98-18685. Post-Fire Safe Shutdown Circuit Analysis Workshop  

  • [Federal Register Volume 63, Number 134 (Tuesday, July 14, 1998)]
    [Notices]
    [Pages 37909-37910]
    From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
    [FR Doc No: 98-18685]
    
    
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    NUCLEAR REGULATORY COMMISSION
    
    
    Post-Fire Safe Shutdown Circuit Analysis Workshop
    
    AGENCY: Nuclear Regulatory Commission.
    
    ACTION: Notice of meeting.
    
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    SUMMARY: The Nuclear Regulatory Commission staff is holding a workshop 
    to discuss with the nuclear industry and the public the status of post-
    fire safe shutdown circuit analysis and the implementation of circuit 
    analysis results at commercial nuclear reactors. A summary of the 
    questions and comments discussed at the workshop on post-fire safe 
    shutdown circuit analysis and of staff follow up plans and actions will 
    be generated by the staff and distributed to the registered 
    participants after the workshop.
    
    DATES: July 23, 1998, from 8:00 a.m.--5:00 p.m.
    
    ADDRESSES: Bethesda Marriott, 5151 Pookshill Road, Bethesda, MD 20814.
    
    FOR FURTHER INFORMATION CONTACT: Leon E. Whitney, Mail Stop O-8-D1, 
    U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. 
    Telephone (301) 415-3081; Internet: [email protected]
    
    SUPPLEMENTARY INFORMATION: The preliminary agenda for the proposed 
    workshop is:
    
    7:30-8:00
        Registration/Acceptance of Papers/Input from Industry and Public/
    Handout of Agenda
    8:00-8:10
        Introduction/Presentation of Agenda--Tad Marsh, Chief, Plant 
    Systems Branch, NRR
    8:10-8:20
        Discussion of Workshop Purpose--Brian Sheron, Acting Associate 
    Director for Technical Review
    8:20-8:25
        Introductory Remarks by a Public Representative
    8:30-8:30
        Introductory Remarks by an Industry Representative
    8:30-9:00
        NRC Presentation of U.S. Commercial Nuclear Reactor Plant Post-fire 
    Safe Shutdown Circuit Analysis History
    
    [[Page 37910]]
    
    and Safety Significance. NRC Discussion of the Potential Severity of 
    Fire-induced Reactor Plant Transients--NRR/SPLB, BNL
    9:00-9:15
        Summary of Industry Views of the Regulatory History of the Post-
    fire Safe Shutdown Circuit Analysis Issues--NEI
    9:15-9:30
        NRC Presentation of Post-fire Safe Shutdown Circuit Analysis Issues 
    as Recently Identified through Inspection, Licensing and Event 
    Experience--NRR/SPLB
    
    Break
    
    9:45-11:00
        Industry and Public Presentations on Selected Technical Topics 
    (five, 15 minute talks)
    11:00-12:00
        Public/Industry/NRC Panel Discussion on the Technical Issues 
    Addressed in Information Notice 92-18 on ``MOV Hot Shorts''.
    12:00-1:30
        Lunch Break
    1:30-2:30
        Public/Industry/NRC Panel Discussion on Circuit Analysis Fault 
    Terminology, and the Types of Assumptions Necessary Regarding Multiple 
    Spurious Electrical Faults, Signals and/or Actuations in a Single Fire.
    2:30-3:30
        Public/Industry/NRC Panel Discussion of the Scope of Necessary 
    Post-fire Safe Shutdown Circuit Analyses and Resultant Plant 
    Modifications--Likelihood and Consequences of Circuit Damage Which 
    Affects Post-fire Safe Shutdown Capability.
    
    Break
    
    3:45-4:45
        Question and Answer Session (NRC, public and industry 
    representatives on the dais).
    4:45-4:50
        Public Closing Remarks
    4:50-4:55
        Industry Closing Remarks
    4:55-5:00
        NRC Closing Remarks
    
        Individuals wishing to make a presentation at the workshop should 
    contact Leon Whitney directly. Individuals who wish to attend the 
    workshop are encouraged to notify Leon E. Whitney at (301) 415-3081; 
    Internet: [email protected] of their planned attendance.
    
        Dated at Rockville, Maryland this 8th day of July, 1998.
    
        For the Nuclear Regulatory Commission.
    K. Steven West,
    Acting Chief, Plant Systems Branch, Division of System Safety and 
    Analysis, Office of Nuclear Regulatory Regulation.
    [FR Doc. 98-18685 Filed 7-13-98; 8:45 am]
    BILLING CODE 7590-01-P
    
    
    

Document Information

Published:
07/14/1998
Department:
Nuclear Regulatory Commission
Entry Type:
Notice
Action:
Notice of meeting.
Document Number:
98-18685
Dates:
July 23, 1998, from 8:00 a.m.--5:00 p.m.
Pages:
37909-37910 (2 pages)
PDF File:
98-18685.pdf