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:
e 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 reviewed on a case-by-case basis. B. Under Option B, it meets the requirements stated in Option B of Appendix J to 10 CFR Part 50 and, under section V.B.2 and V.B.3 of Option B, either complies with methods approved by the Commission and endorsed in a regulatory guide (RG 1.163) and includes a requirement to do so in the Technical Specifications, or complies with the provisions of some other implementation document which has been adequately justified to the staff, with supporting analyses, and is cited as a requirement in the Technical Specifications. As of the publication date of this SRP revision, virtually all applicants and licensees using Option B have chosen compliance with RG 1.163, so this Standard Review Plan (SRP) is written assuming that future applicants will do the same. 7. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations. 8. 10 CFR 52.80(a), which requires that a COL application contain the proposed inspections, tests, and analyses, including those applicable to emergency planning, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will operate in conformity with the combined license, the provisions of the Atomic Energy