Document: NRC Regulatory Guide
Document ID: a094549d-8685-4dad-b90f-c28c7d279a53
Document Type: regulatory_guide
Title: Geologic and Geotechnical Site Characterization Investigations for Nuclear Power Plants + HISTORY – HISTORY 08/2021 – DG-1392 , Proposed Revision 3 07/2014 – Periodic Review of Revision 2 – Reviewed with no issues identified 02/2001 – DG-1101 , Proposed Revision 2 (Rev. 3)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2119/ML21194A176.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.132
CFR Part: 
CFR Title: 

Content:
0 CFR 100.23, “Geologic and seismic siting criteria,” provides geologic and seismic criteria. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (Ref. 4), provides guidance to the NRC staff in performing safety reviews under 10 CFR Part 50 and 10 CFR Part 52. Chapter 2, “Site Characteristics and Site Parameters,” gives general review guidance related to site characteristics and site parameters, together with site-related design parameters and design characteristics, as applicable. • RG 1.29, “Seismic Design Classification for Nuclear Power Plants” (Ref. 5), identifies the structures, systems, and components (SSCs) that should be designed to withstand the effects of the safe shutdown earthquake and remain functional. • RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (Ref. 6), and RG 1.206, “Applications for Nuclear Power Plants” (Ref. 7), provide general guidance on the types of information about the hydrologic setting and assessments of flooding hazards that a license application for a light-water reactor (LWR) power plant should include. • RG 1.138, “Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants” (Ref. 8), provides guidance on sampling, storage, and laboratory investigations of the properties of soils for engineering analysis and design of nuclear power plants. • RG1.201, “Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance” (Ref. 9), describes a risk-informed process for categorizing SSCs according to their safety significance that can remove SSCs of low safety significance from the scope of certain identified special treatment requirements. • RG 4.7, “General Site Suitability Criteria for Nuclear Power Stations” (Ref. 10), assists applicants in the