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:
nts, 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. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities” 2. 10 CFR 50.34, “Contents of applications; technical information” 15.0.3-22 March 2007 3. 10 CFR 50, Appendix A, “General Design Criteria for Nuclear Power Plants” 4. 10 CFR 50, Appendix E, “Emergency Planning and Preparedness for Production and Utilization Facilities” 5. 10 CR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants” 6. 10 CFR Part 100, “Reactor Site Criteria” 7.