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:
DC 54 are imposed so that unanticipated leakage from piping systems penetrating the reactor containment will not occur during the recovery period that follows a LOCA. Such leakage would compromise the ability of the system to limit the release of fission products to the environment. Meeting this requirement provides assurance that piping systems penetrating the reactor containment will not be an additional source of leaking fission products and, hence, that releases of fission products off site will not result in radiation doses in excess of the reference values specified in 10 CFR Part 100. 4. Appendix J to 10 CFR Part 50 specifies requirements and acceptance criteria for preoperational and periodic testing of the leaktightness of the reactor containment and penetrations. Appendix J applies to this SRP section because it contains detailed requirements concerning the manner in which the reactor containment and its parts must be tested. These tests include (a) periodic CILRTs, (b) local testing of containment penetration leakage rates, and (c) local testing of isolation valve leakage rates. Appendix J includes pertinent information on the frequency of testing, pressures at which tests will be conducted, recording of test results, and acceptance criteria for testing. Meeting the requirements of Appendix J to 10 CFR Part 50 provides assurance that the leaktightness of the containment will be within the values specified in the facility 6.2.6-8 Revision 3 - March 2007 technical specifications and that offsite radiation doses in excess of the reference valves specified in 10 CFR Part 100 will not occur. 5. 10 CFR 100.10 focuses on factors to be considered when evaluating potential sites for nuclear power plants. Safety features engineered into the nuclear reactor plant constitute one such factor. The reactor containment is an engineered safety feature that, as specified by 10 CFR Part 100, must be considered when evaluating potential sites for nuclear power plants. Thus,