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:
e (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 credible accident associated with the light-water reactor design, the applicant should consider other accident sequences of greater radiological consequence for the specific reactor designs selected by the applicants or for reasonably foreseeable future reactor designs if the applicant has not selected the specific reactor designs at the time of ESP application. B. The staff reviews a spectrum of representative DBAs selected and evaluated by the applicant for determining the bounding DBA radiological consequences. The selected DBA should cover a spectrum of reactor transients and accidents. C. The applicant’s proposed accident source terms are reviewed in the following areas: i. Fission product inventory in the reactor core operated at the ultimate maximum proposed power level with the limiting condition which maximizes fission product releases. ii. Timing and rate of fission product release from the fuel following selected DBAs. The fission product release rates should be fractions of fission product inventory in the reactor core based on the maximum full power operation. iii. The coolant activity concentration is reviewed under SRP Section 11.1. The non-LOCA DBA coolant source terms are calculated based on the coolant activity concentration and include iodine spiking, using the guidance in RG 1.183. iv. The isotopic quantities in curies and the chemical forms of fission products released to the containment and to the environment. The staff reviews the modeling of changes in chemical form as the releases are processed by mitigating systems. v. Rates of fission product release to the environment from the site during the entire period of the DBA as a function of time. D. The staff reviews the fission product distribution, transport, removal, and release models within