ML050970213
| ML050970213 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/06/2005 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML050970213 (1) | |
Text
ADMINISTRATIVE CONTROLS 6.19 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the primary containment as required by 1 OCFR50.54(o) and 1 OCFR50, 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 Performance-Based Option of 10 CFR Part 50, Appendix 3": The first Type A test performed after the June 10, 1995 Type A test shall be performed no later than June 10, 2010.
The peak calculated primary Containment internal pressure for the design basis loss of coolant accident is P8.
The maximum allowable primary containment leakage rate, La, at Pas is 0.5% of primary containment air weight per day.
Leakage rate acceptance criteria are:
- a.
Primary containment overall leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the combined Type B and Type C tests, and < 0.75 La for Type A tests;
- b.
Air lock testing acceptance criteria are:
- 1. Overall air lock leakage rate is *0.05 La when tested at 2 Pa.
- 2. For each door, pressure decay is *0.1 psig when pressurized to Ž25 psig for at least 15 minutes.
The provisions of SR 4.0.2 do not apply for test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of SR 4.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
6.20 RADIOACTIVE EFFLUENT CONTROLS PROGRAM This program conforms to 10 CFR'50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- a.
Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the REMODCM;
- b.
Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to IOCFR 20.1001-20.2402; MILLSTONE - UNIT 2 6-26 Amendment No. 2IG, I, 276, 285