Document: NUREG-0800
Document ID: dfd1fbdb-0dd1-46f4-8489-99de53d66afc
Document Type: srp
Title: OTHER SEISMIC CATEGORY I STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550054.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.4
CFR Part: 
CFR Title: 

Content:
ctions, 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 3.8.4-18 Revision 2 - March 2007 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced regulatory guides contain implementation schedules for conformance to parts of the method discussed in this section. 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, General Design Criterion 1, “Quality Standards and Records.” 4. 10 CFR Part 50, Appendix A, General Design Criterion 2, “Design Bases for Protection Against Natural Phenomena.” 5. 10 CFR Part 50, Appendix A, General Design Criterion 4, “Environmental and Dynamic Effects Design Bases.” 6. 10 CFR Part 50, Appendix A, General Design Criterion 5, “Sharing of Structures, Systems, and Components.” 7. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 8. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 9. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 10. ACI 349, “Code Requirements for Nuclear Safety Related Concrete Structures,” American Concrete Institute. 11. ANSI/AISC N690-1994, including