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:
ADVANCED LIGHT WATER REACTORS REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of design basis accident radiological consequence analyses Secondary - Organization responsible for the review of meteorology I. AREAS OF REVIEW Chapter 15 of the SRP discusses the analysis of postulated accidents that could affect the safe design and siting of an advanced light-water reactor (LWR). The staff reviews information presented by the applicant for a construction permit (CP), operating license (OL), standard design certification (DC), early site permit (ESP), or combined operating license (COL) concerning radiological consequence analyses for postulated design basis accidents. This SRP section applies to reviews performed for each of these types of applications. The review covers the following specific areas: 1. CP, OL, DC or COL Applications. For a CP, OL, DC or COL application, the staff reviews the radiological consequences of potential design basis accidents (DBAs) in six parts: (1) review of selected bounding design basis accidents, (2) review of accident source terms, (3) review of the major structures, systems, and components of the facility that are intended to mitigate the radiological consequences of a DBA, (4) review of the 15.0.3-2 March 2007 characteristics of fission product releases from the proposed site (for CP, OL and COL reviews) or reference site (for the DC review) to the environment, (5) review of the meteorological characteristics of the proposed site for the CP, OL or COL review (reference site for DC review), and (6) review of the total calculated radiological consequence dose at the exclusion area boundary (EAB), low population zone (LPZ) and control room from the bounding DBAs. In support of the SRP Section 13.3 emergency planning review, the staff also reviews the dose analysis performed to demonstrate technical support center (TSC) habitability. The application must contain sufficient nuclear plant design information for the