Document: NUREG-0800
Document ID: a2d035da-992b-42e8-894f-787a019b437d
Document Type: srp
Title: NUCLEAR DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070410.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.3
CFR Part: 
CFR Title: 

Content:
m 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, and c. That no single malfunction of the reactivity control system causes violation of the fuel design limits. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.37 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 38 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.39 Review procedure III.3.e applies to reviews for all new applications.40 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design.";41 2. 10 CFR Part 50, Appendix A, General Design Criterion 11, "Reactor Inherent Protection."; 3. 10 CFR Part 50, Appendix A, General Design Criterion 12, "Suppression of Reactor Power Oscillations."; DRAFT Rev. 3 - April 1996 4.3-18 4. 10 CFR Part 50, Appendix A, General Design Criterion 13, "Instrumentation and Control."; 5. 10 CFR Part 50, Appendix A, General Design