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:
e, site suitability report or topical report). IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. The reviewer verifies that the SAR contains sufficient information and that the review supports the following kinds of statements and conclusions, which should be included in the staff's safety evaluation report: 15.6.5-13 Revision 3 - March 2007 1. The staff concludes that the loss-of-coolant analysis resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary is acceptable and meets the relevant requirements of 10 CFR 50.46, GDC 13, GDC 35, and 10 CFR 100 or 10 CFR 50.67. This conclusion is based on the following: 2. The applicant meets GDC 13 requirements by demonstrating that all credited instrumentation was available, and that actuations of protection systems, automatic and manual, occurred at values of monitored parameters that were within the instruments’ prescribed operating ranges. 3. The applicant has performed analyses of the performance of the emergency core cooling system (ECCS) in accordance with the Commission's regulations (10 CFR 50.46). The analyses considered a spectrum of postulated break sizes and locations and were performed with an evaluation model that follows the guidance contained in Regulatory Guide 1.157 or Section I of Appendix K to 10 CFR Part 50 and meets the requirements of 10 CFR 50.46. The results of the analyses show that the ECCS satisfy the following criteria: A. The calculated maximum fuel rod cladding temperature does not exceed 1200 oC (2200 oF). B. The calculated total maximum local oxidation of the cladding does not exceed 17% of the total cladding thickness before oxidation. C. The calculated total amount of hydrogen generated from