Document: NUREG-0800
Document ID: ddaa3c7d-ce79-4a3f-aaae-4e4436ab7bc1
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740003.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
CFR Part: 
CFR Title: 

Content:
rences, have met fuel design criteria. B. That the automatic initiation of the RCS assures that fuel design criteria are not exceeded as a result of anticipated operational occurrences and assures the automatic operation of systems and components important to safety under accident conditions. C. That no single malfunction of the RCS causes violation of the fuel design limits. 8. 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. 9. 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 submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Review procedure III.3.E applies to reviews for all new applications. 4.3-20 Revision 3 - March 2007 VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 2. 10 CFR Part 50, Appendix A, General Design Criterion 10, “Reactor Design.” 3. 10 CFR Part 50, Appendix A, General Design Criterion 11, “Reactor Inherent Protection.” 4. 10 CFR Part 50, Appendix A, General Design Criterion 12, “Suppression of Reactor Power Oscillations.” 5. 10 CFR Part 50, Appendix A, General Design Criterion 13, “Instrumentation and