Document: NUREG-0800
Document ID: 00049a4f-6345-4415-8ec0-0e63d8d04990
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070482.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
entified above are as follows: 1a. In meeting the requirements of General Design Criteria 16, 38, and 50 regarding the 23 functional capability of the containment and associated heat removal system to preserve containment integrity under postulated high-energy line break accident conditions, the containment pressure and temperature response should be calculated using the LOTIC-1 (or an equivalent) computer code (Reference. 2522). 24 For plants under review for construction permits, the containment design pressure should provide at least a 20% margin above the highest calculated accident pressure. For plants under review for operating licenses, the highest calculated accident pressure should not exceed the design pressure of the containment. The containment pressure and temperature response to postulated secondary system pipe ruptures should be based on the most severe single active failure of the isolation provisions in the secondary system (e.g., main steam isolation valve failure or feedwater line isolation valve failure). The analysis should also be based on a spectrum of pipe break sizes and reactor power levels. The accident conditions selected should result in the highest calculated containment pressure or temperature, depending on the purpose of the analysis. Acceptable methods for the calculation of the containment environmental response to main steam line break accidents are found in NUREG-0588 (Reference. 35 29). 25 2b. In meeting the requirements of General Design Criterion 50 regarding the integrity of containment internal structures, the containment subcompartment or control volume 6.2.1.1.B-5 DRAFT Rev. 3 - April 1996 differential (internal) pressures should be calculated using the Transient Mass Distribution (TMD) computer code as described in the proprietary report WCAP-807726 (Reference. 2219) , without the augmented critical flow correlation. The TMD 27 calculation should incorporate the heat transfer correlation developed from the 1974 28