Document: NRC Regulatory Guide
Document ID: 9e5c28ce-3a04-491c-8c21-07d90622ba1b
Document Type: regulatory_guide
Title: Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2128/ML21288A115.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.248
CFR Part: 
CFR Title: 

Content:
Part 50 requires, among other things, that structures, systems, and components (SSCs) that are important to safety in a nuclear power plant must be designed to accommodate the effects of environmental conditions (i.e., remain functional under postulated design-basis events). o 10 CFR 50.34(b)(6)(iv) requires each application for an operating license to include a final safety analysis report that contains plans for conducting normal operations, including maintenance, surveillance, and periodic testing of SSCs. o 10 CFR 50.49(a), “Environmental qualification of electric equipment important to safety for nuclear power plants,” requires that holders of or applicants for an operating license issued under 10 CFR Part 50 or a combined license or a manufacturing license issued under 10 CFR Part 52 shall establish a program for the environmental qualification of electric equipment as defined in 10 CFR 50.49(b). For a manufacturing license (as defined in 10 CFR 52.157), only electric equipment defined in 10 CFR 50.49(b) that is within the scope of the manufactured reactor must be included in the program. o 10 CFR 50.65, “Requirements for monitoring the effectiveness of maintenance at nuclear power plants,” requires that each holder of an operating license for a nuclear power plant under 10 CFR Part 50 and each holder of a combined license under 10 CFR Part 52 (after the Commission makes the finding under 10 CFR 52.103(g)) shall monitor the performance or condition of SSCs against licensee-established goals, in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions. These goals shall be established commensurate with safety and, where practical, take into account industrywide operating experience. When the performance or condition of an SSC does not meet established goals, appropriate corrective action shall be taken. For a nuclear power plant for which the licensee has submitted the certifications