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
CFR Part: 
CFR Title: 

Content:
fficient basis and information for the NRC staff to conclude that the proposed alternative demonstrates compliance with GDC 2 and 10 CFR Part 50 Appendices B and S. C. STAFF REGULATORY GUIDANCE 1. The SSCs of a nuclear power plant that are designated as seismic Category I must be designed to withstand the effects of the SSE and remain functional. The titles and functions of these seismic Category I SSCs for LWR designs are based on existing technology from prior applications. In newer designs certain SSCs which were designated seismic Category I in previous designs may not have the same safety-related functions requiring seismic Category I classification, and certain passive SSCs in new LWR designs may be named differently from SSCs that performed similar functions in previous designs. The pertinent quality assurance requirements of Appendix B to 10 CFR Part 50 shall apply to all activities affecting the safety-related functions of seismic Category I SSCs. The following SSCs of a nuclear power plant, including their foundations and supports, should be designated as seismic Category I: a. the reactor coolant pressure boundary as defined in 10 CFR 50.2; b. the reactor core and reactor vessel internals; c. systems1 or portions thereof that are needed for (1) emergency core cooling, (2) post- accident containment heat removal, or (3) post-accident containment atmosphere cleanup (e.g., hydrogen removal system); d. systems or portions thereof (including but not limited to systems such as residual heat removal and auxiliary feedwater) that are needed to (1) shutdown the reactor and maintain it in a safe shutdown condition, (2) remove residual heat (including heat stored within the spent fuel pool), (3) control the release of radioactive material, or (4) mitigate the consequences of an accident; Several key examples of systems included in items 1.c and 1.d are provided below for reference, but do not represent the complete scope of these items. Determining the complete