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:
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 are included among the potential accidents for which fission product releases are postulated. Review under SRP Section 15.4.9 focuses on the extent of fuel damage to allow a determination of the source term to be used by the Appendix A reviewer in evaluating compliance with 10 CFR 100.11. Guidance for determining the acceptability of the source term and dose calculations is found in Regulatory Guide 1.77. Meeting this requirement provides assurance that offsite radiation doses from a BWR rod drop accident are well within the guideline doses specified in 10 CFR 100.11.18 III. REVIEW PROCEDURES The reviewer selects and emphasizes specific aspects of this appendix to Standard Review Plan Section 15.4.9 as appropriate for the particular plant. The judgment of which areas need to be given attention and emphasis is based on the similarity of the information presented in the safety analysis report (SAR) or other licensing submittals. 19 Based on past reviews by the staff, a control rod drop accident is expected to result in radiological consequences less than 10% of the Part 100 guideline values even with conservative assumptions. The reviewer should examine the site meteorology, plant features, and fuel damage as a result of the accident for the plant in question and compare these with the corresponding features and resulting doses for previously reviewed plants to ascertain whether a specific calculation of the radiological consequences should be performed. The reviewer should examine the applicant's description of the control rod drop accident, in particular, the sequence of events following the accident to assure that the most severe case from the standpoint of release of fission products to the environment is analyzed. Unless unusual plant or site features are present or