ML032270445
| ML032270445 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/14/2003 |
| From: | NRC/NRR/DLPM/LPD1 |
| To: | |
| References | |
| TAC MB6487 | |
| Download: ML032270445 (1) | |
Text
6.8.5 Reactor Buildinc Leakage Rate Testing Program The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained as follows:
A program shall be established to Implement the leakage rate testing of the Reactor Building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J":
- a.
Section 9.2.3: The first Type A test performed after the September 1993 Type A test shall be performed no later than September 2008.
The peak calculated Reactor Building internal pressure for the design basis loss of coolant accident, Pac, is 50.6 psig.
The maximum allowable Reactor Building leakage rate, La, shall be 0.1 weight percent of containment atmosphere per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa:.
Reactor Building leakage rate acceptance criteria is s 1.0 La. During the first plant startup following each test performed in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the Type B and Type C tests and s 0.75 La for the Type A tests.
6-11c Amendment No. 241, 244