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:
evant design parameters specified by the applicant in the COL application are bounded by the applicant’s PPE submitted with the ESP application. 3. ESP application that neither references a standard reactor design certified by NRC nor uses the PPE approach. 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). The results of the applicant’s radiological consequence dose calculation are provided in Table [ ]. 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 site-specific χ/Q values at the EAB and LPZ proposed in the ESP application. The staff finds that its results are also within the radiological consequence evaluation factors identified in 10 CFR 50.34(a)(1). 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 ESP 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 [ ]. Therefore, the staff concludes that the distances to the EAB and the LPZ outer boundary of the [site name] site, 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). This conclusion is based on the staff review of the applicant’s analysis and on the staff’s independent analysis, which confirms that the