94-21767. Georgia Power Company, et al; 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 59, Number 170 (Friday, September 2, 1994)]
    [Notices]
    [Page 0]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 94-21767]
    
    
    [[Page Unknown]]
    
    [Federal Register: September 2, 1994]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    [Docket Nos. 50-424 and 425]
    
     
    
    Georgia Power Company, et al; 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 Nos. 
    NPF-68 and NPF-81 issued to Georgia Power Company, Ogelthorpe Power 
    Corporation Municipal Electric Authority of Georgia, City of Dalton, 
    Georgia (the licensee) for operation of the Vogtle Electric Generating 
    Plant, Units 1 and 2, located in Burke County, Georgia.
        The proposed amendment will relocate the requirements of Technical 
    Specification 3/4.7.10, Area Temperature Monitoring, to section 16.3 of 
    the VEGP Final Safety Analysis Report (FSAR). With this relocation to 
    the FSAR, GPC plans to clarify the basis for areas to be monitored and 
    modify these surveillance requirements. This change is being proposed 
    in accordance with NUREG-1431, ``Standard Technical Specifications, 
    Westinghouse Plants.''
        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 purpose of area temperature monitoring is to provide reasonable 
    assurance that the normal operating temperatures in the selected rooms 
    will remain consistent with the temperatures assumed for the 
    environmental qualification of safety related equipment.
        The normal operating temperature is significant for its effect on 
    the qualified life of the components as well as the predicted 
    environmental transients (i.e., pressure, temperature, and radiation) 
    that occur under accident conditions. The following justifications are 
    provided for the proposed changes to the area temperature monitoring 
    program:
        1. The proposed change to perform temperature surveillance only 
    when the normal ventilation system is out of service is justified based 
    on the following:
        a. The HVAC systems at VEGP have been designed to maintain the room 
    temperatures at less than the maximum normal temperature specified for 
    environmental qualification purposes. The HVAC calculations have 
    conservatively considered the worst case heat load conditions with a 
    nominal safety factor when sizing the cooling systems that serve the 
    subject rooms. As a result, the plant is generally maintained at 
    temperatures well below the level assumed for normal operation and used 
    for environmental qualification of equipment.
        b. Temperature monitoring activities per Technical Specification 3/
    4.7.10 have been in place for 6 years on Unit 1 and 4 years on Unit 2. 
    The data collected during this time demonstrate that the temperatures 
    have remained well within environmental qualification limits with the 
    exception of the main steam isolation valve (MSIV) area which has 
    exceeded its reportability limits on several occasions. The MSIV area 
    has since been provided with a new ventilation system and temperature 
    monitoring instrumentation.
        When the normal ventilation system for one of the specified rooms 
    is not functioning, temperature monitoring activities will resume at 
    the previously specified rate of once every 12 hours. The proposed 
    change to monitor these rooms only when the normal ventilation system 
    is out of service will provide a level of assurance that is similar to 
    that provided by the current Technical Specification. Therefore, 
    continued monitoring is not warranted as long as the normal ventilation 
    systems are functioning.
        2. The proposed change in room selection criteria to eliminate 
    rooms that are classified as mild environment is justified based on the 
    current methods of environmental qualification. The qualified life of 
    safety related equipment in mild environment is no longer based on 
    environmental qualification, but is based on a combination of design 
    life, trending, and periodic maintenance and surveillance as discussed 
    in FSAR section 3.11.B. Therefore, the monitoring of mild rooms is not 
    required to verify that the normal design temperature is being 
    maintained. However, the existing Technical Specifications not only 
    require monitoring of the normal room temperature, but also require 
    actions to evaluate equipment operability if an abnormal condition 
    temperature limit is exceeded.
        To address this abnormal temperature condition, the rooms that are 
    not monitored based on mild environment will not exceed 150 deg.F 
    following a complete loss of normal HVAC for a 7-day period.\1\ The 
    abnormal temperature limits currently shown in the Technical 
    Specifications are the calculated room temperatures with a loss of 
    normal HVAC for a 24-hour period. The new criterion is based on an 
    equipment qualification analysis that demonstrates that short duration 
    temperature excursions of up to 24 hours at 150 deg.F have an 
    insignificant effect on the qualified life of electrical and mechanical 
    equipment. The limitation is further supported by Appendix F of NUMARC 
    Report 87-00 that concludes that electrical and mechanical equipment 
    will operate in station blackout conditions with no loss of function 
    with temperatures of up to 150 deg.F for short durations (i.e., 4 
    hours).
    
        \1\Per project calculations, the loss of normal HVAC for 7 days 
    has been shown to be sufficient time to achieve steady state 
    temperature conditions.
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        3. Relocation of area temperature monitoring to the FSAR and the 
    revision of the TS reporting requirements are justified as follows:
        a. As discussed in enclosure 1 [of the licensee's February 3, 1994 
    submittal], the existing TS requirements for the area temperature 
    monitoring program do not meet any of the criteria of the Final Policy 
    Statement on Technical Specification Improvements for Nuclear Power 
    Reactors and can safely be relocated to the FSAR.
        b. The area temperature monitoring program added to the FSAR will 
    continue to ensure that room temperatures are maintained within the 
    limits assumed for environmental qualification. The monitoring 
    requirements of once every 12 hours when the normal ventilation system 
    is not in service will ensure that a room would not experience a short 
    duration temperature excursion for more than 24 hours without an 
    evaluation of equipment operability. Although reporting requirements 
    have been excluded from the FSAR description, an evaluation of 
    equipment operability will continue to be performed in the event that 
    the temperature limits are exceeded. The reporting of operability 
    concerns to the NRC will be based on the reporting requirements for the 
    specific equipment in an affected area after a determination of 
    operability has been made. The current TS requires that a report be 
    prepared and submitted to the NRC that demonstrates the continued 
    operability of the affected equipment if the maximum normal temperature 
    in an area is exceeded for more than 8 hours.
        The new FSAR description will continue to require an evaluation of 
    equipment operability if either the normal temperature limit or 
    abnormal condition temperature limit is exceeded. However, no report to 
    the NRC will be required unless the equipment operability evaluation 
    indicates a reportable condition.
        Based on the above considerations, GPC has concluded the following 
    concerning 10 CFR 50.92.
        1. The proposed change to the Technical Specifications does not 
    involve a significant increase in the probability or consequences of an 
    accident previously evaluated. The environmental qualification and 
    operability of the safety related equipment will not be adversely 
    affected by the proposed changes to the area temperature monitoring 
    program. The relocation of TS to the FSAR and the changes to monitoring 
    frequency will not increase the probability that the room temperature 
    design limits will be exceeded or result in a loss of qualified life of 
    safety related equipment. In addition, the consequences of exceeding 
    the temperature limits will not significantly differ from the existing 
    program since an evaluation of qualified life and operability will 
    continue to be performed.
        2. The proposed change to the Technical Specifications does not 
    create the possibility of a new or different kind of accident from any 
    accident previously evaluated. The relocation of area temperature 
    monitoring to the FSAR and the changes in monitoring procedures do not 
    change the design of individual equipment, systems, nor the plant 
    operating procedures and therefore will not create the possibility of a 
    new or different kind of accident from those already evaluated.
        3. The proposed change to the Technical Specifications does not 
    involve a significant reduction in the margin of safety because the 
    revised monitoring requirements will continue to ensure that the 
    environmental qualification temperature limits of safety related 
    equipment scoped in the area temperature monitoring program will not be 
    exceeded without an evaluation of equipment operability.
        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 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 
    20555.
        The filing of requests for hearing and petitions for leave to 
    intervene is discussed below.
        By October 3, 1994, 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 20555 and at the local 
    public document room located at Burke County Public Library, 412 Fourth 
    Street, Waynesboro, Georgia 30830. 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 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 20555, 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 Herbert N. Berkow: 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 Arthur H. 
    Domby, Troutman Sanders, Nations Bank Plaza, 600 Peachtree Street, NE., 
    Atlanta, Georgia 30308, 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 February 3, 1994, which is available 
    for public inspection at the Commission's Public Document Room, the 
    Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the 
    local public document room located at the Burke County Public Library, 
    412 Fourth Street, Waynesboro, Georgia 30830.
    
        Dated at Rockville, Maryland, this 29th day of August, 1994.
    
        For the Nuclear Regulatory Commission.
    Louis Wheeler,
    Project Manager, Project Directorate II-3, Division of Reactor 
    Projects--I/II, Office of Nuclear Reactor Regulation.
    [FR Doc. 94-21767 Filed 9-1-94; 8:45 am]
    BILLING CODE 7590-01-M
    
    
    

Document Information

Published:
09/02/1994
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
94-21767
Pages:
0-0 (1 pages)
Docket Numbers:
Federal Register: September 2, 1994, Docket Nos. 50-424 and 425