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