Document: NUREG-0800
Document ID: a2b44b5a-11f2-451e-bbde-778c3381cda7
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12353A365.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
ds, 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