Document: NUREG-0800
Document ID: 7e0d3b3e-62c3-4492-ba89-6cebb4e82234
Document Type: srp
Title: SECONDARY CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340701.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.3
CFR Part: 
CFR Title: 

Content:
. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of con- formance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases." 2. 10 CFR Part 50, Appendix A, General Design Criterion 16, "Containment Design." 6.2.3-7 Rev. 2 - July 1981 3. 10 CFR Part 50, Appendix A, General Design Criterion 43, "Testing of Con- tainment Atmosphere Cleanup Systems." 4. R. J. Wagner and L. L. West, "CONTEMPT-LT Users Manual," Interim Report I-214-74-12.1, Aerojet Nuclear Company, August 1973. 5. Branch Technical Position CSB 6-3, "Determination of Bypass Leakage Paths in Dual Containment Plants," attached to this SRP section. 6. Branch Technical Position CSB 6-1, "Minimum Containment Pressure Model for PWR ECCS Performance Evaluation," attached to SRP Section 6.2.1.5. 6.2.3-8 Rev. 2 - July 1981 BRANCH TECHNICAL POSITION CSB 6-3 DETERMINATION OF BYPASS LEAKAGE PATHS IN DUAL CONTAINMENT PLANTS A. BACKGROUND The purpose of this branch position is to provide guidance in the determination of that portion of the primary containment leakage that will not be collected and processed by the secondary containment. Bypass leakage is defined as that leakage from the primary containment wkich can circumvent the secondary contain- ment boundary and escape directly to the environment, i.e., bypasses the leakage collection and filtration systems of the secondary containment. This leakage component must be considered in the radiological analysis of a loss-of-coolant accident. The secondary containment consists of a structure which completely encloses the primary containment and can be maintained at a pressure