Document: NRC Regulatory Guide
Document ID: 848f45be-3c4b-4f6d-a9da-73ea5383e905
Document Type: regulatory_guide
Title: Qualification of Safety-Related Battery Chargers and Inverters for Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2216/ML22160A570.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.210
CFR Part: 
CFR Title: 

Content:
gn approvals, design certifications, and combined licenses under 10 CFR Part 52, were filed on or after May 13, 1999. The system criteria identified in this standard, include the qualification for the safety system equipment to demonstrate that the equipment can perform its safety functions as specified in the design basis. o 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants”:  General Design Criterion (GDC) 1, “Quality standards and records,” requires that structures, systems, and components (SSCs) important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.  GDC 2, “Design bases for protection against natural phenomena,” requires that SSCs important to safety be “designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions.”  GDC 4, “Environmental and dynamic effects design bases,” requires that SSCs important to safety be “designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents.” o 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion III, “Design Control,” Criterion XI, “Test Control,” and Criterion XVII, “Quality Assurance Records,” require design control measures to verify the adequacy of the design, a test program to assure that all testing required to demonstrate that SSCs will perform satisfactorily in service is performed in accordance with written procedures, and the maintenance of sufficient records as evidence of quality assurance activities, respectively. Criterion III specifically requires that a test program used to verify the