PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants: Chapters 9–13 and Appendices A–G (NUREG/CR-2300, Volume 2)
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- NUREG/CR-2300, Volume 2
Manuscript Completed: December 1982
Date Published: January 1983
J.W. Hickman, et al.
Prepared under the auspices of:
The American Nuclear Society
LaGrange Park, IL 60525
NRC Grant No. G-04-81-001
The Institute of Electrical and Electronics Engineers
New York, NY 10017
NRC Grant No. G-04-81-05
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
This procedures guide describes methods for performing probabilistic risk assessments (PRAs) for nuclear power plants at three levels of scope: (1) systems analysis; (2) systems and containment analysis; and (3) systems, containment, and consequence analysis. After reviewing its objectives and limitations, this document describes the organization and management of a PRA project and then presents procedures for accidentsequence definition and systems modeling, human-reliability analysis, the development of a data base, and the quantification of accident sequences. Procedures for evaluating the physical processes of core meltdown are presented next, followed by guidance on the evaluation of radionuclide releases from the containment as well as the analysis of environmental transport and offsite consequences. The analysis of external hazards is discussed next, including procedures for seismic, fire, and flood analyses. The guide concludes with suggestions for the development and interpretation of results and the performance of uncertainty analyses.