ML19338F022

Proposed Tech Specs 3/4.6.1.5-3/4.6.1.7 Re Containment Sys

ML19338F022
Person / Time
Site:	Farley
Issue date:	09/30/1980
From:	ALABAMA POWER CO.
To:
Shared Package
ML19338F021	List: ML19338F020 ML19338F022
References
NUDOCS 8010070398
Download: ML19338F022 (1)

Text

, - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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 l consistent with the accident analyses. l 3/4.6.1.5 AIR TEMPERATURE l

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 l the facility. Structural integrity is required to ensure that the contair ent I 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.

1 -- - . ~.____.-,_ --

yr-,.,,,,,

g[

u, o , s . . s . . . , . , - . a .. u - , _ ,m -- . . . - . - . . , . - . > m M 4g k ...w a w,,- -,;~ -n.. -,,~ a u, ~ l O

FARLEY-UNIT 2 B 3/4 6-2 8 81007

• 3'15