ML022700533
| ML022700533 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/24/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB3941 | |
| Download: ML022700533 (1) | |
Text
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.16 Reactor Building Leakage Rate Testing Program 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, except that the next Type A test performed after the April 16, 1992 Type A test shall be performed no later than April 15, 2007.
In addition, the reactor building purge supply and exhaust isolation valves shall be leakage rate tested once prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days.
The peak calculated reactor building internal pressure for the design basis loss of coolant accident, P0, is 54 psig The maximum allowable reactor building leakage rate, La, shall be 0.20% of containment air weight per day at Pa.
Reactor Building leakage rate acceptance criteria is < 1.OLa. During the first unit startup following each test performed in accordance with this program, the leakage rate acceptance criteria are < 0.6 0L, for the Type B and Type C tests and < 0 75La for Type A tests.
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Reactor Building Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Reactor Building Leakage Rate Testing Program.
Amendment No. 24-5, 219 ANO-1 5.0-25