05000352/LER-1988-001, :on 880106,discovered That RCIC Sys pipe-routing Area Temp Reading Deviating from Previous Shift Readings.Caused by Incorrect Reconnection of Thermocouple & Personnel Error.Technicians Counseled on Error

:on 880106,discovered That RCIC Sys pipe-routing Area Temp Reading Deviating from Previous Shift Readings.Caused by Incorrect Reconnection of Thermocouple & Personnel Error.Technicians Counseled on Error

ML20196D365
Person / Time
Site:	Limerick
Issue date:	02/08/1988
From:	Logue R, Mengers C PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-001, LER-88-1, NUDOCS 8802170088
Download: ML20196D365 (6)

LER-1988-001, on 880106,discovered That RCIC Sys pipe-routing Area Temp Reading Deviating from Previous Shift Readings.Caused by Incorrect Reconnection of Thermocouple & Personnel Error.Technicians Counseled on Error

Event date:
Report date:
3521988001R00 - NRC Website

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Abstract:

88-001 On January 6, 1988, the requirement of Technical Specification 3.3.2.b was not met.

During a review of surveillance test ST 107-590-1 "Daily Surveillance Log" it was noticed that a Reactor Core Isolation Cooling (RCIC) system pipe-routing area temperature reading was deviating from previous shift readings.

Subsequent investigation revealed that during the performance of an ST the thermocouple leads were inadvertently reversed.

This condition went undetected during.the performance of the Independent Verification of Restoration portion of the ST.

Additionally, operations personnel recognized the abnormally low temperature indication but attributed the reading to extreme cold weather.

There were no adverse consequences and no release of radioactive material as a result of this event.

Had a steam leak occurred in the RCIC pipe-routing area with the subject thermocouple leads reversed the isolation logic would still serve its design function due to the presence of an alternate trip system containing a redundant thermocouple.

The thermocouple leads were properly relanded at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on January 6, 1988 and indication was verified to reflect current plant conditions.

The technicians involved were counseled as to their error and discussion of this event will be included in annual technician training.

Shift Operations personnel have received a memo detailing this LER and the requirement to notify Shift Supervision of inconsistent channel readings.

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Operating Mode:

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Reactor Power:

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1 Description of the Event:

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On January 6, 1988, it was discovered that an incorrectly connected thermocouple resulted in a condition which did not meet the requirements of Technical Specification 3.3.2.b which states, "With the number of OPERABLE channels less than required by the minimum OPERABLE channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition with.in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />."

During a review of surveillance test ST-6-107-590-l "Daily Surveillance Log" it was noticed that a Reactor Core Isolation Cooling (RCIC) system pipe-routing area temperature reading was deviating from previous shift readingn.

Specifically, the day shift (X) reading on January 5, 1988 was 84 degrees F while the afternoon (Y) shift and the night (Z) shift readings where both 54 degrees F.

The January 6, 1988 X-shift Instrument and Controls group was l

notified of the problem and requested to investigate the cause.

l While troubleshooting, it was discovered that the leads to a RCIC pipe-routing area high temperature thermocouple (TIS-049-lN603J) had been reversed.

This incorrect wiring hookup had resulted in the inconsistent temperature readings and rendered thermocouple TIS-049-lN603J inoperable.

Consequences of the Event:

There were no adverse consequences as a result of this event.

There was no release of radioactive material as a result of this event.

Had a steam leak occurred in the RCIC pipe-routing area with the thermocouple disabled due to reversed leads, the RCIC steam supply isolation valve would have closed and performed its design function due to redundancy of the temperature detection in this area.

The isolation actuation instrumentation for this system consists of two trip systems.

Thermocouple TIS-049-lN603L

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I is located six feet from thermocouple TIS-049-lN603J and is on the alternate trip system.

The RCIC isolation logic is a one out of one logic, therefore the RCIC steam supply isolation valve would close on a high temperature signal from the redundant thermocouple TIS-049-lN603L.

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Cause of the Event

The immediate cause of t'nis event was the incorrect reconnection l

of the thermocouple, which had apparently occurred when contractor employed Instrument and Control technicians performed surveillance test ST-2-049-613-1, "Nuclear Steam Supply Shutoff System - RCIC Equipment Room Temperature Division I Functional Test."

This ST was completed at approximately 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> on January 5, 1988.

During the performance of this surveillance test it is believed that the thermocouple leads were j

inadvertently reversed on reconnection.

This was not discovered I

during the Independent Verification of Restoration (IVOR) portion i

of the surveillance test.

The IVOR consists of a sign-off space verifying that the field wires have been properly reconnected following the performance of the surveillance test.

Although the IVOR provides wire tag numbers and the terminal numbers to which they are to be attached, the contractor employed Instrument and Control technician performing the IVOR failed to recognize the incorrect reconnection of the field wires.

Operations personnel performing channel checks for this instrument during performance of ST-6-107-590-1 "Daily Surveillance Log" during Y and Z shifts on January 5, 1988 recognized the abnormally low temperature indication but attributed the reading to extreme cold weather.

Corrective Actions

Operations personnel suspected the deviation in the temperature reading might be a problem during the review of ST-6-107-590-1, "Daily Surveillance Log" at the beginning of X-Shift on January 6,

1988.

Instrument and Control personnel were notified of the problem on X-shift, January 6, 1988.

Following an investigation to determine the cause of the problem the thermocouple leads were properly connected at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on January 6, 1988 and indication was verified to reflect current plant conditions.

The incorrect wiring condition existed for approximately 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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Action Taken to Prevent Recurrence:

The event was discussed at the "All Hands" meeting of the I&C technicians on January 15, 1988.

The personnel were reminded of the importance of accurate performance of the independent verification program and the attention to detail requirements involved in the surveillance test program.

The technicians involved were counselvd as to their error and the importance of properly verifying the reconnection of leads when removed for testing.

A memo has been sent from the Assistant Superintendent Operation to Shift Personnel detailing this LER.

When performing channel checks, inconsistent channel readings shall be highlighted aad Shift Supervision notified.

The ST and Independent Verification of Restoration (IVOR) programs are part of the technician continuing training program.

The technician yearly procedurs refresher class will specifically address this event.

All technicians are scheduled for the class in the first quarter of 1988.

The following Human Factors Enhancements will be added to the specific type of surveillance test involved by June 1, 1988 as follows:

1)

The IVOR section of the ST will be formatted in such a way that the sequence of verification is consistent with the physical terminal locations in the panel.

2)

Wire colors will be mentioned throughout the body and the IVOR section of the ST.

This will provide an additional means of identifying the field wires thrcughout the test.

The process of lifting leads during surveillance testing is being evaluated by the Nuclear Engineering Department.

Modification No. 790 is evaluating the possibility of installing switches to obviate the need to lift leads on this test during routine surveillance testing.

EIIS Codes BN - Reactor Core Isolation Cooling System TW - Thermocouple

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Previous Similar Occurrences:

LGS LER 85-019 reports t'eversed thermocouple wires for the High Pressure Coolant Injection System turbine steam supply outboard l.

isolation valve.

Tracking Codes: A, Parsonnel Error S

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February 8, 1988 L-r Docket No. 50-352 r

Document Control Desk

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U.S. Duclear Regulatory Commission Washington, DC 20555 y

SUBJECT:

Licensee Event Report Limerick Generating Station - Unit 1 This LER reportssthe failure to meet Technical Specificalion

, requiteihents of the Re. Actor Core < Isolation Cooling System due to

. person 11el error.

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< Reference:

Docket No..50-352 Report Number:

88-001 Revision Number:

00 Event Date:

Januaryp5, 1988 Discovery Date:

January' % 1988 Report Date:

February'8, 1988 q'

Facility:

Limerick Generating Station i

P.O. Box A, Sanatoga, PA, 19464 This 1ER is being submitted pyrsuant to the requirements of 10 CFR 50173(a)(2)(1)(B).* We regret the delayed edbmittal of thJs LER and any inconvenience that it may have caused.

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I WWW j a, R. H. Logue Assistant to the Manager Nuclear Support Division

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W. T. Russell, Administrator, Regfon,I, USNRC

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