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          NRC Library  Document Collections  NUREG-Series Publications  Publications Prepared by NRC ContractorsPRA Procedures and Uncertainty for PTS Analysis (NUREG/CR-6859, SAND2004-5032P)

On this page: Publication Information AbstractDownload complete document NUREG/CR-6859 (PDF - 328.51 KB)Publication Information **Manuscript Completed:** October 2004**Date Published:** March 2010 **Prepared by:** D.W. Whitehead1 A.M. Kolaczkowski2 1Sandia National Laboratories P.O. Box 5800 Albuquerque, NM 87185-0744 2Science Applications International Corporation 405 Urban Street Suite 400 Lakewood, CO 80228 M.T. Kirk, NRC Project Manager Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission ****Washington, DC 20555-0001 NRC Job Code Y6430 Availability Notice Abstract This report supplements NUREG-1806, "Technical Basis for Revision of the Pressurized Thermal Shock (PTS) Screening Limit in the PTS Rule (10CFR50.61): Summary Report," with additional information regarding the Probabilistic Risk Assessment (PRA) and Human Reliability Analysis (HRA) portions of the PTS analyses presented in that report, including the use of realistic input values and models and an explicit treatment of uncertainties. Best estimate equipment failure values are used throughout based on generic nuclear industry data, or, in cases where it's available, on plant-specific data. Parameters related to human performance are based on plant specific review of procedures and training, observation of plant personnel responding to PTS-related sequences on their simulator, and performance data from actual plant operations. 
      
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