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:
plement the guidance found in RG 1.247 for trial use. Key to the approach in RG 1.247 for trial use is the development of frequency consequence criteria. While guidance for DG-1404, Revision 1, App A, Page 2 Item # Draft Document Being Considered for Possible Update Comments the treatment of uncertainty for the frequency of an event is considered sufficient, the staff is considering the development of additional guidance for the treatment of uncertainty in consequence evaluations. 5 DANU-ISG-2023-01, “Material Compatibility” The guidance DANU-ISG-2023-01, “Material Compatibility” would identify areas of review that could be necessary in a submittal seeking to use materials that would be allowed under American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section III, “Rule for the Construction of Nuclear Facility Components,” Division 5, “High Temperature Reactors” (Section III-5) (ASME, 2017). Section III-5 would specify the mechanical properties and allowable stresses to be used for design of components in high temperature reactors (HTRs). However, as stated in Section III-5, HBB 1110(g), the rules do not provide methods to evaluate deterioration that may occur in service as a result of corrosion, mass transfer phenomena, radiation effects, or other material instabilities. This ISG would identify information that should be included in non-LWR applications to satisfy applicable design requirements including qualification and monitoring programs for safety-significant structures, systems, and components (SSCs). DG-1404, Revision 1, App. B, Page 1 Appendix B Acceptability of a Probabilistic Risk Assessment That Supports a Non-Light-Water Reactor Construction Permit Application Based on the Licensing Modernization Project Methodology B.1 Introduction This appendix provides supplemental guidance on one approach that is acceptable to the U.S. Nuclear Regulatory Commission (NRC) staff for preparing a probabilistic