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:
th (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 4.2. Those analytical predictions dealing with control rod ejection (PWR) or drop (BWR) have been performed in accordance with the interim criteria for RIAs in Appendix B to SRP Section 4.2. 2. The applicant has provided for testing and inspection of new fuel to ensure that it is within design tolerances at the time of core loading. The applicant has made a commitment to perform online fuel failure monitoring and postirradiation surveillance to detect anomalies or confirm that the fuel has performed as expected. The staff concludes that the applicant has described methods of adequately predicting fuel rod failures during postulated accidents so that radioactivity releases are not underestimated and thereby meets the related requirements of 10 CFR Part 100 or 10 CFR 50.67 or 10 CFR 50.34 (for new reactors). In meeting these requirements, the applicant has (1) used the fission-product release assumptions of RG 1.3 (or RG 1.4), RG 1.25, RG 1.77, and RG 1.183 and (2) performed the analysis for fuel rod failures for the rod ejection accident in accordance with the guidelines of Appendix B to Section 4.2 or with methods that the staff has reviewed and found to be an acceptable alternative to Appendix B. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. 4.2-24 Revision 3 - March 2007 In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications