Document: NUREG-0800
Document ID: ef559b35-0671-46e4-b172-09155cca8b81
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350427.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) Secondary - Accident Evaluation Branch (AEB) I. AREAS OF REVIEW The CPB evaluates the consequences of a control rod drop accident in a boiling water reactor (BMR) in the area of physics. The CPB review covers the applicant's description 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 psed to analyze the accident. A general reference on control rod drop accident analysis is noted in Reference 1. The relevant thermal-hydraulic analyses are reviewed under SRP Section 4.4. The AEB, as part of its secondary review responsibility described in the appendix to this SRP section, reviews the radiological consequences of a control rod drop accident, using the amount of failed fuel as obtained by CPB from the reactor core analyses as the source for dose calculations. The evaluation finding provided is as indicated in the attached Appendix. The applicant's determination of the reactor trip delay time, or the amount of time which 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 SRP Sections 7.2 and 7.3. II. ACCEPTANCE CRITERIA CPB acceptance criteria are based on meeting the requirements of General Design Criterion 28 (Ref. 2) as it relates to the effects of postulated reactivity acci- dents neither resulting in damage to the reactor coolant pressure boundary greater than limited local yielding, nor causing sufficient damage to impair significantly the capacity to cool the core. Rev. 2 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for the review of applications to construct and operate nuclear power plants. These documents