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:
aff verifies that the applicant has demonstrated that the radiological consequences associated with the bounding DBAs using the applicant’s site-specific short-term χ/Q values meet the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1). NOTE: At the COL stage, the staff verifies that no changes from the site-specific short- term χ/Q values specified in the ESP application have occurred due to changes in plant design, plant location on the site, building orientation, or fission product release points. The staff 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 to determine the resulting radiological consequences at the EAB and LPZ for public information and to supplement the design basis. NOTE: Also the COL stage, the staff determines that the radiation protection design of the control room is acceptable if the total calculated radiological consequences for the postulated fission product release fall within the exposure acceptance criteria specified in GDC 19 of 5 rem TEDE for the duration of the accident. 2. ESP applications that use the PPE approach A. The staff reviews the proposed PPE values to determine whether the set of PPE values is sufficient to enable the staff to conduct its evaluation of the radiological consequences. The PPE values should be found not unreasonable for 15.0.3-10 March 2007 consideration in the staff’s findings regarding compliance with Subpart A of 10 CFR Part 52. B. To enable the staff to perform its independent radiological consequence analyses, the PPE values should include, but are not limited to, the following design basis accident source term parameters: i. The isotopic quantities of fission products released in curies to the environment from the site. ii. Rates of fission product release to the environment from the site as a function of time. C. The