Document: NUREG-0800
Document ID: c75a9de4-9927-49e4-b078-7f5dadd37acd
Document Type: srp
Title: DESIGN BASIS ACCIDENT RADIOLOGICAL CONSEQUENCE ANALYSES FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.3
CFR Part: 
CFR Title: 

Content:
onsequences analyses against the relevant regulatory criteria. The evaluation should support the staff’s conclusions as to whether the regulations are met. The reviewer should state what was done to evaluate the applicant’s submittal. The staff’s evaluation may include verification that the applicant followed applicable regulatory guidance, performance of independent calculations, and/or validation that the appropriate assumptions were made. The reviewer may state that certain information provided by the applicant was not considered essential to the staff’s review and was not reviewed by the staff. While the reviewer may summarize or quote the information offered by the applicant in support of its application, the reviewer should clearly articulate the bases for the staff’s acceptance and conclusions. The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. 15.0.3-16 March 2007 A conclusion of the following type for the radiological consequence analyses will be included in Section 15 of the site safety evaluation, standard design safety evaluation, or combined license safety evaluation: 1. ESP application that references a standard reactor design certified by NRC. As set forth above, the staff has reviewed the site-specific short-term atmospheric dispersion (χ/Q) values at the exclusion area boundary (EAB) and at the boundary of the low population zone (LPZ) for the proposed site in the early site permit (ESP) application and has verified that they are within the postulated design basis χ/Q values specified in the [name of certified reactor design] design control document. Therefore, the staff concludes that the distance to the EAB and to the LPZ boundary of the [name] site, in conjunction with the engineered safety features as