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
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CFR Title: 

Content:
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 COL 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 evaluation report, and the results are listed in Table [ ]. 15.0.3-19 March 2007 Therefore, the staff concludes that the distances to the EAB and the LPZ outer boundary of the [site name] site and plant features intended to mitigate the radiological consequences of postulated design basis accidents, in conjunction with the source term and the fission product release rates from the site to the environment provided by the applicant, are sufficient to provide reasonable assurance that the total radiological consequences of the design basis accidents will be within the dose evaluation factors set forth at 10 CFR 50.34(a)(1) and GDC 19. 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) and GDC 19. 6. Combined license application with certified standard reactor design. As set forth above, the staff has reviewed the site-specific short-term atmospheric dispersion (χ/Q) values at the exclusion area boundary (EAB), at the boundary of the low population zone (LPZ), in the