Document: NUREG-0800
Document ID: 855b2438-2ddf-48e9-8762-e39097109e12
Document Type: srp
Title: FUEL SYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340660.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.2
CFR Part: 
CFR Title: 

Content:
quirements of this SRP section and that the evaluation supports conclusions of the following type, to be included in the staff's safety evaluation report: 4.2-13 Rev. 2 - July 1981 The staff concludes that the fuel system of the plant has been designed so that (a) the fuel system will not be damaged as a result of normal operation and anticipated operational occurrences, (b) fuel damage during postulated accidents would not be severe enough to prevent control rod insertion when it is required, and (c) core coolability will always be main- tained, even after severe postulated accidents and thereby meets the related requirements of 10 CFR Part 50, §50.46; a0 CFR Part 50, Appendix A, General Design Criteria 10, 27 and 35; 10 CFR Part 50, Appendix K; and 10 CFR Part 100. This conclusion is based on the following: 1. The applicant has provided sufficient evidence that these design objectives will be met based onoperating experience, prototype testing, and analytical predictions. Those analytical predictions dealing with structural response, control rod ejection (PWR) or drop (BWR), and fuel densification have been performed in accordance with (a) the guidelines of Regulatory Guides 1.60, 1.77, and 1.126, or methods that the staff has reviewed and found to be acceptable alternatives to those Regulatory Guides, and (b) the guidelines for !'Evaluation of Fuel Assembly Structural Response to Externally Applied Forces" in Appendix A 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 on-line 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