Document: NRC Regulatory Guide
Document ID: 3b4c5897-7060-42e3-83a9-cf0790b7dc60
Document Type: regulatory_guide
Title: Acceptability of ASME Code, Section XI, Division 2, Requirements for RIM Programs for NPPs, for Non-LWRs
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2112/ML21120A185.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.246
CFR Part: 
CFR Title: 

Content:
evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as necessary to assure a quality product in keeping with the required safety function. • 10 CFR 50.55a incorporates by reference ASME Code Sections III, “Rules for Construction of Nuclear Facility Components,” (Ref. 4), Section XI, and the ASME Operation and Maintenance (OM) Code (Ref. 5), mandates that systems and components of boiling and pressurized water-cooled nuclear power reactors meet these codes, and provides conditions on their use. Although 10 CFR 50.55a is not currently applicable to non-LWRs, these codes and the NRC’s conditions on their use may be relevant guidance for non-LWRs, similar to the GDCs in Appendix A to 10 CFR Part 50. • RG 1.28, “Quality Assurance Program Criteria (Design and Construction)” (Ref. 6), provides guidance for the establishment and execution of Quality Assurance programs for nuclear power plants during their design and construction. • RG 1.193, “ASME Code Cases Not Approved for Use” (Ref. 7), lists the Code Cases for ASME Code, Section III, Section XI, and the ASME OM Code that the NRC has not approved for generic use in 10 CFR 50.55a. • RG 1.232, “Guidance for Developing Principal Design Criteria for Non-Light-Water Reactors” (Ref. 8), describes the NRC’s proposed guidance on how the GDCs in 10 CFR Part 50, Appendix A, may be adapted for non-LWR designs. DG-1383, Page 3 • 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. 9), describes the NRC’s proposed guidance on using a technology-inclusive, risk-informed, and performance-based methodology to inform the licensing basis and content of applications for non-LWRs, including, but not limited to, molten salt reactors, high-temperature gas-cooled reactors, and a