05000254/LER-1980-010-03, /03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted

/03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted

ML19323F238
Person / Time
Site:	Quad Cities
Issue date:	05/16/1980
From:	Kan S COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19323F231	List: 05000254/LER-1980-010, Forwards LER 80-010/03L-0 05000254/LER-1980-010-03, /03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted
References
LER-80-010-03L-03, LER-80-10-3L-3, NUDOCS 8005280685
Download: ML19323F238 (2)

LER-1980-010, /03L-0:on 800423,while Performing Loss of Electrohydraulic Control Fluid Pressure Scram Surveillance, Pressure Switch 1-5600-PS-3 Tripped Below Tech Spec Limit. Caused by Instrument Setpoint Drift.Switch Adjusted

Event date:
Report date:
2541980010R03 - NRC Website

text

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSloN (7 77)

LICENSEE EVENT REPORT Q

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8 60 61 OOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSECUENCES O'o 10121l While performing the Loss of Electrohydraulic Control Fluid Pressure Scram l

surveillance, procedure QlS-39, pressure switch 1-5600-PS-3 was found to trip at l

,o,3, 896 psig. This is 4 psig below the 900 psig setpoint requirement of TS Table 3.1-3 l

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Since redundant switches were demonstrated to be within allowable limits, an EHC low l

,o,,,9 fluid pressure condition would have been sensed at the proper setpoint and a reactor l

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3 31 40 43 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 1: 10 l l The cause of this occurrence was instrument setpoint drift. The 1-5600-PS-3 oressure l

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LER NUMBER:

LER/R0 80-10/03L-0 11.

LICENSEE NAME:

Commonwealth Edison Company Quad-Cities Nuclear Power Station lit.

FACILITY NAME:

Unit One IV.

DOCKET NUMBER:

050-254 V.

EVENT DESCRIPTION

On April 23, 1980 while performing surveillance test procedure QlS-39, Loss of Electrohydraulic Control Fluid Pressure Scram, pressure switch 1-5600-PS-3 was found to trip at 896 psig. This is 4 psig below the 900 psig setpoint requirement of Technical Specification Table 3. 1-3 The other three EHC pressure switches were found to be within the Technical Specification limit. The switch was immediately recalibrated and functionally tested satisfactorily.

VI.

PROBABLE CONSEQUENCES OF THE OCCURRENCE:

The four pressure switches are arranged in a one-out-of-two-twice logic to initiate a reactor protection system function upon loss of EHC pressure.

Since redundant switches were demonstrated to be within allowable limits an EHC low fluid pressure condition would have been sensed at the proper setpoint and a reactor scram would have been initiated.

Safe operation of the reactor was not affected at any time.

Vll. CAUSE:

The cause of this occurrence was instrument setpoint drift. The pressure switch is model C-9612-2, manufactured by Barksdale Co.

Vill. CORRECTIVE ACTION:

The immediate corrective action was to recalibrate the pressure switch setpoint. A functional test was then successfully performed to demon-strate the operability of the pressure switch.