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:
considerations but would instead be governed by the regulatory requirement in 10 CFR 100.21(b) for reactors to be located distant from densely populated centers with more than about 25,000 residents. However, an advanced reactor with estimated doses below 1 rem at the e The scope of RG 1.233 is limited to non-LWRs. In the future, the staff may expand the applicability of RG 1.233 to LWRs as part of the guidance development for ongoing rulemakings. f The term “major accident” is described in 10 CFR 50.34(a)(1)(ii)(D), footnote 6 as follows: "The fission product release assumed for this evaluation should be based upon a major accident, hypothesized for purposes of site analysis or postulated from considerations of possible accidental events. Such accidents have generally been assumed to result in substantial meltdown of the core with subsequent release into the containment of appreciable quantities of fission products." g The methodology endorsed in RG 1.233 also includes specific steps to assess defense in depth provided by the combination of plant design, siting, and programmatic controls. h The NRC can accept methodologies and computer models via endorsement of generally accepted methods, standards, and practices (e.g., regulatory guide for a consensus standard or approval of generic topical report) or as part of specific applications. Such acceptances can be for broad methodologies such as RG 1.247, “TRIAL—Acceptability of Probabilistic Risk Assessment Results for Non-Light-Water Reactor Risk-Informed Activities,” or combinations of individual computer codes and related simulations. DG-4034, Appendix A, Page A-5 site boundary over the month following the assumed postulated accident could be sited within towns with populations of no more than approximately 25,000 residents. A-3.2 Regulatory Guide 1.183 Plus Severe Accidents Approach (LWRs) Section C.1.3 of this RG and RG 1.183 address the siting assessments and determination or confirmation of the