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:
tdown 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) or 10 CFR 100.11. • 10 CFR 50.48, “Fire protection,” contains the requirement for a fire protection plan for nuclear power facilities. 10 CFR 50.48(c) addresses the risk-informed, performance-based standard for fire protection programs. Classification of fire protection equipment is beyond the scope of this regulatory guide. • 10 CFR 50.55a(h) requires that safety system equipment be designed to meet their functional performance requirements over the range of normal environmental conditions during normal, abnormal and accident circumstances, including SSE. • 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” (Ref. 2) governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities licensed under Section 103 of the Atomic Energy Act of 1954, as amended (68 Stat. 919), and Title II of the Energy Reorganization Act of 1974 (88 Stat. 1242). • 10 CFR Part 100, “Reactor Site Criteria” (Ref. 3), addresses the physical characteristics of a site including seismology and geology in determining the site’s acceptability for a nuclear power reactor, as well as guidelines for limiting potential offsite exposure. Related Guidance • NUREG-0800, “Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” (Ref. 4) provides guidance to the NRC staff for review of Safety Analysis Reports submitted as part of license applications for nuclear power plants. o SRP Section 3.2.1, “Seismic Classification,” provides guidance to the NRC staff in reviewing seismic classification of SSCs for nuclear power plant applications. o SRP Chapter 7, “Instrumentation and