97-20654. Advisory Committee on Reactor Safeguards; Joint Meeting of the ACRS Subcommittees on Probabilistic Risk Assessment, Plant Operations, and on Fire Protection; Notice of Meeting  

  • [Federal Register Volume 62, Number 151 (Wednesday, August 6, 1997)]
    [Notices]
    [Pages 42269-42270]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 97-20654]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    
    Advisory Committee on Reactor Safeguards; Joint Meeting of the 
    ACRS Subcommittees on Probabilistic Risk Assessment, Plant Operations, 
    and on Fire Protection; Notice of Meeting
    
        The ACRS Subcommittees on Probabilistic Risk Assessment, Plant 
    Operations, and on Fire Protection will hold a joint meeting on August 
    28 and 29, 1997, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland.
        The entire meeting will be open to public attendance.
        The agenda for the subject meeting shall be as follows:
    
    Thursday, August 28, 1997--8:30 a.m. until the conclusion of business
    Friday, August 29, 1997--8:30 a.m. until the conclusion of business
    
        The Subcommittees will continue their review of matters included in 
    the Staff Requirements Memorandum (SRM) dated May 27, 1997: (1) 
    Acceptance criteria for plant-specific safety goals and deriving lower-
    tier acceptance criteria; and (2) the use of uncertainty versus point 
    values in the PRA-related
    
    [[Page 42270]]
    
    decisionmaking process. The Subcommittees will review the proposed 
    action plan to improve the Senior Management Meeting process and the 
    voluntary approach proposed by the industry for reporting reliability 
    and availability information for risk-significant systems and 
    equipment. The Subcommittees will also review the NRC program for risk-
    based analysis of reactor operating experience, as well as the results 
    of special studies performed by the staff (e.g., auxiliary feedwater, 
    Westinghouse reactor protection systems, loss of offsite power, 
    initiating events, reactor core isolation cooling, high pressure core 
    injection, fire events, etc.). The purpose of this meeting is to gather 
    information, analyze relevant issues and facts, and to formulate 
    proposed positions and actions, as appropriate, for deliberation by the 
    full Committee.
        Oral statements may be presented by members of the public with the 
    concurrence of the Subcommittee Chairman; written statements will be 
    accepted and made available to the Committee. Electronic recordings 
    will be permitted only during those portions of the meeting that are 
    open to the public, and questions may be asked only by members of the 
    Subcommittees, their consultants, and staff. Persons desiring to make 
    oral statements should notify the cognizant ACRS staff engineer named 
    below five days prior to the meeting, if possible, so that appropriate 
    arrangements can be made.
        During the initial portion of the meeting, the Subcommittees, along 
    with any of their consultants who may be present, may exchange 
    preliminary views regarding matters to be considered during the balance 
    of the meeting.
        The Subcommittees will then hear presentations by and hold 
    discussions with representatives of the NRC staff, its consultants, and 
    other interested persons regarding this review.
        Further information regarding topics to be discussed, whether the 
    meeting has been cancelled or rescheduled, the Chairman's ruling on 
    requests for the opportunity to present oral statements and the time 
    allotted therefor can be obtained by contacting the cognizant ACRS 
    staff engineer, Mr. Michael T. Markley (telephone 301/415-6885) between 
    7:30 a.m. and 4:15 p.m. (EDT). Persons planning to attend this meeting 
    are urged to contact the above named individual one or two working days 
    prior to the meeting to be advised of any potential changes to the 
    agenda, etc., that may have occurred.
    
        Dated: July 31, 1997.
    Sam Duraiswamy,
    Chief, Nuclear Reactors Branch.
    [FR Doc. 97-20654 Filed 8-5-97; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
08/06/1997
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Document Number:
97-20654
Pages:
42269-42270 (2 pages)
PDF File:
97-20654.pdf