Document: NUREG-0800
Document ID: 598d070d-fb96-43ce-ad4f-27f14623be46
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350119.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
CFR Part: 
CFR Title: 

Content:
maximum), reactor coolant system pressure, minimum DNBR (PWR) or CPR (BWR); core and recirculation loop coolant flow rates (BWR), coolant conditions (inlet temperature, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions), steam line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor coolant system to the containment system (if applicable) are reviewed. The more important of these parameters for the limiting transient are compared to those predicted for other similar plants to verify that they are within expected range. IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and his review supports the followin? kinds of statements and conclusions, which 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, and 26. This conclusion is based on the following: The applicant has met the requirements of GDC 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 GDC 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 acceptable limits by assuring 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 malfunc- tions, main steam isolation valve closure (in BWRs), loss of condenser vacuum, loss of nonemergency ac power to the station