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:
ately 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 boundaries of the exclusion area and LPZ based on the assumption of a major accident, the performance of containment and other systems included in a design to limit fission product release, and the characteristics of the subject site. An applicant may also use the analyses of a major accident using guidance such as RG 1.183 plus the evaluation of potential severe accidents that challenge the containment to evaluate an alternative to the assumed 20-mile distance from the plant for which population density is not to exceed 500 ppsm. LWR applicants using this method would evaluate the radiological consequences of DBAs described in RG 1.183 and severe accidents that challenge containment to estimate the distance at which a hypothetical individual would experience a dose of 1 rem TEDE over the 30-day period following the initiation of a release. The radiological source term from RG 1.183 can be used along with insights from generic or design-specific analyses to address the performance of containment and other systems included to limit the release of radionuclides from severe accidents. At a minimum, the containment leakage will be assumed to be the same as that used for the evaluation of the exclusion area boundary and LPZ. The magnitude and timing of possibly greater releases to the environment should be assumed based on the analyses of accident progression and containment performance from the assessment of severe accidents for the as-designed plant (including potential severe accident design features). 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