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:
itute 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, the potential for leakage from the containment vessel must be considered as an integral aspect of determining the acceptability of the site. Addressing engineering safety features collectively (including reactor containment) provides assurance that the reference values specified in 10 CFR Part 100 will not be exceeded should an accident occur. 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 reference values specified in 10 CFR Part 100. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. At the CP or design certification stage, the preliminary design provisions that will permit containment leakage rate testing to be done in accordance with the requirements of Appendix J are reviewed.