Document: NUREG-0800
Document ID: ef80f444-3259-4db1-b721-096a73435ff7
Document Type: srp
Title: CONTAINMENT LEAKAGE TESTING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070464.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.6
CFR Part: 
CFR Title: 

Content:
conducted, reporting 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 technical specifications and that offsite radiation doses in excess of the guideline doses specified in 10 CFR Part 100 will not occur.32 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. 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, the potential for leakage from the containment vessel must be considered as an integral aspect of determining the acceptability of the site. DRAFT Rev. 3 - April 1996 6.2.6-6 Addressing engineering safety features collectively (including reactor containment) provides assurance that the guideline doses specified in 10 CFR Part 100 will not be exceeded should an accident occur.33 6. 10 CFR 100.11 specifies the manner in which exclusion area distance, low population zone distance, and population center distance are determined for a proposed nuclear plant site. The containment leakage rate is one of the factors considered when calculating radiation doses associated with accidents. Radiation doses thus calculated determine the acceptability of the exclusion area distance, low population zone distance, and population center distance. Verifying the containment leakage rate by means of periodic testing provides assurance that the leakage rate will remain below values assumed in the accident analysis conducted to determine the acceptability of the nuclear power plant site and that offsite radiation doses will be within the guideline doses specified in 10 CFR Part 100. 34 III. REVIEW PROCEDURES At the CP stage, the CSBSCSB will review