Document: NUREG-0800
Document ID: 621763b9-bd48-4ded-8c42-b942a23a06d4
Document Type: srp
Title: – 15.2.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070680.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.1
CFR Part: 
CFR Title: 

Content:
should be included in the staff's safety evaluation report (SER): The staff concludes that the plant design is acceptable with regard to transients resulting in unplanned decreases in heat removal by the secondary system that are expected to occur with moderate frequency and that the predicted response meets the requirements of General Design Criteria 10, 15, 17, and 26. This conclusion is based on the 51 following: The applicant has met the requirements of General Design Criteria 10 and 26 with respect to demonstrating that specified acceptable fuel design limits are not exceeded for this event and has met the requirements of General Design Criterion 15 with respect to demonstrating that the reactor coolant pressure limits have not been exceeded by this event, and that resultant leakage will be within The SER should present one statement for moderate frequency transients involving an 1 unplanned decrease in heat removal by the secondary system. Thus, the results of the reviews under SRP Sections 15.2.6 and 15.2.7 are included in this statement. The SER should present one statement for moderate frequency transients involving an 2 unplanned decrease in heat removal by the secondary system. Thus, the results of reviews conducted under SRP Sections 15.2.6 and 15.2.7 are included in this statement. DRAFT Rev. 2 - April 1996 15.2.1-10 acceptable limits by assuring ensuring that plant transients do not result in an unplanned decrease in heat removal by the secondary system. Those that might be expected to occur with moderate frequency are turbine trip, loss of external load, steam pressure regulator malfunctions, main steam isolation valve closure (in BWRs), loss of condenser vacuum, loss of nonemergency ac power to the station auxiliaries, and loss of normal feedwater flow. All these 1 postulated transients have been reviewed. It was found that the most limiting in regard to core thermal margins and pressure within the reactor coolant and main steam systems was the