Document: NUREG-0800
Document ID: dae11b53-e280-4543-9b4d-00a793745d2c
Document Type: srp
Title: – 15.4.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550007.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
STARTUP OF AN INACTIVE LOOP OR RECIRCULATION LOOP AT AN INCORRECT TEMPERATURE, AND FLOW CONTROLLER MALFUNCTION CAUSING AN INCREASE IN BWR CORE FLOW RATE REVIEW RESPONSIBILITIES Primary - Organization responsible for review of transient and accident analyses for PWRs/BWRs Secondary - None I. AREAS OF REVIEW A number of anticipated operational occurrences (AOOs) may cause either increased core flow or introduction of cooler or de-borated water into the core. These AOOs result in an increase in core reactivity due to decreased moderator temperature, moderator boron concentration, or core void fraction. This Standard Review Plan (SRP) section is intended to be applicable to all such AOOs. Each of these AOOs should be discussed in individual sections of the applicant's Safety Analysis Report (SAR) or Design Control Document (DCD), as specified in NRC Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants" and Regulatory Guide 1.206, "Combined License Applications for Nuclear Power Plants (LWR Edition)." The specific area of review are as follows: 1. Boiling water reactor (BWR): Startup of an idle recirculation pump. 2. BWR: Flow controller malfunction causing increased recirculation flow.