05000293/LER-1980-030-03, /03L-0:on 800725,relief Valve 203-3D Did Not Respond When Control Switch Was Placed to Open Position at Reactor Pressure of 970 Psig.Caused by Locktite Dripping Along Face of Plunger,Binding Plunger & Bonnet Together

/03L-0:on 800725,relief Valve 203-3D Did Not Respond When Control Switch Was Placed to Open Position at Reactor Pressure of 970 Psig.Caused by Locktite Dripping Along Face of Plunger,Binding Plunger & Bonnet Together

ML19330B472
Person / Time
Site:	Pilgrim
Issue date:	07/29/1980
From:	Mcloughlin M BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19330B470	List: 05000293/LER-1980-030, Forwards LER 80-030/03L-0 05000293/LER-1980-030-03, /03L-0:on 800725,relief Valve 203-3D Did Not Respond When Control Switch Was Placed to Open Position at Reactor Pressure of 970 Psig.Caused by Locktite Dripping Along Face of Plunger,Binding Plunger & Bonnet Together
References
LER-80-030-03L, LER-80-30-3L, NUDOCS 8008040063
Download: ML19330B472 (2)

LER-1980-030, /03L-0:on 800725,relief Valve 203-3D Did Not Respond When Control Switch Was Placed to Open Position at Reactor Pressure of 970 Psig.Caused by Locktite Dripping Along Face of Plunger,Binding Plunger & Bonnet Together

Event date:
Report date:
2931980030R03 - NRC Website

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8 60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT OATE SQ EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h Io l2l l On July 25, 1980 at approximately 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Relief Valve 203-3D did not respond l

lo Ia l l when its control switch was placed to the 'Open' position at reactor pressure of l

l o 141 l 970 psig. This operation was initiated in conjunction with torus transient pres-l Io Isl l sure testing of Refuel IV torus modifications under the guidelines specified in

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lo Is l l PNPS Temporary Procedure No. 80-65.

The valve solenoid assembly was removed and anl lo l7l l "in kind" replacement. installed. During the July 26, 1980 startup following the l

l o Ia 1 l planned maintenance outage the valve was tested at 160 psig.

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NAME OF PREPARER PHONE:

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET No. 50-293 Attachment'to LER 80-030/03L.

On July 25, 1980 at approximately 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> Relief Valve 203-3D did not respond when'its control switch was placed to the 'Open' position at reactor pressure of 970 psig. -This operation was initiated in conjunction with torus transient pressure testing of Refuel IV torus modifications under the guidelines specified in PNPS Temporary Procedure No. 80-65.

Relief Valves 203-3B & C were opened to verify operability and both functioned as required.

The plant was shutdown at 0555 on July 25, 1980 and a drywell entry was made to investigate. Upon investigation, air was observed to be blowing out the solenoid bleed port. The solenoid valve was removed and transported to the shop. Disassembly and analysis by factory representatives determined that the cause of_the solenoid's assembly malfunction was that "Locktite" dripped along the face of the assembly's plunger and collected on the OD/ID clearance of the plunger / bonnet and bound them together.

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An "in kind" solenoid was installed on RV-203-3A & D.

RV-203-3A solenoid valve was replaced because it had not been tested prior to shutdown and a small amount

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of leakage was observed. Relief Valve 203-3D was tested during the subsequent startup at 160 PSIG. The first time the switch'was placed to open nothing happened. Two additional opening sequences were conducted and both times the valve functioned as required. No apparent reason has been determined for why the valve did not open on the first try.

Personnel in the control room at the time could not be certain if they had received open indication, therefore, the switching ' sequence may not have been completed.

Relief ' alve 203-3A opened satisfactorily-on the first attempt.

To ensure proper v

operation of the newly installed solenoid assembly the drywell was entered and the valve assembly inspected at 600 psig. There was no evidence of leakage at the-bleed port of any Relief Valve Solenoid.

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