Document: NUREG-0800
Document ID: 55688d47-80f6-498a-af38-5bfb9d7420aa
Document Type: srp
Title: Revision 3 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740004.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
listically, considering equipment design limitations and test sensitivities. This value should be used in calculating the offsite radiological consequences of postulated LOCAs and in setting technical specification limits with margin for bypass leakage. 7. There should be provisions for preoperational and periodic leakage rate testing similar to the Type B or C tests of 10 CFR Part 50, Appendix J, for each bypass leakage path listed in item 5. An acceptable alternative for local leakage rate testing for welded joints would be a soap bubble test of the welds concurrently with the integrated (Type A) leakage test of the primary containment required by Appendix J. Any detectable leakage determined would require repair of the joint. 8. If air or water sealing systems or leakage control systems are proposed to process or eliminate leakage through valves, these systems should be designed, to the extent practical, according to the guidelines for leakage control systems in RG 1.96. BTP 6-3-4 Revision 3 - March 2007 9. If a closed system is proposed as a leakage boundary to preclude bypass leakage, then the system should: A. Either (a) not directly communicate with the containment atmosphere or (b) not directly communicate with the environment following a LOCA. B. Be designed in accordance with Quality Group B standards, as defined by RG 1.26. (Systems designed to Quality Group C or D standards that qualify as closed systems to preclude bypass leakage will be considered case by case.) 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