Document: NUREG-0800
Document ID: b486e8d3-c8b0-4990-b7ec-211a3aae25c3
Document Type: srp
Title: CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070456.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1
CFR Part: 
CFR Title: 

Content:
ainment are given in General Design Criteria 54 thru 57. The General Design Criteria provide design requirements for the installation of containment isolation valves on piping lines that penetrate the containment barrier. 8 For new plant applicants and those PWRs subject to the guidance contained in reference 45 (Generic Letter 88-17), the containment analyses should also consider shutdown conditions, when appropriate, to ensure that a basis is provided for procedures, instrumentation, operator response, equipment interactions and equipment response. The analyses should encompass shutdown thermodynamic states and physical configurations to which the plant can be subjected during shutdown conditions (such as time to core uncovery during a loss of shutdown decay heat removal capability) and should provide sufficient depth such that adequate bases can be developed (see Reference 46).9 There are a number of different containment types and designs, and several aspects of 10 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) dry containments, including sub-atmospheric containments (SRP Section 6.2.1.1.A). 2. Ice condenser containments (SRP Section 6.2.1.1.B). 3. Mark I, II, and III, and ABWR boiling water reactor (BWR) pressure-suppression type 11 containments (SRP Section 6.2.1.1.C). 6.2.1-3 DRAFT Rev. 3 - April 1996 4. Subcompartment analysis (SRP Section 6.2.1.2). 5. Mass and energy release analysis for postulated loss-of-coolant accidents (SRP Section 6.2.1.3). 6. Mass and energy release analysis for postulated secondary system pipe ruptures (SRP Section 6.2.1.4). 7. Minimum containment pressure analysis for emergency core cooling system (ECCS) performance capability studies (SRP Section 6.2.1.5). A separate SRP section has been prepared for each of these