Document: NUREG-0800
Document ID: 6997f9d9-dedc-49d7-ac15-7615c1bd9713
Document Type: srp
Title: SPECTRUM OF ROD DROP ACCIDENTS (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550015.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.9
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for review of transient and accident analyses for PWRs/BWRs Secondary - None I. AREAS OF REVIEW The specific areas of review are as follow: 1. The reviewer evaluates the consequences of a control rod drop accident in a boiling water reactor (BWR) in the area of physics. The reviewer covers the applicant's description of the occurrences that lead to the accident, initial conditions, rod patterns and worth, safety features designed to limit the amount of reactivity, the rate at which reactivity can be added to the core, and methods for analyzing the accident. Reference 5 is on control rod drop accident analysis generally. The review also examines potential fission product releases from a control rod drop accident. These releases contribute to the source term in analyses for determining compliance with dose limits specified in either 10 CFR 100.11 or 10 CFR 50.67. The staff conducted an evaluation of the advanced boiling water reactor (ABWR) described in Reference 2 because it was the first application for an ABWR standard design with hypothetical site boundaries establishing a reference for future applications. This review applies to BWRs only. 15.4.9-2 Revision 3 - March 2007 2. COL Action Items and Certification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident analyses is provided in SRP Section 15.0. 2. Design basis radiological