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:
.65 requires these goals to be established DG 1419, Page 2 commensurate with safety and, where practical, take into account industrywide operating experience. 10 CFR 50.65 also states that appropriate corrective action will be taken when the performance or condition of an SSC does not meet established goals. For a nuclear power plant for which the licensee has submitted the certifications specified in 10 CFR 50.82(a)(1) or 10 CFR 52.110(a)(1), as applicable, 10 CFR 50.65 only applies to the extent that the licensee monitor the performance or condition of all SSCs associated with the storage, control, and maintenance of spent nuclear fuel in a safe condition, in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions. o The general design criteria (GDC) in Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50 establish minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission. The GDC are also considered to be generally applicable to other types of nuclear power units and are intended to provide guidance in establishing the principal design criteria for such other units. The following GDC is related to quality assurance (QA): o GDC 1, “Quality standards and records,” requires, in part, that SSCs important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. o Nuclear power plants and fuel reprocessing plants include SSCs that prevent or mitigate the consequences of postulated accidents that could cause undue risk to public health and 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