Document: NUREG-0800
Document ID: 6761ba88-e94f-41a4-902a-9009391ff709
Document Type: srp
Title: 15.3.2 LOSS OF FORCED REACTOR COOLANT FLOW INCLUDING TRIP OF PUMP
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550010.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
MOTOR AND FLOW CONTROLLER MALFUNCTIONS REVIEW RESPONSIBILITIES Primary - Organization responsible for review of transient and accident analyses for PWRs/BWRs Secondary - None I. AREAS OF REVIEW A decrease in reactor coolant flow while a plant is at power could result in degraded core heat transfer. An increase in fuel temperature and accompanying fuel damage then could result if specified acceptable fuel design limits (SAFDLs) are exceeded during the transient. This Standard Review Plan (SRP) section covers a number of transients expected to occur with moderate frequency that decrease forced reactor coolant flow rate. Each transient should be addressed in individual sections of the applicant's safety analysis report (SAR) or design control document (DCD), as specified in Regulatory Guide (RG) 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 areas of review are as follow: 1. Core thermal and hydraulic transients with partial and complete loss of reactor coolant flow are evaluated, including: