Document: NRC Regulatory Guide
Document ID: 0708f346-65c1-488f-bc1b-9296dfb9e37b
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:
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 specified in 10 CFR 50.82(a)(1) or 10 CFR 52.110(a)(1), as applicable, 10 CFR 50.65 shall only apply to the extent that the licensee shall monitor the performance or condition of all SSCs associated with the storage, control, and maintenance of spent fuel in a safe condition, in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions. o General Design Criterion 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. • 10 CFR Part 52 requires that SSCs important to safety in a nuclear power plant be designed to accommodate the effects of environmental conditions and that design control measures, such as testing, be used to check the adequacy of the design. o Under 10 CFR 52.79(a)(15), an application for a combined license shall contain a final safety analysis report that describes the program, and its implementation, for monitoring the effectiveness of maintenance necessary to meet the requirements of 10 CFR 50.65. o 10 CFR 52.137(a)(13) requires that an applicant for a standard design approval must provide the list of electric equipment that is important to safety as defined by 10 CFR 50.49(d). DG-1393, Page 3 • 10 CFR Part 54 provides the requirements for the issuance of renewed (or subsequently renewed) operating licenses and renewed (or subsequently renewed) combined licenses for nuclear power plants licensed in accordance with Sections 103 or 104b