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:
) from DBAs, is used to confirm or establish performance requirements, including maximum leak rates, for the containment features using the existing criteria for doses at the exclusion area boundary i This approach is provided to address non-LWRs using a containment-type barrier that encloses other barriers similar to the essentially leak tight structures used for LWRs. The consideration of multiple barriers and event-specific mechanistic source terms are supported in the LMP methodology (see section A-3.1). Hybrid approaches may be justified but are outside the scope of this guidance. DG-4034, Appendix A, Page A-6 and LPZ. (See for example, the discussion in RG 1.183, Section C.2, “Attributes of an Acceptable AST [alternative source term].”) The non-LWR source term for the traditional siting analyses should be expressed in terms of times and rates of appearance of radioactive fission products released into the containment-type feature, the types and quantities of the radioactive species released, and the chemical forms for those radionuclides expected to significantly influence the public dose. Similar to the traditional approach described above for LWRs (section A-3.2), the conservative source term introduced to the interior of a containment-type feature should also be used in combination with an assessment of containment performance under severe accidents. Demonstrating that the population density for a subject site does not exceed 500 ppsm out to twice the calculated distance at which the 1 rem TEDE is estimated for a major accident with consideration of containment performance during severe accidents is sufficient to meet the requirements of 10 CFR 100.21(h). If an applicant can show that the calculated offsite dose does not exceed 1 rem TEDE for the 30-day exposure period, the siting of a reactor might not be determined by population-density considerations but would instead be governed by the regulatory requirement in 10 CFR 100.21(b) for reactors to be