Document: NUREG-0800
Document ID: f60cdc8f-3c25-45c3-a1d3-b0f530961625
Document Type: srp
Title: DETERMINING THE TECHNICAL ADEQUACY OF PROBABILISTIC RISK
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1219/ML12193A107.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.1
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tainty The reviewer should not approve this portion of the analysis in the application unless the reviewer is satisfied that the key assumptions and key sources of uncertainty identified as having the potential to significantly impact the particular PRA results have been characterized in an acceptable manner given the current state of knowledge, and that the characterization has taken into account the results of the peer review. V. IMPLEMENTATION This SRP is intended to be used in conjunction with, and in support of, an application-specific SRP such as SRP Section 19.0, Section 19.2, Section 16.1, Section 9.5.1.2, Section 3.9.7, or Section 3.9.8. VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 2. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 3. American Society of Mechanical Engineers/American Nuclear Society. “Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications,” Revision 1, ASME RA-S-2002. ASME/ANS RA-S-2008. ASME: New York, NY. ANS: La Grange Park, IL. April 2008. 4 In the ASME/ANS PRA Standard (Reference 4) a source of model uncertainty is labeled “key” when it could impact the PRA results that are being used in a decision, and consequently, may influence the decision being made. 19.1- 10 Rev. 3 – September 2012 4. American Society of Mechanical Engineers/American Nuclear Society. “Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications,” Addendum A to ASME/ANS RA-S-2008. ASME/ANS RA-Sa-2009, ASME: New York, NY. ANS: La Grange Park, IL. February 2009. 5. Nuclear Energy Institute. “Probabilistic Risk Assessment (PRA) Peer Review Process Guidance.” Revision A3, NEI 00-02. NEI: Washington, DC. March 20, 2000. 6. Nuclear Energy Institute. “Process for Performing Follow-On PRA Peer Reviews Using the ASME PRA Standard.” Revision 2,