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:
he LPZ. The boundary of the population center is determined by population distribution, not political boundaries. In accordance with 10 CFR 50.34(a)(1)(ii)(D)(1), 10 CFR 52.17(a)(1)(ix)(A), and 10 CFR 52.79(a)(1)(vi)(A), the exclusion area is required to be of such a size that an individual located at any point on its outer boundary would not receive a radiation dose above 25 rem total effective dose equivalent (TEDE) over any 2-hour period following a postulated fission product release. The required exclusion area size depends on the atmospheric characteristics of the site, as well as on plant design. In accordance with 10 CFR 50.34(a)(1)(ii)(D)(2), 10 CFR 52.17(a)(1)(ix)(B), and 10 CFR 52.79(a)(1)(vi)(B), the LPZ must be of such a size that an individual located on its outer boundary during a postulated accident would not receive a radiation dose above 25 rem TEDE. The required LPZ size depends on the atmospheric dispersion characteristics and population characteristics of the site, as well as on plant design. The regulations in 10 CFR 52.17 for ESPs and 10 CFR 52.79 for COLs require an applicant’s site safety analysis report and final safety analysis report, respectively, to include information on site location, the facility location on the site, population characteristics, locations of nearby facilities, postulated releases in the event of an accident, and other technical factors. NUREG-0800, Section 2.1.1, “Site Location and Description,” and section 2.1.2 describe the NRC staff’s review procedures for the site location, description, and exclusion area authority and control. Based on the assumptions in the radiological consequence analyses for the design-basis accident, the required distances to the exclusion area boundary and the outer boundary of the LPZ will depend on aspects of the plant design, such as the reactor power level, allowable containment leak rate, and engineered safety features, as well as the atmospheric dispersion characteristics of