Document: NUREG-0800
Document ID: bc3e4db6-5bf3-4ccc-95dd-955e48799612
Document Type: srp
Title: CONTAINMENT LEAKAGE TESTING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070620007.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.6
CFR Part: 
CFR Title: 

Content:
age rates and is compatible with current leakage rate test methods and test acceptance criteria. Therefore, the minimum acceptable design containment leakage rate should not be less than 0.1% per day. 5. 10 CFR 100.10 addresses factors to be considered when evaluating nuclear power plant sites and includes the safety features that are engineered into the facility. The secondary containment of dual-type containments, which provide for a controlled, filtered release to the environs of leakage from the primary reactor containment, is such an engineered safety feature, whose effectiveness should be periodically tested as stated in Appendix J, Option A, in Section IV.B.; Option B plants should also be tested in 6.2.6-4 Revision 3 - March 2007 the same way. In so doing, the leakage limit of the secondary containment is acceptable if it is based on the limit used in the analysis of the secondary containment depressurization time. The test should be conducted at each refueling outage or at a comparable frequency. The test limit should be consistent with the limit used for direct leakage in the analysis of the radiological consequences by the organization responsible for analysis of radiological consequences. Potential bypass leak paths (identified in accordance with Branch Technical Position 6-3, "Determination of Bypass Leakage Paths in Dual Containment Plants") should be locally leakage rate tested in accordance with the requirements of Appendix J. 6. The reactor containment leakage rate testing program, as described in the safety analysis report (SAR) or design certification document (DCD), will be acceptable if: A. Under Option A, it meets the requirements stated in Option A of Appendix J to 10 CFR Part 50. Appendix J, Option A, provides the test requirements and acceptance criteria for preoperational and periodic leakage rate testing of the reactor containment and of systems and components which penetrate the containment. Exemption from Appendix J requirements will be