Document: NRC Regulatory Guide
Document ID: 1bd47be4-b79c-4108-b744-3e7d400266e8
Document Type: regulatory_guide
Title: ASME Code Cases Approved for Use Without Conditions (Rev. 0)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2509/ML25091A013.pdf
Revision Date: 2025-09
Chapter: 
Section ID: RG-1.262
CFR Part: 
CFR Title: 

Content:
uction and Utilization Facilities” (Ref. 1): o General Design Criterion (GDC) 1, “Quality Standards and Records,” of Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 requires, in part, that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed. Where generally recognized codes and standards are used, GDC 1 requires that they be identified and evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as necessary to ensure a quality product in keeping with the required safety function. o 10 CFR Part 50, Appendix A, GDC 30, “Quality of Reactor Coolant Pressure Boundary,” requires, in part, that components that are part of the reactor coolant pressure boundary be designed, fabricated, erected, and tested to the highest quality standards practical. o 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” requires, in part, that measures be established for the control of special processing of materials and that proper testing be performed. RG 1.262, Page 2 o 10 CFR 50.55a(c) requires, in part, that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested in accordance with the requirements for Class 1 components of Section III, “Rules for Construction of Nuclear Power Plant Components,” of the ASME Boiler and Pressure Vessel (BPV) Code (Ref. 2). o 10 CFR 50.55a(f) requires, in part, that Class 1, 2, and 3 components and their supports meet the requirements of the ASME Operation and Maintenance (OM) Code (Ref. 3). o 10 CFR 50.55a(g) requires, in part, that Class 1, 2, and 3 metal containment (MC), and concrete containment (CC) components and their supports meet the requirements of Section XI, “Rules for Inservice Inspection of Nuclear Power