Document: NUREG-0800
Document ID: 0c95c042-addf-4bad-84f5-1d1692769268
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550052.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
pose to eliminate consideration of design loads associated with the dynamic effects of pipe rupture is performed in accordance with SRP Section 3.6.3. 4. Determination of loads generated from pressure under accident conditions is performed in accordance with SRP Section 6.2.1. The loads thus generated are included in the load combinations in this SRP section. 5. Distribution systems including their supports (e.g., cable trays; conduit; heating, ventilation, and air conditioning) and equipment supports are reviewed in accordance with SRP Sections 3.9.2 and 3.9.3. 6. The review for quality assurance is coordinated and performed in accordance with SRP Chapter 17. The specific acceptance criteria and review procedures are contained in the reference 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 50, Appendix A, General Design Criterion (GDC) 1, as they relate to the design, fabrication, erection, and testing of containment internal structures in accordance with quality standards commensurate with the importance of the safety function to be performed. 3.8.3-15 Revision 2 - March 2007 2. GDC 2, as it relates to the ability of the containment internal structures without loss of capability to perform their safety function, to withstand the effects of natural phenomena, such as earthquakes, tornadoes, floods, and the appropriate combination of all loads. 3. GDC 4, as it relates to the protection of containment internal structures 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 5, as it relates to safety-related structures not being shared among nuclear power units, unless it can be shown that such sharing will not significantly impair their ability to perform their safety