Document: NUREG-0800
Document ID: 3e1b34e6-0e9d-4d8f-9338-98860adfc499
Document Type: srp
Title: CONCRETE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070570009.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
, General Design Criterion 16, “Containment Design.” 8. 10 CFR Part 50, Appendix A, General Design Criterion 50, “Containment Design Basis.” 9. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 10. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 11 10 CFR Part 50, Appendix J, “Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors.” 12. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 13. ASCE 4-98, “Seismic Analysis of Safety-Related Nuclear Structures and Commentary,” American Society of Civil Engineers (Sections 3.1.3 and C3.1.3 for concrete cracking, and Section 3.5.3.2 for embedded walls). 14. American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Section III, “Code for Concrete Reactor Vessels and Containments,” Division 2, “Code for Concrete Reactor Vessels and Containments.” New York, NY. 15. American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Subsection IWE, “Requirements for Class MC and Metallic Liners of Class CC Concrete Components of Light-Water Cooled Power Plants.” New York, NY. 16. American Society of Mechanical Engineers. Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components.” Subsection IWL, “Requirements for Class CC Concrete Components of Light-Water Cooled Plants.” New York, NY. 17. Institute of Electrical and Electronics Engineers., “IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations,” Appendix D, “Test Duration and Number of Cycles,” IEEE 344-1987. June 1987. 18. U.S. Nuclear Regulatory Commission. “Containment Integrity Research at Sandia National