Document: NUREG-0800
Document ID: d16b9ee8-5c9f-4596-b2a2-01e02c859540
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF CONTROL ROD DROP ACCIDENT
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:
(BWR) APPENDIX A REVIEW RESPONSIBILITIES Primary - Accident Evaluation Branch (AEB)Emergency Preparedness and Radiation Protection Branch (PERB)1 Secondary - Core Performance Branch (CPB)Reactor Systems Branch (SRXB)2 I. AREAS OF REVIEW The AEBPERB review under this appendix to Standard Review Plan (SRP) Section 15.4.9 3 4 includes the following aspects of the postulated control rod drop accident for a boiling water reactor facility: 1. an examination of the plant response to the accident; 2. the release of fission products from the core to the environment via the turbine and condensers, as a result of the accident; and 3. the calculation of whole-body and thyroid doses at the exclusion area boundary (EAB) and the low population zone (LPZ) boundary due to the releases from the accident. The standard design certification applicant may make reasonable assumptions regarding certain site parameters such as /Q and exclusion area and low population zone characteristics.5 DRAFT Rev. 3 - April 1996 15.4.9-2 Review Interfaces The PERB will coordinate other branch evaluations that interface with the overall review of the radiological consequences of a control rod drop accident as follows:6 A secondary review is performed by the CPBSRXB and the results are used by AEBPERB in 7 8 the overall evaluation of the accident analysis. The core response aspects of the accident are reviewed by the CPBSRXB as part of its primary review responsibility for SRP Section 15.4.9. 9 Verification of the applicant's calculation of the number of fuel rod failures and the amount of fuel reaching the melting temperature is provided by the CPBSRXB based on the SRP Section