Document: NRC Regulatory Guide
Document ID: 74c49394-8dbf-46e7-b62a-b85de93b47d8
Document Type: regulatory_guide
Title: Initial Test Programs for Water-Cooled Nuclear Power Plants + HISTORY - HISTORY 11/2012 – DG-1259 , Proposed Revision 4 11/2006 – DG-1166 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1229/ML12298A071.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.68
CFR Part: 
CFR Title: 

Content:
on devices perform as required under simulated accident conditions. The following list illustrates the systems, features, and performance demonstrations that should be included in the test program: 1. containment design overpressure structural tests12 and vacuum tests for sub- atmospheric containments; 2. containment isolation valve functional and closure timing tests; 3. containment isolation valve leak rate tests13 and in-leakage tests for sub- atmospheric containments; 4. containment penetration leakage tests13; 5. containment airlock leak rate tests13; 6. integrated containment leakage tests13; 7. main steam-line leakage sealing and feedwater leakage sealing systems (BWR); 8. primary and secondary containment isolation initiation logic tests; 9. containment purge system tests; 10. containment and containment annulus vacuum breaker tests (BWR); 11. containment supplementary leak collection and exhaust system tests; 12. containment air purification and cleanup system tests; 13. containment inerting system tests; 14. standby gas treatment system tests; 15. containment penetration pressurization system tests; 16. containment ventilation system tests; 17. secondary containment system ventilation tests; 18. containment annulus and cleanup system tests, including demonstrating the ability to maintain design pressure control in all modes of operation; 19. bypass leakage tests on pressure suppression containments; 20. ice condenser containments (sufficient measurements should be made to ensure that gross bypass leakage paths are not present); and 12 Overpressure structural tests should be conducted in accordance with Section III of the ASME BPV Code. 13 The requirements for such tests are given in Appendix J, “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” Appendix A to DG-1259, Page A-12 21. containment penetration cooling system tests. In general,