Document: NUREG-0800
Document ID: 2bfc8c43-56b1-4f0b-ba5a-a421dfcbc125
Document Type: srp
Title: - 15.4.5-9
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:
e included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. A number of plant AOOs can result in a core flow increase. Those that might be expected to occur with moderate frequency are the startup of an idle recirculation pump (BWR, if applicable), flow controller malfunction causing increasing core flow (BWR), startup of a pump in an inactive reactor coolant loop (PWR), and startup of a pump in an initially isolated inactive reactor coolant pump loop. All these postulated AOOs have been reviewed. It was found that the most limiting with regard to core thermal margins and pressure within the reactor coolant and main steam systems was the AOO. This AOO was analyzed by the applicant using a mathematical model that has been previously reviewed and found acceptable by the staff. The parameters used as input to this model were reviewed and found to be suitably conservative. The staff concludes that the plant design with regard to AOOs that result in an increase in coolant flow through the reactor core is acceptable and meets the relevant requirements of GDCs 10, 15, 20, 26 and 28. This conclusion is based on the following: 1. The applicant has met the requirements of GDCs 10, 20 and 26 with respect to demonstrating that SAFDLs are not exceeded for this event.