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:
, the staff reviews the applicant’s radiological dose calculations and performs independent confirmatory radiological consequence dose calculations using the site-specific short-term χ/Q values and the source term provided in the certified reactor design control document. D. For each postulated accident, the calculated doses from all postulated fission product release pathways from the facility are combined and are compared with the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1) at the nearest EAB and LPZ outer boundary stated in the applicant’s site safety assessment. E. For each postulated accident, the calculated doses from all postulated fission product release pathways from the facility, including all sources of radiation exposure to the control room personnel, are combined, and the calculated dose in the control room is compared with the radiological consequence evaluation factors identified in GDC 19. F. For each postulated accident, the calculated doses from all postulated fission product release pathways from the facility, including all sources of radiation exposure to the personnel in the technical support center, are combined, and the calculated dose in the TSC is compared with the radiological consequence evaluation factors identified for the control room of 5 rem TEDE for the duration of the accident. 4. CP, OL, DC and COL and ESP applications that neither reference a standard reactor design certified by NRC nor use the PPE approach A. The staff reviews the sequences of DBA events as described by the applicant to ensure that the spectrum of DBAs includes the bounding DBA with respect to calculated fission product releases. The spectrum of DBAs has generally been assumed to reflect a substantial meltdown of the reactor core (a major reactor accident) with subsequent release of appreciable quantities of fission products to 15.0.3-12 March 2007 the environment. Although the loss-of-coolant (LOCA) is typically the maximum