Document: NUREG-0800
Document ID: 30986e6c-887a-4c3b-b82a-e1a06d319fcd
Document Type: srp
Title: should be provided in a separate section of the SER.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660522.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3
CFR Part: 
CFR Title: 

Content:
2. 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. 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. 14.3.2-12 March 2007 VI. REFERENCES 1. 10 CFR 50.55a, "Codes and Standards." 2. 10 CFR 52.47 "Contents of Applications." 3. 10 CFR 52.80 "Contents of Applications." 4. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 5. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for the Protection Against Natural Phenomena." 6. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects Design Basis." 7. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 8. 10 CFR Part 50, Appendix A, General Design Criterion 16, "Containment Design." 9. 10 CFR Part 50, Appendix A, General Design Criterion 50, "Containment Design Basis." 10. 10 CFR Part 50, Appendix J, “Primary Reactor Containment leakage Testing for Water- Cooled Power Reactors.” 11. NUREG-1503, "Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor," Volumes 1 and 2, July 1994. 12. NUREG-1462, "Final Safety Evaluation Report Related to the Certification of the System 80+ Design," Volumes 1 and 2, August 1994. 13.