Document: NUREG-0800
Document ID: a92282c2-a360-4183-a326-b730f21b5b1b
Document Type: srp
Title: 15.3.2.-2
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:
Revision 2 - March 2007 A. For boiling water reactors (BWRs), partial and complete recirculation pump trips and malfunctions of the recirculation flow controller causing decreasing flow. B. For pressurized water reactors (PWRs), partial and complete reactor coolant pump trips. 2. A partial loss of coolant flow may be caused by a mechanical or electrical failure in a pump motor, a fault in the power supply to the pump motor, a pump motor trip caused by such anomalies as over-current or phase imbalance, or a failure within the recirculation flow control network (BWR) resulting in decreased flow (if applicable). A complete loss of forced coolant flow may be the result of the simultaneous loss of electrical power to all pump motors. 3. The review includes the postulated initial core and reactor conditions pertinent to the loss of flow transient; the methods of thermal and hydraulic analysis; the postulated sequence of events, including time delays before and after protective system actuation; assumed reactions of reactor system components; the functional and operational characteristics of the reactor protection system affecting the sequence of events; and all operator actions required to secure and maintain the reactor in a safe condition. 4. Results of the applicant's analyses are reviewed for whether values of pertinent system parameters are within expected ranges for the type and class of reactor under review. The system parameters evaluated include core flow and flow distribution, channel heat flux (average and hot), minimum critical heat flux ratio (or minimum critical power ratio), departure from nucleate boiling ratio (DNBR), vessel water level, thermal power, vessel pressure, steam line pressure (BWR), main steam flow (BWR), and feedwater flow (BWR). Results of the applicant's fuel damage analysis are reviewed by the methods described in SRP Section 4.2. 5. The sequence of events described in the SAR or DCD is reviewed by the organization responsible for the