Document: NRC Regulatory Guide
Document ID: 1f8fd3ff-bc9e-4b84-b4d9-71d2a51882f7
Document Type: regulatory_guide
Title: Seismic Design Classification for Nuclear Power Plants + HISTORY - HISTORY DG-1315 , Proposed Revision 5, published 09/2015 DG-1156 , Proposed Revision 4, published 10/2006 (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1506/ML15061A048.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.29
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CFR Title: 

Content:
ders acceptable for use in identifying and classifying those features of light- water-reactor (LWR) nuclear power plants that must be designed to withstand the effects of the safe- shutdown earthquake (SSE). Applicable Regulations • Title 10, Part 50, of the Code of Federal Regulations (10 CFR 50) “Domestic Licensing of Production and Utilization Facilities,” (Ref. 1), provides for the licensing of production and utilization facilities. o Appendix A to 10 CFR Part 50, “General Design Criteria for Nuclear Power Plants,” contains general design criteria (GDC) for nuclear power plants. GDC 2, “Design Bases for Protection Against Natural Phenomena,” requires that nuclear power plant structures, systems, and components (SSCs) important to safety must be designed to withstand the effects of earthquakes without loss of capability to perform their safety functions. o Appendix B to 10 CFR Part 50, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” establishes quality assurance requirements for the design, manufacture, construction, and operation of nuclear power plant SSCs that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. The pertinent requirements of Appendix B apply to all activities affecting the safety-related functions of those SSCs. o Appendix S to 10 CFR Part 50, “Earthquake Engineering Criteria for Nuclear Power Plants,” requires that all nuclear power plants must be designed so that certain SSCs DG-1315, Page 2 remain functional if the SSE ground motion occurs. These SSCs are those 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 CRF 50.34(a)(1)