05000352/LER-1987-066, Forwards LER 87-066-00,correcting Date of Rept from 870107 to 880107

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Forwards LER 87-066-00,correcting Date of Rept from 870107 to 880107
ML20147C224
Person / Time
Site: Limerick Constellation icon.png
Issue date: 01/07/1988
From: Logue R
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8801190134
Download: ML20147C224 (1)
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LER-2087-066, Forwards LER 87-066-00,correcting Date of Rept from 870107 to 880107
Event date:
Report date:
3522087066R00 - NRC Website
v • d • e

text

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PHILADELPHIA ELECTRIC COMPANY ,

2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A, PA.191o1 j

ta nsi e4i 4cco j January 7, 1988 l l

Docket No. 50-352 )

Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 l

SUBJECT:

Licensee Event Report Limerick Generating Station - Unit 1 Attached is a corrected copy of LER 87-066. Coded field (7) of NRC form 366 was incorrectly dated 1/07/87 rather than 01/07/88. We regret any inconvenience this error may have caused you or your staff. This LER reports the inoperability of the High Pressure Coolant Injection System due to a malfunction of the hydraulic-mechanical overspeed trip mechanism.

Reference:

Docket No. 50-352 Report Number: 87-066 Revision Number: 00 Event Date: December 8, 1987 Report Date: January 7, 1988 Facility: Limerick Generating Station P.O. Box A, Sanatoga, PA 19464 This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(v)(d).

Very truly rs, R. H. Logue

'W Assistant to the Manager Nuclear Support Division cci W. T. Russell. Administrator, Region I, USNRC E. M. Kelly, Senior Resident Inspector, USNRC p,

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On December 8, 1987 at 1447 hours0.0167 days <br />0.402 hours <br />0.00239 weeks <br />5.505835e-4 months <br />, during the performance of surveillance test ST-6-055-230-1, "HPCI Pump, Valve And Flow Test", the High Pressure Coolant Injection (HPCI) system (an Emergency Core Cooling System) was declared inoperable due to the erratic operation of the HPCI turbine stop valve. Approximately 20 minutes into the test, while in its full flow test configuration, the HPCI stop valve unexpectedly fully closed and reopened. The stop valve continued to close and reopen several times. An immediate investigation into the cause of the problem revealed that although a HPCI turbine overspeed condition was not present, the hydraulic-mechanical overspeed trip mechanism was cycling between the tripped and normal positions. The cause of the malfunction is believed to have been a blockage of a small internal drain port in the overspeed trip and automatic reset l piston assembly. There were no adverse consequences of this event. No radioactive material was released as a result of the r event. The Automatic Depressurization System (ADS), Reactor Core

! Isolation Control (RCIC) System and the other Emergency Core Cooling Systems were operable during the event. The HPCI system l was declared operable at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on December 9, 1987 after l being inoperable for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> and 43 minutes. Increased I

surveillance of the overspeed trip mechanism has been initiated.

Appropriate procedures have beers revised to include monitoring stop valve position while the auxiliary oil pump is running.

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Operating Mode 1 (Power Operation)

Reactor Power 99%

Description of the Event:

On December 8, 1987 at 1447 hours0.0167 days <br />0.402 hours <br />0.00239 weeks <br />5.505835e-4 months <br />, during the performance of a surveillance test the High Preseure Coolant Injection (HPCI)

System (an Emergency Core Cooling System) was declared inoperable due to the erratic operation of the HPCI turbine stop valve.

Approximately 20 minutes into the performance of ST-6-055-230-1, "HPCI Pump, Valve And Flow Test", with the HPCI system operating in its full flow test configuration, the HPCI stop valve FV-56 ,

112 unexpectedly fully closed and reopened. The stop valve continued to close and reopen several times.. The test engineers and operators then made the decision to shut down the HPCI turbine and declare the HPCI system inoperable. Cycling of the HPCI stop valve continued with the turbine secured and the auxiliary oil pump running.

An immediate investigation discovered that the hydraulic portion of the hydraulic-mechanical overspeed trip mechanism was cycling to the tripped position causing the stop valve movement. The cycling of the trip mechanism stopped following manual manipulation af the reset knob. The HPCI system was unavailable for service for 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> and 43 minutes.

Consequences of the Event:

There were no adverse consequences as a result of this event. No l radioactive material was released as a result of the event. The Automatic Depressurization System (ADS), Reactor Core Isolation i

Cooling (RCIC) System and other low pressure emergency core I cooling systems were operable during this event. If the HPCI had t

been required to operate, the Automatic Depressurization System I would have responded reducing reactor pressure permitting the low pressure cooling systems to initiate.

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The erratic operation of the HPCI stop valve was caused by the cycling of the HPCI hydraulic-mechanical overspeed trip mechanism (see diagram on page 5 of this LER) to its tripoed condition.

The cause of the malfunction of the trip mechanism is believed to have been the blockage of the small internal drain port 'F' in the overspeed trip reset plunger assembly. Port 'F' performs a dual function; 1) draining hydraulic fluid from under the piston which leaks in from port 'C' during normal operation and 2) draining hydraulic fluid following a trip as part of the automatic reset function. The blockage of port 'F' would have allowed normal oil leakage to become entrapped and pressurize the ,

volume under the piston, raising it to the tripped position.

This aligned openings in the piston with ports 'C' and 'B' thereby reducing oil pressure to the pilot valve on the turbine stop valve hydraulic cylinder and closing the stop valve. The automatic reset function then operated as designed and stopped the oil flow to port 'C' and the piston repositioned re-establishing oil pressure to the pilot valve of the hydraulic cylinder and opening the stop valve. At the same time, oil pressure was re-established to port 'C' and the blocked port 'F' may have prevented the drain-off of normal oil leakage past the piston preventing it from reseating entirely. This may have once again lifted the piston to the tripped position restarting the cycle.

The hydraulic-mechanical overspeed trip mechanism is manufactured by the Terry Corporation and is detailed on page 5 of this LER.

Corrective Actions:

The HPCI system was declared inoperable at 1447 hours0.0167 days <br />0.402 hours <br />0.00239 weeks <br />5.505835e-4 months <br /> on December 8, 1987, and Technical Specification 3.5.1.c Action 'c' was entered. General Electric personnel were consulted to determine what cctrective actions to pursue. The following steps were then taken:

12/8/87 - The auxiliary oli pump was run for 20 minutes while manually cycling the overspeed mechanism and rotating the reset knob in an attempt to flush the internals of the mechanism.

12/9/87 - The reset spring force was measured and found to be within acceptable limits. .

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- The HPCI turbine was satisfactorily run for 1 hou' and 40 minutes in accordance with ST-6-055-230-1, "HPCI Pump, Valve And Flow Test".

Following these corrective actions the incident could not be Juplicated with the HPCI turbine shutdown or in operation. The HPCI system was declared operable at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> on December 9, 1987. after ST-6-055-230-1 was successfully completed.

-Actione Taken to Prevent Recurrence:

Plant records were examined to verify that proper procedures were satisfactorily cempleted for the last HPCI turbine lube oil and filter change. Results of this examination showed that the HPCI oil was changed in February, 1987. During this change "Preventive Maintenance Procedure for HPCI Oil Tar.k Clean, laspection and Drain and Refil'1", (PMQ-056-022) was performed.

P s procedure included verification of internal cleanliness and

  • umaltion of the correct filtered oil.

During the 1987 Refuel Outage "Preventive Maintenance Procedure for HPCI Oil Pilter Replacement", (PMQ-056-028) was performed.

This procedure included verification of internal cleanliness, installation of a filter element and, addition of the correct filtered oil.

On December 10, the auxiliary oil pump was run for 40 minutes and a turbine lube oil sample obtained from the sump. The sample was checked for particulates and found to be within acceptable limits.

A temporary increase in the runtime of the auxiliary oil pump in '

i conjunction with an increased surveillance of the overspeed trip .

mechanism has been initiated with an eventual return to the l monthly surveillance frequency. On December 16, 1987, the

auxiliary oil pump was run for 30 minutes for the first of the increased surveille ces. RT-1-055-330-1, "HPCI Turbine Overspeed l Trip Operability Check", was successfully completed at that time.

! During its performance the overspeed trip mechanism was manually

  • cycled 8-10 times with no abnormal movement observed.

Appropriate pt:cedures havs been revised to include monitoring stop valve position while the auxiliary oil pump is running to prevent any undetected recurrence of the event.

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BJ - High Pressure Coolant Injection System

SHV - Shutoff Valve TRB - Turbine ,

Previous Similar Events:

Limerick LER 87-015 reports an 'noperable HPCI stop valve due to ,

a different cause.

Tracking Code - (C99) External Cause, Other 4 .

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