Document: NRC Regulatory Guide
Document ID: a1541707-8144-409c-8842-4ea7d4b8ef4e
Document Type: regulatory_guide
Title: 10/2019 (Rev. 19)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1912/ML19128A244.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.147
CFR Part: 
CFR Title: 

Content:
ME BPV Code provisions that are incorporated by reference into Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2). Applicability This RG applies to reactor licensees subject to 10 CFR Part 50, Section 50.55a, “Codes and standards.” Applicable Rules and Regulations • 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. RG 1.147, Rev. 19, Page 2 • 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 practical quality standards. • 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants,” requires, in part, a program for the inspection of activities that affect quality to verify its conformance with documented instructions and procedures. • 10 CFR 50.55a(g) requires, in part, that Class 1, 2, 3, metal containment (MC), and concrete containment (CC) components and their supports meet the requirements of ASME BPV Code, Section XI, or equivalent quality standards. • 10 CFR 52.79(a)(11) (Ref. 3) requires the final safety analysis report to include “a description of the program(s), and their implementation, necessary to ensure that the