Document: NRC Regulatory Guide
Document ID: d940ffea-1d07-4cc8-b0f2-64d5495912d7
Document Type: regulatory_guide
Title: Criteria for Power Systems for Nuclear Power Plants + HISTORY - HISTORY DG-1420 , Proposed Revision 4, published 08/2024 DG-1079 , Proposed Revision 3, published 04/2003 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2415/ML24158A060.pdf
Revision Date: 2024-08
Chapter: 
Section ID: RG-1.32
CFR Part: 
CFR Title: 

Content:
ctures, systems, and components important to safety be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. o GDC 5, “Sharing of structures, systems, and components,” requires that structures, systems, and components important to safety not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. o GDC 17, “Electric power systems,” requires, in part, an onsite and an offsite electric power system to permit functioning of certain structures, systems, and components. o GDC 18, “Inspection and testing of electric power systems,” requires, in part, that electric power systems important to safety be designed to permit appropriate periodic inspection and testing of important areas and features to assess the continuity of the systems and the condition of their components. • 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion XI, “Test Control,” requires, in part, that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will perform satisfactorily in service is identified and performed. • 10 CFR 50.55a, “Codes and standards,” requires, in part, that structures, systems, and components (SSCs) be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. Furthermore, 10 CFR 50.55a(h) provides requirements for protection and safety systems and incorporates by reference IEEE Std. 279-1968, “Proposed IEEE Criteria for Nuclear Power Plant Protection Systems” (Ref. 4), IEEE Std. 279-1971, “Criteria for