Document: NUREG-0800
Document ID: dfd1fbdb-0dd1-46f4-8489-99de53d66afc
Document Type: srp
Title: OTHER SEISMIC CATEGORY I STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550054.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.4
CFR Part: 
CFR Title: 

Content:
red 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. 4. Determination of loads generated because of 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. 5. 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 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 structures, systems, and components 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 safety-related structures being able to withstand the most severe natural phenomena such as wind, tornadoes, floods, and earthquakes and the appropriate combination of all loads 3. GDC 4, as it relates to safety-related structures 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 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 functions 5. 10 CFR Part 50, Appendix B, as it relates to the quality assurance criteria for nuclear power plants 6. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections,