Document: NRC Regulatory Guide
Document ID: 22ccfd5e-c5d8-4615-a02c-32369aa9f533
Document Type: regulatory_guide
Title: Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1930/ML19308B636.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.200
CFR Part: 
CFR Title: 

Content:
ose 95 percent of the CDF or the LERF/LRF, or that individually contribute more than 1 percent to the CDF or LERF/LRF. This set of risk significant accident sequences may be defined functionally or in terms of systems. significant basic event/contributor A basic event (i.e., equipment unavailabilities and HFEs) or risk contributor is considered significant when its Fussell-Vesely importance measure value is greater than 0.005 or the risk-achievement worth importance measure value is greater than 2. state of practice See definition for current good practice. DG-1362, Page 57 REFERENCES 5 1. NRC, “Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement,” Federal Register, Volume 60, No. 158: pp. 42622, (60 FR 42622), Washington, DC, August 16, 1995. 2. U.S. Code of Federal Regulations (CFR), “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy.” 3. CFR, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52, Chapter 1, Title 10, “Energy.” 4. U.S. Nuclear Regulatory Commission (NRC), NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” Chapter 19.1, “Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,” Washington, DC. 5. NRC, NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” Chapter 19.0, “Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,” Washington, DC. 6. NRC, NUREG-1855, “Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decisionmaking,” Washington, DC. 7. NRC, RG 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” Washington, DC. 8. NRC, RG 1.175, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice