Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
eviewed, the staff may perform calculations to verify the adequacy of the analytical methods. Thereafter, audit calculations will not typically be performed to verify the results of an approved method that has been submitted in a safety analysis report. Calculations, benchmarking exercises, and additional reviews of generic methods may be undertaken, however, at any time a clear need arises to reconfirm the adequacy of the method. 4.2-23 Revision 3 - March 2007 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 staff concludes that the fuel system of the ________ plant has been designed so that (1) the fuel system will not be damaged as a result of normal operation and anticipated operational occurrences, (2) fuel damage during postulated accidents will not be severe enough to prevent control rod insertion when it is required, and (3) core coolability will always be maintained, even after severe postulated accidents, thereby meeting the related requirements of 10 CFR 50.46; GDC 10, 27, and 35 in Appendix A to 10 CFR Part 50; and 10 CFR Part 100 (for existing reactors) or 10 CFR 50.34 (for new reactors) or 10 CFR 50.67 (as an alternative to 10 CFR Part 100 for existing reactors). This conclusion is based on the following: 1. The applicant has provided sufficient evidence that these design objectives will be met based on operating experience, prototype testing, and analytical predictions. Those analytical predictions dealing with structural response and fuel densification have been performed in accordance with (1) the guidelines of RG 1.60, RG 1.77, and RG 1.126, or methods that the staff has reviewed and found to be acceptable alternatives to those RGs and (2) the guidelines in Appendix A to SRP Section