Document: NUREG-0800
Document ID: baab1f26-b869-4986-9c53-36842ceaa7c3
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070723.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
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CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Core Performance Branch (CPB)Reactor Systems Branch (SRXB)1 Secondary - Accident Evaluation Branch (AEB)Emergency Preparedness and Radiation Protection Branch (PERB)2 I. AREAS OF REVIEW The CPBSRXB evaluates the consequences of a control rod drop accident in a boiling water 3 reactor (BWR) in the area of physics. The CPBSRXB review covers the applicant's description 4 of the occurrences that lead to the accident, safety features designed to limit the amount of reactivity available and the rate at which reactivity can be added to the core, and methods used to analyze the accident. A general reference on control rod drop accident analysis is noted in Reference 1. An evaluation for the advanced boiling water reactor (ABWR) is described in Reference 4. The evaluation was conducted by the staff because it was the first application involving an ABWR standard design with hypothetical site boundaries, thereby establishing a reference for comparing future applications. 5 The relevant thermal-hydraulic analyses are reviewed under SRP Section 4.4. DRAFT Rev. 3 - April 1996 15.4.9-2 Review Interfaces SRXB will coordinate other branch evaluations with the overall review of this Standard Review Plan (SRP) section, as follows:6 1. The AEBPERB, as part of its secondary review responsibility described in the appendix 7 8 to this SRP section, reviews the radiological consequences of a control rod drop accident, using the amount of failed fuel as obtained by CPBSRXB from the reactor core analyses 9 as the source for dose calculations. The evaluation finding provided is as indicated in the attached appendix. 2. The applicant's determination of the reactor trip delay time, or the amount of time which 10 elapses between the instant the sensed parameter (e.g., pressure or neutron flux) reaches the level for which protective action is required and the onset of negative reactivity insertion, is reviewed under by the Instrumentation & Controls Branch (HICB)