Risk-Informed Decision Making in Generic Safety Issue Resolution and Rulemaking

  • S. D. Weerakkody
Conference paper


This paper discusses several major issues the U.S. Nuclear Regulatory Commission (USNRC) has risk-informed in its regulatory actions. The major issues discussed are:
  1. 1

    GSI-189: “Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion during Severe Accidents.”

  2. 2

    GSI-191: “Assessment of Debris Accumulation on PWR Sump Performance.”

  3. 3

    10 CFR 50.48 (c) or NFPA 805 Rule. The NFPA 805 standard is titled “Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants.”

  4. 4

    Risk-informing circuit analysis.



Fire Protection Nuclear Reactor Regulation Electric Power Research Institute Pressurize Water Reactor Severe Accident 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.


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  1. 1.
    Federal Register Notice 60 FR 42623, Use of Probabilistic Methods in Nuclear Regulatory Activities; Final Policy Statement. 16 August 1995Google Scholar
  2. 2.
    Regulatory Guide 1.174, An Approach for using Probabilistic Risk Assessment in Risk-Informed Decisions On Plant-Specific Changes to the Licensing Basis. US Nuclear Regulatory Commission. November 2002Google Scholar
  3. 3.
    10 CFR 50.44, Combustible Gas Control for Nuclear Power ReactorsGoogle Scholar
  4. 4.
    Backup Power for PWRs with Ice Condenser Containments and for BWRs with Mark III Containments under SBO conditions: Impact Assessments. US NRC, 2002Google Scholar
  5. 5.
    NUREG/BR-0058, Regulatory Analysis Guidelines of the US Nuclear Regulatory Commission. July 2000Google Scholar
  6. 6.
    SRM-SECY-00-198, Status Report on Study of Risk-Informed Changes to the Technical Requirements of 10 CFR 50 (Option 3) and Recommendations on Risk-Informed Changes to 10 CFR 50.44 (Combustible Gas Control). 19 January 2001Google Scholar
  7. 7.
    Thadani, A. Memorandum to S. Collins, RES Proposed Recommendation for Resolving Generic Safety Issue 189: Susceptibility of Ice Condenser and Mark III Containments to Early Failure from Hydrogen Combustion during a Severe Accident. 17 December 2002Google Scholar
  8. 8.
    Lehner J, Vinod M, Pratt WT, Conrad C. Benefit Cost Analysis of Enhancing Combustible Gas Control Availability at Ice Condenser and Mark III Containment Plants. Technical Letter Report, Brookhaven National Laboratory, 2002Google Scholar
  9. 9.
    10 CFR 50.109, BackfittingGoogle Scholar
  10. 10.
    US NRC Information Notice 92-71, Partial Plugging of Suppression Pool Strainers at a Foreign BWR, 30 September 1992Google Scholar
  11. 11.
    US NRC Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-water Reactors, 6 May 1996Google Scholar
  12. 12.
    Rao DV, Letellier B, Shaffer C, Ashbaugh S, Bartlein L. GSI-191: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance, Technical Letter Report LA-UR-01-4083, Los Alamos National Laboratory, 2001Google Scholar
  13. 13.
    NUREG/CR-6762, Technical Assessment: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance, Technical Letter Report LA-UR-01-4083, Volumes 1-4, USNRC, 2002Google Scholar
  14. 14.
    Darby JL, Thomas W, Rao DV, Letellier B, Ashbaugh S, Leonard MT. NUREG/CR-6771, GSI-191: The Impact of Debris Induced Loss of ECCS Recirculation on PWR Core Damage Frequency, Technical Letter Report LA-UR-02-0279, US NRC, 2001Google Scholar
  15. 15.
    Kern KT, Thomas W. The Impact of Recovery from Debris-Induced Loss of ECCS Recirculation on PWR Core Damage Frequency. Technical Letter Report LA-UR-02-7562, Los Alamos National Laboratory, 2003Google Scholar
  16. 16.
    US NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors, 9 June 2003Google Scholar
  17. 17.
    National Fire Protection Association (NFPA). NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors. NFPA, Quincy, 2001Google Scholar
  18. 18.
    SRM-SECY-00-009, Rulemaking Plan, Reactor Fire Protection Risk-Informed, Performance-Based Rulemaking, 24 February 2000Google Scholar
  19. 19.
    67 FR 66578, Voluntary Fire Protection Requirements for Light Water Reactors; Adoption of NFPA 805 as a Risk-informed, Performance-based Alternative, RIN 3150-AG48, 2002.Google Scholar
  20. 20.
    Nuclear Energy Institute (NEI). Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program Under 10CFR 50.48 (c), NEI 04-01, Revision D, 2003.Google Scholar
  21. 21.
    US NRC Enforcement Guidance Memorandum (EGM) 98-002, Disposition of Violations of Appendix R, Sections III.G and III.L Regarding Circuit Failures, 2 February 2000Google Scholar
  22. 22.
    US NRC Regulatory Issue Summary (RIS) 2003-XX, Risk-Informed Inspection Guidance for Post-Fire Safe-Shutdown Inspections, draft for public comment, 2003.Google Scholar
  23. 23.
    Electric Power Research Institute (EPRI). Characterization of Fire-Induced Circuit Faults. EPRI Report 1003326, EPRI, Palo Alto, CA, 2002Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • S. D. Weerakkody
    • 1
  1. 1.United States Nuclear Regulatory CommissionUSA

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