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:
alve leakage is within acceptable limits. 10 CFR Part 100, § 100.11 requires that, as an aid in evaluating a proposed nuclear power plant 14 site, an applicant should assume the expected demonstrable leak rate from the containment. Nuclear power plant leak testing experience shows that a design leak rate of 0.1% per day provides adequate margin above typically measured containment leak rates and is compatible with current leak test methods and test acceptance criteria. Therefore, the minimum acceptable design containment leakage rate shall not be less than 0.1% per day. 6.2.6-3 DRAFT Rev. 3 - April 1996 10 CFR Part 100, §100.1 100.10 addresses factors to be considered when evaluating nuclear 15 power plant sites and includes the safety features that are engineered into the facility. The secondary containment of dual-type containments, which provide for a controlled, filtered release to the environs of leakage from the primary reactor containment, is such an engineered safety feature, whose effectiveness must be periodically verified as required by Appendix J in Section IV.B. In so doing, the leakage limit of the secondary containment is acceptable if it is based on the limit used in the analysis of the secondary containment depressurization time. The test should be conducted at each refueling or at intervals not exceeding 18 months. The test limit should be consistent with the limit used for direct leakage in the analysis of the radiological consequences by Accident Evaluation Branch (AEB)the Emergency Preparedness and Radiation Protection Branch (TERB). Potential bypass leak paths (identified in accordance with Branch 16 Technical Position CSB 6-3, "Determination of Bypass Leakage Paths in Dual Containment 17 Plants") should be locally leak tested in accordance with the requirements of Appendix J. Appendix J in Section III.A.1(a) requires that no adjustment be made to the containment prior to the performance of the containment integrated leak rate test (CILRT) so