Document: NUREG-0800
Document ID: 1f4dbda0-7bea-416c-9d89-910450ba3299
Document Type: srp
Title: provide further guidance on the use of OBE.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12353A377.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.2
CFR Part: 
CFR Title: 

Content:
e 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apply to reviews of applications submitted 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced RGs. VI. REFERENCES 1. 10 CFR 50.55a, “Codes and Standards.” 2. 10 CFR 50.65, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.” 3. 10 CFR Part 50, Appendix A, GDC 1, “Quality Standards and Records.” 4. 10 CFR Part 50, Appendix A, GDC 2, “Design Bases for Protection Against Natural Phenomena.” 3.8.3-37 Draft Revision 4 - December 2012 5. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Basis.” 6. 10 CFR Part 50, Appendix A, GDC 5, “Sharing of Structures, Systems, and Components.” 7. 10 CFR Part 50, Appendix A, GDC 50, “Containment Design Bases.” 8. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 9. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 10. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 11. ACI 349, “Code Requirements for Nuclear Safety Related Concrete Structures,” American Concrete Institute.