Document: NUREG-0800
Document ID: e708512f-f35c-453e-9fc1-354ab0bf12ad
Document Type: srp
Title: STEEL CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550050.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.2
CFR Part: 
CFR Title: 

Content:
quations of this SRP section. 3. The determination of loads generated by pressure under accident conditions is performed in accordance with SRP Section 6.2.1. The loads thus generated are accepted for inclusion in the load combinations in this SRP section. 3.8.2-8 Revision 2 - March 2007 4. The review for quality assurance is coordinated and performed in accordance with SRP Chapter 17. 5. The exclusion of postulated pipe ruptures from the design basis is generally referred to as the leak before break. The review of those applications that propose to eliminate consideration of design loads associated with the dynamic effects of pipe rupture is performed in accordance with SRP Section 3.6.3. 6. The reviews of containment performance and the satisfaction of severe accident criteria are performed in accordance with SRP Section 19.0. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.55a and 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 1 as they relate to designing, fabricating, erecting, testing, and inspecting steel containments to quality standards commensurate with the importance of the safety function to be performed 2. GDC 2, as it relates to designing steel containments to be capable of withstanding the most severe natural phenomena such as winds, tornados, floods, and earthquakes and the appropriate combination of all loads 3. GDC 4, as it relates to the capability of steel containments to withstand the dynamic effects of equipment failures, including missiles, pipe whipping, and blowdown loads associated with LOCAs 4. GDC 16, as it relates to the capability of the steel containment to act as a leaktight membrane to prevent the uncontrolled release of radioactive effluents to the environment 5. GDC 50, as it relates to designing steel