ML20043J086

LER 90-017-00:on 900526,instrument Setpoint Drift Exceeds Tech Spec Limit for HPCI Turbine Trip on High Reactor Water Level.Cause Unknown.Transmitter Included in Program for Weekly Monitoring of Rosemount transmitters.W/900621 Ltr

ML20043J086
Person / Time
Site:	FitzPatrick
Issue date:	06/21/1990
From:	Fernandez W, Fish H POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JAFP-90-0481, JAFP-90-481, LER-90-017, LER-90-17, NUDOCS 9006270265
Download: ML20043J086 (4)

Text

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James A.FleePetelok e . 96uoteer Power Mont

, P.U. Box 41

,. Lycomin0. New York 13093

, 315 342 3640 Pbwer William Femander 11 Resident Manager June 21, 1990 JAFP-90-0481 i

United States Nuclerr Regulatory Commission Document Control Dei,k i Mail Station PI-137 )

Washington, D.C. 20555

SUBJECT:

DOCKET No. 50-333 I LICENSEE EVENT REPORT: 90-01'-00 l Level Instrument Setpoint Drift 1

Dear Sir:

This Licensee Event Report is submitted in accordance with 10 CFR 50.73(a)(2)(1). -

Questions concerning this report may be addressed to Mr. Hamilton Fish at (315) 349-6013.

Very trul yours, ILLIAM FERNANI EZ WF:HCFilar Enclosure cci USNRC, Region I USNRC Resident Inspector INPO Records Center American Nuclear Insurers n p #1" .

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The reactor was shutdown for refueling on 3/31/90. An Instrument Surveillance Procedure, " Reactor Level (ECCS) Transmitter Calibration I and Funccional Test (ATTS)", was performed on 5/26/90. The test found J that the high reactor water level trip point on a transmitter for the High Pressure Coolant Injection (HPCI) [BJ) turbine was 0.2 inches (0.3 percent of range) above the setpoint value required by Technical Specifications. The safety function prevents potential water carryover damage to turbines by shutdown of HPCI to prevent excessively high reactor water level. The transmitter was recalibrated and surveillance was temaorarily increased from once per cycle to once every six months I until three consecutive as-found readings are within specifications

) unless a consistent non-conservative trend in the direction of the l setpoint drift indicates a need for earlier replacement. The upward setpoint drift of 0.2 inches was not significant to safety since it would not have resulted in a measurable increase in moisture carryover should a high level situation have occurred. More than five feet remained between the trip setpoint and the steam lines.

Related LERs: 85-014, 85-015, and 86-008.

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Description The reactor was shutdown on March 31, 1990 for a refueling outage.

Instrument Surveillance Procedure, ISP-276A, " Reactor Level (ECCS)

Transmitter Calibration and Functional Test (ATTS)", was performed on

'May 26, 1990. At 11:00 A.M. during performance of the surveillance test the transmitter for the high reactor water level trip of the High Pressure Coolant Injection (HPCI) (BJ) turbine was found to be out of calibration. The as-found setpoint value could have resulted in an actual water level of 222.7 inches above Top of Active (TAF) at the time of tripping. This is 0.2 inches (0.3 percent of range) above the Technical S'accification value of less than or equal to 222.5 inches TAF found in Taale 3.2-2, " Instrumentation That Initiates or Controls the Core and Containment Cooling Systems", Item 3. The instrument was recalibrated.

The transmitter was previously calibrated on September 26, 1989 following initial installation as part of the Analog Transmitter Trip ,

System (ATTS) modification. '

Cause i This transmitter was manufactured after July 11, 1989 and is therefore considered less likely to experience the loss of fill oil which was characteristic of earlier transmitters from this vendor. No specific cause for this small setpoint drift was established.

Analysis i The as-found trip point of this instrument would have delayed the trip

, of the HPCI system until reactor water level rose to a value 0.2 inches above the trip point required by Technical Specifications.

Accordingly, it is reported as a condition prohibited by Technical  ;

I Specifications under the provisions of 10 CFR 50.73(a)(2)(1)(B). The safety function of this device is to. prevent potential carryover water j damage to turbines from high reactor water level. This is accomplished i by generating a turbine trip signal which results in closing of the steam supply isolation valve from the reactor to HPCI. The slight .

I increase in trip setpoint of 0.2 inches would have had no effect on the  ?

I ability of the transmitter to perform its safety function of preventing carryover. This slight increase is not significant when compared to the magnitude of the instantaneous water level variation due to boiling in the reactor vessel and the remaining distance of five and one-half feet between the high level trip setpoint and the elevation of the main steam line nozzles.

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0l0 tl3 or g1 3 Corrective Action The transmitter has been included in the program for weekly monitoring of Rosemount transmitters for loss of sensor fill oil. The frequenc of performance of the calibration surveillance has been temporarily y increased from once per operating cycle to once every six rnonths until three consecutive "as-found" calibration checks are within specified limits. The direction of the drift of the as-found setpoint will be monitored. Replacement of the transmitter will be evaluated if a defined non-conservative drift trend is identified.

Additional Information

1. Component Information Name/ Function: Reactor liigh Water Level Trip Transmitter for liigh Pressure Coolant Injection Turbine Plant Identification: 02-3LT-830 Vendor: Rosemount Model: 1153DB4RC Normal Trip Setpoint 221.2 Inches Above TAF Range: 164.5 to 224.5 Inches Above TAF NPRDS Vendor Code R369 NPRDS Component Code: IXMITR

2. Related LERs,85-014, 85-015, and 86-008

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