Document: NUREG-0800
Document ID: 048d2078-58a2-440a-a58f-f456e6c8dec8
Document Type: srp
Title: CONTAINMENT LEAKAGE TESTING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340706.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.6
CFR Part: 
CFR Title: 

Content:
f has reviewed and found to be acceptable; c. meeting the regulatory position in BTP __; 6.,2.6-5 Rev. 2 - July 1981 d. using calculational methods for (state what evaluated) that have been previously reviewed by the staff and found acceptable; the staff has reviewed the impact parameters in this case and found them to be suitably conservative or performed independent calcu- lations to verify acceptability of their analysis; and/or e. meeting the provisions of (industry standard number and title) that have been reviewed by the staff and determined to be appro- priate for this application. 2. Repeat discussion for each regulation cited above. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding NRC staff plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alterna- tive method for complying with specified portions of the Commission's regula- tions, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. VI. REFERENCES 1. 10 CFR Part 50, Appendix J, "Primary Reactor Containment for Water-Cooled Power Reactors." Leakage Testing 2. 10 CFR Part 50, Appendix A, General Design Containment Leakage Rate Testing." 3. 10 CFR Part 50, Appendix A, General Design Containment Testing and Inspection." 4. 10 CFR Part 50, Appendix A, General Design ting Containment." Criterion 52, "Capability for Criterion 53, "Provisions for Criterion 54, "Systems Penetra- 5. 10 CFR Part 100, "Reactor Site Criteria." I 6.2.6-6 Rev. 2 - July 1981