Document: NRC Regulatory Guide
Document ID: 4774af39-208c-4761-97e8-2d66c6d14794
Document Type: regulatory_guide
Title: Performance-Based Containment Leak-Test Program (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2200/ML22006A317.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.163
CFR Part: 
CFR Title: 

Content:
nce-Based Requirements” in Appendix J, “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,” to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities” (Ref. 1). Applicability This RG applies to reactor licensees and applicants subject to 10 CFR Part 50, Appendix J, and 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2). Applicable Regulations • 10 CFR Part 50 provides regulations for licensing production and utilization facilities. o 10 CFR 50.54(o) provides a condition that primary reactor containments shall meet the containment leakage test requirements in 10 CFR Part 50, Appendix J. o 10 CFR 50.55a specifies requirements for inservice inspection programs. o 10 CFR 50.90, “Application for amendment of license, construction permit, or early site permit,” requires an application whenever a holder of a license desires to amend the license or permit. o 10 CFR Part 50, Appendix J, specifies requirements and acceptance criteria for preoperational and periodic testing of the leak tightness of the reactor containment and penetrations. DG-1391, Page 2 • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. o 10 CFR 52.79(a)(12) requires, in part, that combined license applicants describe the primary containment leak rate test program to ensure the requirements of 10 CFR Part 50, Appendix J, are met. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” Chapter 6, “Engineered Safety Features,” Section 6.2.6, “Containment Leakage Testing” (Ref. 3), gives guidance on an acceptable containment leakage rate testing program and leakage rate test methods, procedures, and analyses that may be