ML19262C674

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Revised Tech Specs 1.7-1.9 for Reactor Bldg,Fire Suppression Water Sys & Test Basis
ML19262C674
Person / Time
Site: Arkansas Nuclear 
Issue date: 06/08/1979
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19262C672 List:
References
NUDOCS 8002150376
Download: ML19262C674 (2)


Text

ATTACHMEl4T 1 REFEREf1CE:

ITEM 1 REVISED JUNE 8,1979 SUBMITTAL

1.7 REACTOR BUILDING Reactor building integrity exists when the following conditions are satisfied:

The equipment hatch is closed and sealed and both doors of the a.

personnel lock and emergency lock are closed and sealed, or b.

below.

b.

At least one door on each of the personnel lock and emergency lock is closed and sealed during personnel access or repair.

c.

All non-automatic reactor building isciction valves and blind flanges are closed as required.

d.

All automatic reactor building isolation valves are operable or deactivated in the closed position.

e.

The reactor building leakage determined at the last testing interval satisfies Specification 4.4.1.

1.8 FIRE SUPPRESSION WATER SYSTEM 30 The fire suppression water system consists of:

water sources, pumps, and distribution piping with associated sectionalizing isolation valves.

Such valves include the hose standpipe shutoff valves and the first valve ahead of the water flow alarm device or each sprinkler system.

1.9 STAGGFRED TEST BASIS A staggered test basis shall consist of:

a.

A test schedule for n systems, subsystems, trains or designated components obtained by dividing the specified test interval into n equal subintervals, b.

The testing of one system, subsystem, train or designated component at the beginning of each subinterval.

Amendment 30 5