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 dose evaluation factors set forth at 10 CFR 50.34(a)(1). This conclusion is based on the staff review of the applicant’s analysis and on the staff’s independent analysis, which confirms that the calculated total doses are within the dose evaluation factors set forth at 10 CFR 50.34(a)(1). 4. Standard reactor design certification application. As set forth above, the applicant has selected and analyzed the bounding design basis accidents and has determined that the total radiological consequences of such accidents meet the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1) and GDC 19 for the standard reactor design, considering a reference site. The results of the applicant’s radiological consequence dose calculation are provided in Table [ ]. 15.0.3-18 March 2007 The staff reviewed the radiological consequence analyses provided by the applicant and has performed an independent analysis of the radiological consequences of each design basis accident considered in the application using the design reference χ/Q values at the EAB, LPZ, and control room proposed in the application. The staff finds that its results are also within the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1) and GDC 19. Although the staff performed an independent radiological consequence dose calculation as a means of confirming the licensee’s results, the staff’s approval of the standard design is based on the applicant’s analyses. Details of the staff’s analyses are presented in Section [ ] of this safety evaluation report, and the results are listed in Table [ ]. The staff performed a similar review of the applicant’s evaluation of the design basis accident radiological consequences in the technical support center in support of the emergency planning review. The staff has reasonable assurance that the dose in the TSC will be within 5 rem TEDE. The details of the staff’s analysis is presented in Section [ ] of this safety