Document: NUREG-0800
Document ID: 7d56ab5c-90b1-42b4-a509-857fbfd674db
Document Type: srp
Title: review.10
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070724.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
conclusion is based upon (1) its review of the applicant's analysis of the accident and radiological consequences and (2) an independent dose calculation by the staff using the source term assumptions contained in Regulatory Guide 1.77, the atmospheric dispersion factors as discussed in SRP Section 2.0, and other conservative assumptions. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.32 V. IMPLEMENTATION The following provides guidance to applicants and licensees regarding the staff's plans for using this appendix to SRP Section 15.4.9. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 33 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.34 Implementation schedules for conformance to parts of the method discussed herein are contained in the reference regulatory guides. VI. REFERENCES 1. 10 CFR Part 100, Paragraph 11, "Determination of Exclusion Area, Low Population Zone, and Population Center Distance." 2. Regulatory Guide 1.77, "Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors." 3. Appendix A, SRP Section 15.6.5, "Radiological Consequences of a Design Basis Loss-of-Coolant Accident (Containment Leakage