Document: NRC Regulatory Guide
Document ID: acab976c-e936-49be-8c59-865767973599
Document Type: regulatory_guide
Title: Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2319/ML23194A194.pdf
Revision Date: 2023-09
Chapter: 
Section ID: RG-1.253
CFR Part: 
CFR Title: 

Content:
�� (Ref. 22), endorses with exceptions and clarifications the ASME/ANS RA-S-1.4-2021, “Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants,” (Ref. 23), guidance for non-LWR PRAs and endorses with no exceptions and clarifications the NEI 20-09, “Performance of PRA Peer Reviews Using the ASME/ANS Advanced Non-LWR PRA Standard” (Ref. 24), guidance on PRA peer reviews. RG 1.247 describes one approach acceptable to the NRC staff for determining whether a PRA used to support an application is sufficient to provide confidence in the results, such that the PRA can be used in regulatory decision making for non-LWRs. The NRC staff notes that additional guidance is being considered for development that would supplement the guidance in RG 1.247. Appendix A of this document identifies guidance that is being considered for development that could result in a revision of this Draft RG. References may be included to other SAR chapters that discuss the use of the PRA and its results (e.g., selection of LBEs, evaluation of LBE risk significance against the LMP frequency-consequence targets (Figure 3-1 of NEI 18-04, Revision 1), determination of integrated risk DG-1404, Revision 1, Page 15 and comparison to cumulative risk metrics, PRA uncertainties and assessment of DID adequacy, PRA safety functions, SSC safety classification, and reliability and capability targets).8 In Chapter 2 of an SAR following NEI 21-07, Revision 1, the applicant provides information on event sequence source terms specific to its design that is used in the LBE consequence analyses. The source term information should cover all radioactive material inventories and include the type, quantity, and timing of the release of radioactive material from the facility during LBEs. This chapter should include analysis methodologies, assumptions, bases, and justifications associated with transport of radioactive material from its point of origin to the accessible