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:
The parameters in the atmospheric diffusion and dose calculation models are reviewed by PERB as part of its primary review responsibility for SRP Section 15.6.5, Appendix A.11 The exclusion area and the low population zone are reviewed by the Civil Engineering and Geosciences Branch (ECGB) as part of its primary review responsibility under SRP Sections 2.1.1, 2.1.2, and 2.1.3.12 The site characteristics assumed by the design certification applicant will be reviewed by the ECGB as part of its primary review responsibility for SRP Section 2.1.1.13 II. ACCEPTANCE CRITERIA The acceptance criteria are based on the requirements of 10 CFR Part 100 as related to mitigating the radiological consequences of an accident. The plant site and dose mitigating engineered safety features are acceptable with respect to the radiological consequences of a postulated control rod drop accident if the calculated whole-body and thyroid doses at the exclusion area boundaries (EAB) and at the low population zone (LPZ) boundaries are well within the exposure guideline values in 10 CFR Part 100, paragraph 11 (Ref. 1). "Well within" 14 is defined as 25% of the 10 CFR Part 100 exposure guideline values or 750 mSv (75 rem) for 15 the thyroid and 60 mSv (6 rem) for whole-body doses. The fission product source term used in the dose analysis is acceptable if it meets the guidelines of Regulatory Guide 1.77 (Ref. 2).16 Technical Rationale17 The technical rationale for application of these acceptance criteria to reviewing the radiological consequences of a control rod drop accident is discussed in the following paragraphs: Compliance with 10 CFR 100.11 requires that the exclusion area and the low population zone be defined based on assurances that specified limits will not be exceeded for radiation doses to individuals at the outer boundaries of those regions for postulated fission product releases. 15.4.9-3 DRAFT Rev. 3 - April 1996 This requirement applies to this appendix because rod drop accidents