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:
s of surface water use, and location downstream from the point of entry. Alternate conceptual models should be developed that reasonably bound hydrogeological conditions at the site. A bounding set of plausible surface and subsurface pathways from potential points of accidental release should be developed, to determine the critical pathways that may have the most severe impact on existing uses and known and likely future uses of ground and surface water resources near the site. The basis of the assumed liquid radioactive source term should be clearly stated and should include sufficient information for the staff to perform an independent evaluation or confirmation. The discussions should indicate the type of reactor design forming the basis of the source term. They should state whether the radioactive material inventories are based on a design’s certification or have been adjusted (e.g., upward or downward), in whole or in part, for designs whose certifications the NRC has not yet approved at the time of submission of the application. The site conceptual model should consider whether the ground and surface water environment could delay, disperse, dilute, or concentrate accidentally released radioactive liquid effluent during its transport. The model should assess scenarios combining accidental release of radioactive effluents with hydrologic extreme events such as floods or low flows, as well as with seismic and non-seismic events (e.g., it should assess the effects of structural or operational failures of hydraulic structures located upstream and downstream of the plant and the ensuing sudden changes in the flow regime). Applicants need to minimize contamination and radioactive waste generation over the total life cycle of a facility, from initial layout and design through operation and final decontamination and dismantlement at the time of decommissioning, in accordance with 10 CFR 20.1406, “Minimization of contamination.” RG 4.21 provides guidance on