Document: NRC Regulatory Guide
Document ID: e16da529-b6b4-4fdf-bc3f-7490180363f3
Document Type: regulatory_guide
Title: Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2018/ML20183A423.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.89
CFR Part: 
CFR Title: 

Content:
issued under Part 50 shall establish a program for the EQ of electric equipment as defined in 10 CFR 50.49. o 10 CFR 50.55a(h), “Protection and safety systems,” states that protection systems must meet the requirements of the IEEE Std. 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations” (Ref. 4), or IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations” (Ref. 5), contingent on the date of construction permit issuance. The design basis criteria identified in those standards or, for plants with construction permits issued before January 1, 1971, the criteria identified in the licensing basis for such facilities, include the range of transient and steady state environmental conditions during normal, abnormal, and accident conditions during which the equipment must perform its safety functions. o General Design Criterion (GDC) 4, “Environmental and dynamic effects design bases,” of Appendix A, “General Design Criteria for Nuclear Power Plants,” to 10 CFR Part 50, states, in part, that SSCs important to safety shall 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 General requirements associated with equipment qualification appear in GDC 1, “Quality Standards and Records,” GDC 2, “Design Bases for Protection Against Natural Phenomena,” and GDC 23, “Protection System Failure Modes,” of Appendix A to 10 CFR Part 50. o Criterion III, “Design Control,” Criterion XI, “Test Control,” and Criterion XVII, “Quality Assurance Records,” of Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants” to 10 CFR Part 50 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