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:
ts Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1For Part 50 applicants not listed in 10 CFR 50.34(f), the provisions of 50.34(f) will be made a requirement during the licensing process. 3.8.1-8 Revision 2 - March 2007 1. 10 CFR 50.55a and GDC 1, as they relate to concrete containment being designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety function to be performed. 2. GDC 2, as it relates to the design of the concrete containment being able to withstand the most severe natural phenomena such as winds, tornadoes, floods, and earthquakes and the appropriate combination of all loads. 3. GDC 4, as it relates to the concrete containment being appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit. 4. GDC 16, as it relates to the capability of the concrete containment to act as a leak-tight membrane to prevent the uncontrolled release of radioactive effluents to the environment. 5. GDC 50, as it relates to the concrete containment being designed with sufficient margin of safety to accommodate appropriate design loads. 6. 10 CFR Part 50, Appendix B as it relates to the quality assurance criteria for nuclear power plants 7. 10 CFR 50.34(f), as it relates to demonstrating containment integrity of applicable plants for loads associated with an accidental release of hydrogen generated from metal-water reaction of the fuel cladding, accompanied by hydrogen burning or added pressure from postaccident inerting1 8. 10 CFR 50.44, as it relates to demonstrating the structural integrity of BWRs with Mark III type containments, all PWRs with ice condenser containments, and all containments used in future water-cooled reactors for loads associated with combustible gas generation 9. 10 CFR