ML20207R452

Proposed Tech Specs,Extending Exception Re Automatic Opening of RCIC Injection Valve Until 871031

ML20207R452
Person / Time
Site:	Perry
Issue date:	03/09/1987
From:	CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20207R440	List: ML20207R452
References
NUDOCS 8703170240
Download: ML20207R452 (1)

Text

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PLANT SYSTEMS

( 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM LIMITING CONDITION FOR OPERATION

.; 6

- 3.7.3 The reactor core isolation cooling (RCIC) system shall be OPERABLE with c an OPERA 8LE Wlow path capable of automatically taking suction from the sup-pression pool and transferring the water to the reactor pressure vessel.

APPLICABILITY: 0PERATIONAL CONDITIONS 1, 2 and 3* with reactor steam dome pressure greater than 150 psig.

ACTION:

With the RCIC system inoperable, operation may continue provided the HPCS system is OPERABLE; restore the RCIC system to OPERABLE status within 14 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS , 4.7.3 The RCIC system shall be demonstrated 0PERABLE:

h a. At least once per 31 days by:

1. Verifying by venting at the high point vents that the system piping from the pump discharge valve to the system isolation y valve is filled with water.

2. Verifying that each valve, manual, power operated or automatic '

in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position. .

3. Verifying that the pump flow controller is in the correct position. ,

b. When tested pursuant to Specification 4.0.5 by verifying that the RCIC pump develops a flow of greater than or equal to 700 gpm in the test flow path with a system head corresponding to reactor vessel operating pressure when steam is being supp* lied to the turbine at 1020 + 25 - 100 psig (steam dome pressure);

e703170240 B70309 PDR ADOCK 05000440 P PDR ,

• The provisions of Specifica. tion 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is

, adequate to perform the test.

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