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:
a technical assistance contract to assist the NRC staff should be placed to verify the applicant’s proposed fission product removal credit. F. The staff reviews the points of fission product release from the major structures and systems, and from the ESF components of the facility. G. Using Section 2.3.4 of this standard review plan, the staff reviews the site- specific short-term χ/Q values determined by the applicant, and performs an independent evaluation as described therein. H. The staff performs an independent confirmatory radiological consequence analysis using pertinent information in the applicant’s SAR to determine whether the proposed site meets the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1). For applications other than an ESP, the staff also determines if the requirements of GDC 19 for maintaining the control room in a safe condition are met. By performing an independent confirmatory calculation, the staff will evaluate the reasonableness of the licensee’s analysis model and results. I. For each postulated accident, the calculated doses from all postulated fission product release pathways from the site are combined, and the calculated doses are compared with the radiological consequence evaluation factors identified in 10 CFR Part 50.34(a)(1) at the nearest EAB and LPZ outer boundary stated in the applicant’s SAR. J. For each postulated accident, the calculated doses from all postulated fission product release pathways from the site, 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. K. For each postulated accident, the calculated doses from all postulated fission product release pathways from the site, including all sources of radiation exposure to the personnel in the technical support center, are combined, and the calculated dose in the TSC is