PRA Procedures and Uncertainty for PTS Analysis (NUREG/CR-6859, SAND2004-5032P)

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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


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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