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:
using the guidelines for leakage control systems given in Regulatory Guide 1.96 (Ref. 4). 9. If a closed system is proposed as a leakage boundary to preclude bypass leakage, then the system should: a. Either (1) not directly communicate with the containment atmosphere, of (2) not directly communicate with the environment, following a loss-of-coolant accident. b. Be designed in accordance with Quality Group B standards, as defined by Regulatory Guide 1.26. (Systems designed to Quality Group C or D standards that qualify as closed systems to preclude bypass leakage will be considered on a case-by-case basis.) c. Meet seismic Category I design requirements. d. Be designed to at least the primary containment pressure and temperature design conditions. e. Be designed for protection against pipe whip, missiles, and jet forces in a manner similar to that for engineered safety features. f. Be tested for leakage, unless it can be shown that during normal plant operations the system integrity is maintained. C. REFERENCES 1. 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." 6.2.3-11 Rev. 2 - July 1981 2. Regulatory Guide 1.26, "Quality Group Classification and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." 3. Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants." 4. Regulatory Guide 1.96, "Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants." 6.2.3-12 Rev. 2 - July 1981