Document: NRC Regulatory Guide
Document ID: 239cc7c1-f2cb-46cc-945d-8009db28aa6c
Document Type: regulatory_guide
Title: General Site Suitability Criteria for Nuclear Power Stations + HISTORY - HISTORY 12/2023 – DG-4034 , Proposed Revision 4 12/2011 – DG-4021 , Proposed Revision 3 02/1995 – DG-4004, Second Proposed Revision 2 11/1992 – DG-4003, Proposed Revision 2 (Rev. 4)
Source: NRC Regulatory Guide Division 4
Source URL: https://www.nrc.gov/docs/ML2312/ML23123A090.pdf
Revision Date: 2023-10
Chapter: 
Section ID: RG-4.7
CFR Part: 
CFR Title: 

Content:
omplement the period of record in order to identify the expected minimum flow for the region. The U.S. Geological Survey 7Q10 calculation is an accepted screening-level method for estimating potential low-flow conditions from regional stream flow historical records. This statistical method identifies the minimum value as the lowest 7-day average flow in a 10-year period. If the 7Q10 is too low to supply adequate water for the plant, then other sources of water for non-safety-related and safety-related structures and ultimate heat sink requirements need to be identified. Bedient et al. (Ref. 59) and Riggs (Ref. 60) provide hydrologic frequency analysis of regional stream gauges with sufficient record lengths to represent expected minimum flows. 1.8 Industrial, Military, and Transportation Facilities Potential sites should be evaluated for possible safety impacts of operations at nearby industrial, military, and transportation facilities. 1.8.1 Relevant Regulations • 10 CFR 50.34, “Design objectives for equipment to control releases of radioactive material in effluents— nuclear power reactors;” o 10 CFR 50.34(a)(1); • 10 CFR Part 50, Appendix A, GDC 4, “Environmental and dynamic effects design bases;” • 10 CFR 52.17, “Contents of applications; technical information” o 10 CFR 52.17(a)(1); • 10 CFR 52.79, “Contents of applications; technical information in final safety analysis report” o 10 CFR 52.79(a)(1); and • 10 CFR Part 100, “Non-seismic site criteria” o 10 CFR Part 100.21(e). 1.8.2 Related Guidance • RG 1.78, “Evaluating the Habitability of a Nuclear Power Plant Control Room during a Postulated Hazardous Chemical Release” (Ref. 61); DG-4034, Page 26 • RG 1.76, “Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants;” • RG 1.221, “Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants;” • RG 1.91, “Evaluations of Explosions Postulated to Occur on Transportation Routes Near Nuclear