Document: NUREG-0800
Document ID: acc638c2-20fb-4686-892d-e70277acd189
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070220505.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
lated rupture in the primary or secondary coolant system piping. The subsequent thermodynamic effects in the containment resulting from the release of the coolant mass and energy are determined from a solution of the incremental space and time-dependent energy, mass, and momentum conservation equations. The basic functional design requirements for containment are given in General Design Criteria (GDC) 4, 16 and 50 in Appendix A to 10 CFR Part 50 and in 10 CFR Part 50, Appendix K. GDC 4 provides the basic environmental and dynamic effects design requirements for all structures, systems, and components important to safety including leak-before-break. GDC 16 establishes the fundamental requirement to design a containment that is essentially a leak-tight barrier against the uncontrolled release of radioactivity to the environment. GDC 50, among other things, requires that consideration be given to the potential consequences of degraded engineered safety features, such as the containment heat removal system and the emergency core cooling system, the limitations in defining accident phenomena, and the conservatism of calculational models and input parameters in assessing containment design margins. 10 CFR Part 50 Appendix K.I.D.2 requires that the containment pressure used for evaluating cooling effectiveness during reflood and spray cooling shall not exceed a conservatively low value. 10 CFR 50 Appendix K.I.A can be used as guidance in ensuring that all sources of energy are included in determining the mass and energy release from loss-of-coolant accidents and Pressurized Water Reactor (PWR) secondary system pipe ruptures. There are a number of different containment types and designs and several aspects of containment functional design that are within the scope of SAR Section 6.2.1. The various containment types and aspects to be reviewed under this SRP section have been separated and assigned to a set of other SRP sections as follows: 1 Pressurized water reactor (PWR)