no significant 
    increase in the consequences of a previously analyzed event.
        Therefore, this change will not involve a significant increase 
    in the probability or consequences of any accident previously 
    evaluated.
        (2) The proposed change would not create the possibility of a 
    new or different kind of accident from any accident previously 
    evaluated.
        The proposed change revises the acceptance criteria for meeting 
    the ``ready-to-load'' requirement denoted by TS SR 3.8.1.17 for the 
    Division 3 DG. The proposed change also adds a discussion of this 
    acceptance criterion to the USAR to clarify the intent of the 
    requirement. The proposed change does not change the operating 
    characteristics or the safety function of the DG. The DG performs a 
    mitigative function. No new or
    
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    different equipment is being installed and no installed equipment, 
    which might initiate an analyzed event, is being operated in a 
    different manner. The proposed change does not impact core 
    reactivity or the manipulation of fuel bundles. There is no 
    alteration to the parameters within which the plant is normally 
    operated or in the setpoints that initiate protective or mitigative 
    actions. As a result no new failure modes are being introduced. 
    There are no changes in the methods governing normal plant 
    operation, nor are the methods utilized to respond to plant 
    transients altered.
        Therefore, the proposed change does not create the possibility 
    of a new or different kind of accident from any previously 
    evaluated.
        (3) The proposed change will not involve a significant reduction 
    in the margin of safety.
        The margin of safety is established through the design of the 
    plant structures, systems, and components, the parameters within 
    which the plant is operated, and the establishment of the setpoints 
    for the actuation of equipment relied upon to respond to an event. 
    The proposed change revises the acceptance criteria for meeting the 
    ``ready-to-load'' requirement denoted by TS SR 3.8.1.17 for the 
    Division 3 DG. The proposed change also adds a discussion of this 
    acceptance criterion to the USAR to clarify the intent of the 
    requirement. The proposed change allows manual operator action to 
    reset the governor upon receipt of an ECCS signal. This ensures that 
    appropriate frequency limits are obtained and that the Division 3 DG 
    can perform its intended function. Thus, the proposed change does 
    not significantly impact the condition or performance of structures, 
    systems, and components relied upon for accident mitigation. 
    Additionally, the proposed change does not significantly impact any 
    safety analysis assumptions or results.
        Therefore, the proposed 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 30 days of 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 October 13, 1998, 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 Vespasian Warner Public Library, 310 N. 
    Quincy Street, Clinton, IL 61727. 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
    
    [[Page 48531]]
    
    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 Leah Manning Stetzner, Vice 
    President, General Counsel, and Corporate Secretary, 500 South 27th 
    Street, Decatur, IL 62525, 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 August 24, 1998, 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 Vespasian Warner Public Library, 310 N. 
    Quincy Street, Clinton, IL 61727.
    
        Dated at Rockville, Maryland, this 2nd day of September 1998.
    
        For the Nuclear Regulatory Commission.
    Jon B. Hopkins,
    Senior Project Manager, Project Directorate III-3, Division of Reactor 
    Projects--III/IV, Office of Nuclear Reactor Regulation.
    [FR Doc. 98-24303 Filed 9-9-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
09/10/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
98-24303
Pages:
48529-48531 (3 pages)
Docket Numbers:
Docket No. 50-461
PDF File:
98-24303.pdf