Document: NRC Regulatory Guide
Document ID: ed595a39-2817-46a5-93dd-476899712ff9
Document Type: regulatory_guide
Title: 10/2017 (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1720/ML17207A293.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.28
CFR Part: 
CFR Title: 

Content:
SSCs of the facility that satisfies applicable portions of Appendix B to 10 CFR Part 50, as well as a discussion of how the applicable requirements of Appendix B to 10 CFR Part 50 were satisfied. o 10 CFR 52.79(a)(25) requires a combined license applicant to include description of the QA program, applied to the design, and to be applied to the fabrication, construction, and testing, of the SSCs of the facility, as well as a discussion of how the applicable requirements of Appendix B to 10 CFR Part 50 have been and will be satisfied, and how the quality assurance program will be implemented. o 10 CFR 52.137(a)(19) requires a standard design approval applicant to include a description of the QA program applied to the design of the SSCs of the facility, as well as a discussion of how the applicable requirements of Appendix B to 10 CFR Part 50 were satisfied. o 10 CFR 52.157(f)(17) requires a manufacturing license applicant to include a description of the QA program applied to the design, and to be applied to the manufacture of, the SSCs of the reactor, as well as a discussion of how the applicable requirements of Appendix B to 10 CFR Part 50 have been and will be satisfied. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants” (Ref. 3), Section 17.5, “Quality Assurance Program Description- Design Certification, Early Site Permit and New License Applicants,” provides guidance to the NRC staff in reviewing QA program descriptions submitted by applicants for a design certification, combined license, early site permit, construction permit, and operating license. • RG 1.33, “Quality Assurance Program Requirements (Operation)” (Ref. 4), addresses additional guidance for the establishment and execution of QA programs for nuclear power plants during the operations phase. Purpose of Regulatory Guides The NRC issues RGs to describe to the public methods that the staff considers acceptable for use