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
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CFR Title: 

Content:
gulatory requirements for assessing, monitoring, and mitigating the aging effects on electrical equipment used in nuclear power generating stations. It endorses Institute of Electrical and Electronics Engineers (IEEE) Standard (Std.) 1205-2014, “IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities” (Ref. 1). Applicability This RG applies to licensees and applicants subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 2); 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 3); 10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants” (Ref. 4). With respect to 10 CFR Part 50, this RG applies to holders of or applicants for an operating license and / or holders of a renewed or subsequently renewed operating license. With respect to 10 CFR Part 52, this RG applies to holders of and applicants for combined licenses, standard design certifications, standard design approvals, and manufacturing licenses. With respect to 10 CFR Part 54, this RG applies to applicants for and holders of a renewed or subsequently renewed operating license. This RG does not apply to nuclear power plants that have submitted licensing termination certifications as required by 10 CFR 50.82(a)(1) and 10 CFR 52.110(a). Though the guidance primarily reflects past reviews of large light-water nuclear power plant applications, this RG may also provide useful guidance to fuel cycle, spent fuel storage, waste disposal facilities, and non-power production or utilization licensees. DG-1393, Page 2 Applicable Regulations • 10 CFR 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