B14391, Proposed TS 4.6.1.2 Re Calculating Containment Integrated Leakage Rates During Surveillance Testing
| ML20034H682 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/16/1993 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20034H679 | List: |
| References | |
| B14391, NUDOCS 9303190226 | |
| Download: ML20034H682 (2) | |
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Docket No.-50-213
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Proposed Revision to Technical Specification
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7, CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of less than or equal to La, 0.18 % by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, 39.6 psig, or b.
A combined leakage rate of less than 0.60 La for all penetrations and valves subject to Type B and C tests, when pressurized to Pa.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION With either the measured overall integrated. containment leakage rate exceeding 0.75 La or. the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.6g La prior to increasing the Reactor Coolant System temperature above-200 F.
SURVEILLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule, and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using ANSI N45.4-1972 (Total Time Method), ANSI 56.8 (Mass Point Method), or the Total Time Method from BN-TOP-1, Revision 1-1972, during the Type A and verification test.
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shall be conducted at 40 i 10 month intervals during shutdown at a pressure not less than Pa, 39.6 psig during each 10-year service period.
The third test of each set shall be conducted during the shutdown for the 10-year plant inservice' inspection; i
HADDAM NECK 3/4 6-2 Amendment No. J U,
0344