Document: NRC Regulatory Guide
Document ID: cdc706d5-60ed-40a4-b55a-9771904107a7
Document Type: regulatory_guide
Title: Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1809/ML18093A675.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.100
CFR Part: 
CFR Title: 

Content:
postulated accidents that could cause undue risk to public health and safety. The pertinent requirements of Appendix B apply to all activities that affect the safety-related functions of those SSCs. o Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants,” to 10 CFR Part 50 requires that all NPPs must be designed to ensure that certain SSCs remain functional if the safe-shutdown earthquake (SSE) ground motion occurs. These SSCs are those that are necessary to ensure (1) the integrity of the reactor coolant pressure boundary; (2) the capability to shut down the reactor and maintain it in a safe shutdown condition; or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10 CFR 50.34(a)(1) or 10 CFR 100.11, “Determination of Exclusion Area, Low Population Zone, and Population Center Distance.” • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (SRP) (Ref. 3), provides guidance to the NRC staff for review of license applications for NPPs: o SRP Section 3.2.1, “Seismic Classification,” provides guidance to the NRC staff in reviewing the seismic classification of SSCs for NPP applications. o SRP Section 3.7.2, “Seismic System Analysis,” provides guidance to the NRC staff on an applicant’s seismic analysis methods (response spectrum analysis method, time history analysis method, or equivalent static load analysis method) for all seismic Category I SSCs. DG-1328, Page 3 o SRP Section 3.9.6, “Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints,” provides guidance to the NRC staff in reviewing