ML19338F022
| ML19338F022 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/30/1980 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19338F021 | List: |
| References | |
| NUDOCS 8010070398 | |
| Download: ML19338F022 (1) | |
Text
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ENCLOSURE 2 CONTAINMENT SYSTEMS BASES i
The maximum peak pressure expected to be obtained from a LOCA event is 45 psig.
The limit of 3 psig for initial positive containment pressure will i
limit the total pressure to 48 psig which is less than design pressure and is consistent with the accident analyses.
3/4.6.1.5 AIR TEMPERATURE lThelimitationsoncontainmentaverageairtemperatureensurethatthe overall containment average air temperature does not exdeed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.
3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility.
Structural integrity is required to ensure that the contair ent will withstand the maximum pressure of 48 psig in the event of a LOCA. Th:
i visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test, along with the data obtained from Unit 1 tendon surveillance, is sufficient to demonstrate this capability.
The surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of paragraph C.1.3 of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures," January 1976.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves.are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.
Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge _ system.
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