Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
nd prevention for both large and small break LOCAs. 15.6.5-9 Revision 3 - March 2007 2. An adequate failure mode analysis has been performed to justify the selection of the most limiting single active failure. This analysis is reviewed in part under SRP Section 6.3. If the design has been changed from that presented in previous applications, changes in the reactor coolant system, reactor core, and ECCS are reviewed with respect to the most limiting single failure. 3. A variety of break locations and the complete spectrum of break sizes were analyzed. If part of the evaluation is done by referencing earlier work, design differences (ECCS, reactor coolant system, reactor core, etc.) between the facilities in question are reviewed. If there are significant differences, sensitivity studies on the important parameters should have been made by the applicant. If such sensitivity studies are not presented in the SAR, the reviewer requests that they be made. 4. New generation LWRs for which core uncovery is not expected during the entire period of a LOCA should be reviewed to ensure that a significant number of fuel rods will not be damaged due to local dryout conditions. This may be demonstrated by showing that the limiting fuel rod heat flux remains below the Critical Heat Flux (CHF) at a given pressure after depressurization has taken place. If, however, the heat flux exceeds the CHF, further analyses should be performed to estimate the amount of fuel damage expected from “burn-out” while the bulk of the core remains covered with water during the LOCA. Fuel damage and potential for radioactivity release to the environment must be consistent with 10 CFR 100 or 10 CFR 50.67. If such evaluations are not provided in the SAR, the reviewer requests that they be made. 5. The parameters and assumptions used for the calculations were conservatively chosen, including the following points: A. The initial power level is taken as the licensed core thermal power for the number of