Document: NRC Regulatory Guide
Document ID: 82659041-98b0-4721-b25d-c4fb2ea394d0
Document Type: regulatory_guide
Title: An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1635/ML16358A153.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.174
CFR Part: 
CFR Title: 

Content:
�An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications,” Washington DC. 33. NRC, RG 1.178, “An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Inspection of Piping,” Washington, DC. 34. NRC, RG 1.201, “Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance,” Washington, DC. 35. NRC, SRM on SECY-04-0118, “Plan for the Implementation of the Commission’s Phased Approach to Probabilistic Risk Assessment Quality,” Washington, DC, October 6, 2004. (ADAMS Accession No. ML042800369) 36. G. Apostolakis and S. Kaplan, “Pitfalls in Risk Calculations,” Reliability Engineering, Vol. 2, pp. 135–145, 1981.6 37. NRC, NUREG-CR-5485, “Guidance on Modeling Common-Cause Failures in Probabilistic Risk Assessment,” Washington, DC. 38. CFR, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Part 50, Chapter 1, Title 10, Appendix B, “Energy” 39. CFR, “Conditions of license,” Part 50, Chapter 1, Title 10, Section 50.54, “Energy” 40. CFR, “Notice for public comment; State consultation,” Part 50, Chapter 1, Title 10, Section 50.91, “Energy” 41. CFR, “Written communications,” Part 50, Chapter 1, Title 10, Section 50.4, “Energy” 42. NRC, RG 1.33, “Quality Assurance Program Requirements (Operation),” Washington, DC. 6 Copies of the non-NRC documents included in these references may be obtained directly from the publishing organization. This document may be found at http://www.sciencedirect.com. DG-1285, Page 50 43. CFR, “Standards for Protection Against Radiation,” Part 20, Chapter 1, Title 10, “Energy” 44. CFR, “Reactor Site Criteria,” Part 100, Chapter 1, Title 10, “Energy” 45. NRC, Management Directive 8.4, “Management of Facility-Specific Backfitting and Information Collection,” Washington, DC. 46. NRC, NUREG-1409, “Backfitting Guidelines,”