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:
ubpart C of 10 CFR Part 52 that reference an SDA under Subpart E of 10 CFR Part 52 shall use and update the PRA 1 See the Background discussion in Section B of this RG for additional information about ongoing activities related to rulemakings for which the analysis described in this RG may inform applications to address those new or revised requirements. RG 1.247, Page 3 information for the SDA to account for site-specific design information and any design changes or departures. o 10 CFR 52.79(d)(1) requires that applicants for a COL under Subpart C of 10 CFR Part 52 that reference a standard DC under Subpart B shall use and update the PRA information for the standard DC to account for site-specific design information and any design changes or departures. o 10 CFR 52.79(e)(1) requires that applicants for a COL under Subpart C of 10 CFR Part 52 that reference the use of one or more manufactured nuclear power reactors licensed under Subpart F of 10 CFR Part 52 shall use and update the PRA information for the manufactured reactor to account for site-specific design information and any design changes or departures. o 10 CFR 52.137(a)(25) requires that applicants for an SDA under Subpart E of 10 CFR Part 52 shall include a description of the design-specific PRA and its results. o 10 CFR 52.157(a)(31) requires that applicants for an ML under Subpart F of 10 CFR Part 52 shall include a description of the design-specific PRA and its results. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (Ref. 4), provides guidance to the NRC staff in performing safety reviews of CP or OL applications (including requests for amendments) under 10 CFR Part 50 and ESP, DC, COL, SDA, and ML applications under 10 CFR Part 52 (including requests for amendments) for light water reactors (LWRs). o NUREG-0800, Section 19.1, “Determining the Technical Adequacy of Probabilistic Risk Assessment Results for