Document: NRC Regulatory Guide
Document ID: 8a2332d3-66ca-40af-84e1-507db8b26559
Document Type: regulatory_guide
Title: TRIAL - Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2123/ML21235A008.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.247
CFR Part: 
CFR Title: 

Content:
ped and documented in NEI 20-09, Revision 1, which provides guidance on how to perform a PRA peer review to meet the PRA peer review requirements in the ASME/ANS NLWR PRA standard. Regulatory Position C.2.2 of this RG provides guidance on the performance of PRA peer reviews and endorses NEI 20-09, Revision 1, in its entirety and with no exceptions as a means of satisfying the peer review requirements in the ASME/ANS NLWR PRA standard, as endorsed by the NRC in this RG. NEI 20-09, Revision 1, is based on a related industry PRA peer review guidance document, NEI 17-07, Revision 2, “Performance of PRA Peer Reviews Using the ASME/ANS PRA Standard,” issued August 2019 (Ref. 21), as well as other earlier, related industry guidance documents. Reactor owners’ groups and other industry organizations have been applying the PRA peer review process for several years, domestically and internationally. Consistent with the scope of the ASME/ANS NLWR PRA standard, NEI 20-09, Revision 1, addresses PRA peer reviews for an NLWR PRA that considers all radiological sources, all hazards, all POSs, and all levels of PRA analysis. Figure 1 illustrates the three, co-dependent aspects involved in achieving PRA acceptability. RG 1.247, Page 11 Figure 1. NRC general framework for achieving PRA acceptability Initial licensing application activities generally refer to any one or more of the types of applications listed in the Applicability section of this RG. The NRC staff notes that current regulations do not require applicants for CPs or OLs under 10 CFR Part 50 to provide PRA-related information. However, the following should be noted: • The Commission’s severe accident policy statement (Ref. 22) articulates the Commission’s determination that all new nuclear power plant designs can be shown to be acceptable for severe accident concerns, in part, by completing a PRA and considering the severe accident vulnerabilities the PRA exposes, along with the insights that it may add to the