Abstract
In 1995, the U.S. Nuclear Regulatory Commission (NRC) issued a Policy Statement [1] on the use of probabilistic risk analysis (PRA), encouraging its use in all regulatory matters. The Policy Statement states that “…the use of PRA technology should be increased to the extent supported by the state of the art in PRA methods and data and in a manner that complements the NRC’s deterministic approachI’ Since that time, many uses have been implemented or undertaken, including modification of NRC’s reactor safety inspection program and initiation of work to modify reactor safety regulations. Consequently, confidence in the information derived from a PRA is an important issue: the accuracy of the technical content must be sufficient to justify the specific results and insights that are used to support the decision under consideration.
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References
USNRC, “Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement,” Federal Register, Vol. 60, p. 42622 (60 FR 42622), August 16, 1995.
USNRC, “An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,” Regulatory Guide 1.200 for Trial Use, February 2003.
USNRC, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Regulatory Guide 1.174, Revision 1, November 2002.
USNRC, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing,” Regulatory Guide 1.175, August 1998.
USNRC, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Inspection of Piping,” Regulatory Guide 1.178, Revision 1, September 2003.
USNRC, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance,” Regulatory Guide 1.176, August 1998.
USNRC, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications,” Regulatory Guide 1.177, August 1998.
American Society of Mechanical Engineers, “Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications,” ASME RA-S-2002, April 5, 2002 and Addenda A, RA-Sa-2003, December 2003.
Nuclear Energy Institute, “Probabilistic Risk Assessment Peer Review Process Guidance,” NEI-00-02, Revision A3, March 20, 2000.
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© 2004 Springer-Verlag London
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Drouin, M., Parry, G. (2004). Addressing the Issue of PRA Quality. In: Spitzer, C., Schmocker, U., Dang, V.N. (eds) Probabilistic Safety Assessment and Management. Springer, London. https://doi.org/10.1007/978-0-85729-410-4_345
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DOI: https://doi.org/10.1007/978-0-85729-410-4_345
Publisher Name: Springer, London
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