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:
-1362, Page 60 38. NRC, SECY-90-016, “Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationships to Current Regulatory Requirements,” Washington, DC, June 26, 1990. (ADAMS Accession No. ML003707885) 39. NRC, SECY-13-0029, “History of the Use and Consideration of the Large Release Frequency Metric by the U.S. Nuclear Regulatory Commission,” Washington, DC, March 22, 2013. (ADAMS Accession No. ML13022A207) 40. NRC, Staff Requirement Memorandum to SECY-12-0081, “Staff Requirements – SECY-12-0081 – Risk-Informed Regulatory Framework for New Reactors,” Washington, DC, October 22, 2012. (ADAMS Accession No. ML12296A158) 41. NRC, “Good Practices for Implementing Human Reliability Analysis (HRA),” NUREG-1792, Washington, DC, April 2005. (ADAMS Accession No. ML051160213) 42. NRC, “Evaluation of Human Reliability Analysis Methods Against Good Practices,” NUREG- 1842, Washington, DC, September 2006. (ADAMS Accession No. ML063200058) 43. CFR, “Backfitting,” Part 50, Chapter 1, Title 10, Section 50.109, “Energy” 44. NRC, Management Directive 8.4, “Management of Facility-Specific Backfitting and Information Collection,” Washington, DC. DG-1362, Appendix A, Page A-1 APPENDIX A NRC REGULATORY POSITION ON ASME/ANS RA-SA-2009 Introduction The American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS) previously published ASME/ANS RA-Sa-2009, “Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications” (Ref. 21). The standard states that it “sets forth requirements for probabilistic risk assessments (PRAs) used to support risk-informed decisions for commercial nuclear power plants, and describes a method for applying these requirements for specific applications.” The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed ASME/ANS RA-Sa-2009 against the characteristics and attributes of an acceptable PRA as discussed in regulatory positions C.1 and C.2 in Section C