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:
metric). The characteristics and attributes of the PRA elements define specific criteria for successfully performing those technical analyses and achieving a defined objective. 4. Plant representation and PRA configuration control: Plant representation is defined in terms of how closely the PRA represents the plant as it is designed, built, and operated. In general, PRA results used to support CP applications should be derived from a PRA model that represents the as-designed, as-to-be-built, and as-to-be-operated plant. Consequently, the PRA should be developed using an acceptable configuration control process. The following sections provide guidance on these four interrelated areas of PRA acceptability and PRA documentation in the context of a CP application that is based on the LMP methodology. Consistent with NEI 18-04, Revision 1 and NEI 21-07, Revision 1, “Technology-Inclusive Guidance for Non-Light Water Reactors, Safety Analysis Report Content: For Applicants Using the NEI 18-04 Methodology” (Ref. B-4), and their endorsements in RG 1.233, “Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors” (Ref. B-5), and the main body of this RG, this appendix assumes that the CP applicant will use the American Society of Mechanical Engineers (ASME) and American Nuclear Society (ANS) non-LWR PRA standard, ASME/ANS RA-S-1.4-2021, “Probabilistic Risk Assessment Standard for Advanced Non-Light Water Reactor Nuclear Power Plants” (Ref. B-6), to demonstrate the acceptability of the PRA. CP applicants may use other approaches to demonstrate the acceptability of the PRA with appropriate justification; the NRC staff will review such an approach on a case-by-case basis. B.2 General B.2.1 As discussed in Section B of Appendix A to DANU-ISG-2022-01, “Review of Risk-Informed, Technology-Inclusive Advanced