Document: NUREG-0800
Document ID: 94ab38ac-ddfc-4ba1-ae38-bc25ffa6e976
Document Type: srp
Title: – 15.4.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070716.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
S The reviewer verifies that the SAR contains sufficient information and that thehis review 39 supports the following kinds of statements and conclusions which should be included in the staff's safety evaluation report (SER): The SER should present one statement for all similar transients. 2 DRAFT Rev. 2 - April 1996 15.4.4-10 A number of plant transientsAOOs 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), 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 2 transientsAOOs 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 _________ transientAOO. This transientAOO was evaluated 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 transientsAOOs that result in an increase in coolant flow through the reactor core is acceptable and meets the relevant requirements of General Design Criteria 10, 15, 20, 26, and 28. This conclusion is based on the following: 1. The applicant has met the requirements of General Design Criteria 10, 20, and 26 with respect to demonstrating that the specified acceptable fuel design limits are not exceeded for this event. 2. The applicant has met the requirements of General Design Criteria 15 and 28 with respect to ensuringassuring that the design conditions of the reactor coolant pressure boundary are not exceeded because the protection system operates to maintain the maximum pressure within the reactor coolant and main steam system pressures below