Document: NUREG-0800
Document ID: d0dc4b96-4c89-45ee-909a-04dace284668
Document Type: srp
Title: FOUNDATIONS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100621093.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.5
CFR Part: 
CFR Title: 

Content:
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apply to reviews of applications submitted 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced RGs include the implementation schedules for conformance to parts of the method discussed herein. 3.8.5-17 Revision 3 - May 2010 VI. REFERENCES 1. 10 CFR 50.55(a), ACodes and Standards.@ 2. 10 CFR 50.65, AMonitoring the Effectiveness of Maintenance at Nuclear Power Plants.@ 3. 10 CFR Part 50, Appendix A, General Design Criterion 1, AQuality Standards and Records.@ 4. 10 CFR Part 50, Appendix A, General Design Criterion 2, ADesign Bases for Protection Against Natural Phenomena.@ 5. 10 CFR Part 50, Appendix A, General Design Criterion 4, AEnvironmental and Dynamic Effects Design Bases.@ 6. 10 CFR Part 50, Appendix A, General Design Criterion 5, ASharing of Structures, Systems and Components.@ 7. 10 CFR Part 50, Appendix B, AQuality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.@ 8. 10 CFR Part 50, Appendix S, AEarthquake Engineering Criteria for Nuclear Power Plants.@ 9. 10 CFR Part 52, AEarly Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.@ 10. American Concrete Institute, ACI 349, ACode Requirements for Nuclear Safety-Related Concrete Structures.@ 11. ANSI/AISC N690-1994 including Supplement 2 (2004), ASpecification for the Design, Fabrication and Erection of Steel Safety-Related Structures for Nuclear Facilities.@ 12. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, Division 2, ACode for Concrete Reactor Vessels and Containments.@