Document: NRC Regulatory Guide
Document ID: 3bd14847-40b5-4903-a0ae-9c2d5da42974
Document Type: regulatory_guide
Title: Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2322/ML23222A182.pdf
Revision Date: 2023-12
Chapter: 
Section ID: RG-1.30
CFR Part: 
CFR Title: 

Content:
safety. Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” to 10 CFR Part 50 establishes QA requirements for the design, manufacture, construction, and operation of those SSCs. The pertinent requirements of Appendix B to 10 CFR Part 50 apply to all activities affecting the safety-related functions of those SSCs. • 10 CFR Part 52.79(a) requires that an application for a combined license contain a final safety analysis report that describes the facility, presents the design bases and the limits on its operation, and presents a safety analysis of the structures, systems, and components of the facility as a whole. o 10 CFR 52.79(a)(10) requires that SSCs important to safety in a nuclear power plant be designed to accommodate the effects of environmental conditions and that design control measures, such as testing, be used to check the adequacy of the design. o 10 CFR 52.79(a)(15) requires an application for a combined license to contain a final safety analysis report that describes the program and its implementation for monitoring the effectiveness of maintenance necessary to meet the requirements of 10 CFR 50.65. Related Guidance • RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants” (Ref. 4), provides general guidelines for complying with 10 CFR 50.65(a)(1). • NUREG-1537, Parts 1 and 2, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors,” issued February 1996 (Ref. 5), contains format and content DG 1419, Page 3 guidance for non-power reactor applicants and licensees, as well as a standard review plan and acceptance criteria for NRC staff. • “Final Interim Staff Guidance Augmenting NUREG-1537, ‘Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors,’ Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors,” issued October 2012 (Ref. 6), updates and