NRC-91-0069, LER 90-012-01:on 901016,HPIC Steam Line Flow Transmitter Failed Due to Short Circuit Across Capacitor Plates.Circuit Boards Replaced & Failure Analysis Performed by Rosemount,Inc.W/910524 Ltr

LER 90-012-01:on 901016,HPIC Steam Line Flow Transmitter Failed Due to Short Circuit Across Capacitor Plates.Circuit Boards Replaced & Failure Analysis Performed by Rosemount,Inc.W/910524 Ltr

ML20024H225
Person / Time
Site:	Fermi
Issue date:	05/24/1991
From:	Orser W, Siemasz B DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-91-0069, CON-NRC-91-69 LER-90-012, LER-90-12, NUDOCS 9105300247
Download: ML20024H225 (5)

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EC ISOn '~." 10CrR30.73 Hay 24, 1991 NRC-91-0069 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Reference:

Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Licensee Event Report (LER) No. 90-012-01 Please find enclosed LER No. 90-012-01, dated May 24, 1991, for a reportable event that occurred on October 16, 1990. A copy of this LER is also being sent to the Regional Administrator, USNRC Region Ill.

If you have any questions, please contact Barbara Siemasz, Compliance Engineer, at (313) 586-1683 Sincerely, 7

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Enclosure:

NRC Forms 366, 366A cc: A. B. Davis J. R. Eckert R. W. DeFayette W. G. Rogers J. F. Stang Wayne County Emergency Management Division l

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y33 On October 16, 1990, at 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />, the High Pressure Coolant Injection System (HPCI) was found to have a failed channel for HPCI Steam Line Differential Pressure High, Division 1 (Lcgic A). The system was in st,andby at the time of discovery of the channel failure. In compliance with Technical Specification action statement requirements, the channel was declared inoperable. The HPCI System was subsequently declared inoperable and the appropriate Limiting Condition for Operation was entered.

Initial investigation revealed that one or both internal circuit boards on differential pressure transmitter, E41-N057A, had failed. <

The failed circuit. boards were sent to Rosemount Inc., for failure I analysis to aid in deternining the root cause of the channel failure.1 Besults of this analysis indicated a capacitor on the amplifier I circuit board failed due to a short circuit across the capacitor i pl a te.> . I The transmitter was repaired. Post maintenance surveillance testing demonstrated the effectiveness of the repair wcrk and the channel was declared operable. Subsequently, HPCI was declared operable.

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Initial Plant Conditions:

Operational Condition: 1 (Power Operation)

Reactor Power: 96.1%

Reactor Pressure: 999 psig Reactor Temperatures 535 F Description of Event:

At 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br /> on October 16, 1990, the High Pressure Coolant Injection System ((HPCI)(BJ)] was found to have a failed channel for HPCI Steam Line Differential High Pressure, Division I (Logic A). The failed channel was found during the performance of a channel check in accordance with surveillance 24.000.02, "Shiftly, Daily, Weekly and Situation Required Surveillances." 'the failed Division I channel was immediately declared inoperable and the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action statement for Technical Specification (TS) 3 3 2.b was entered. Tne 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action statement subsequently expired, and Action 23 or TS 3 3 2-1 was entered. This requires the isolation valves (ISV) for HPCI to be closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the system to be declared inoperable. Prior to reaching the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Technical Specification time limit, troubleshooting of the failed Division I channel was conducted by performing surveillance 44.020.203, "NSSSS-HPCI Steam Line Flow Division I, Calibration." At this time, all other Emergency Core i Cooling Systems (ECCS) and th 'cactor Core Isolation Coo.ing l

((RCIC)(BN)] system were verirled operable as required by TS l 3 5.1.c.1, Action c.1. Data gathered during the performance of l

44.020,203 showed that differential pressure transmitt(r (PT) ,

l E41-N057A, was malfunctionir,g and had caused the failed channel check. At 1957 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.446385e-4 months <br />, HPCI was declared inoperable and HPCI isolation valves, E41-F002 and E41-F042, were de-energized in the closed position in accordance with TS 3 3 2-1. Action 23 A Deviation 0:'ent l

Report (DER .3-0611) was written to investigate and evaluate the Division I channel failure.

At 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on October 17, 1990, after repair and successful testing of differential pressure transmitter E41-N057A, the HPCI system was declared operable.

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initial tuvestigation of the failed Division i channel revealed that l one or both circuit boards internal to differential pressure I transmitter E41-N057A had failed. The suspect circuit boards were I sent to the manufacturer, Rosemount Inc., for failure analysis to I aid in determining the root cause of the channel failure. The I results of this analysis indicate a capacitor on the amplifier l circuit board failed due to a short circuit. The likely cause of I the capacitor short circuit was metal migration bet. ween the I capacitor plates. Along with the failure analysis, Hosemount Inc. I reviewed data relating to similar transmitter failures and concluded I that this capacitor failure was random. 1 Analysis of. Event:

The Division I channel failure rendered inoperable the capability to detect a HPCI steam line break, therefore HPCI, as required by Technical Specifications, was isolated and declared inoperable. The ,

appropriate Technical Specification actions were met, following this event. While HPCI was inoperable, the Automatic Depressurization System (part of ECCS) would have been available to reduce reactor pressure to the point where Low Pressure Coolant Injection (BO) and Core Spray (BH) could have been used. RCIC was available to provide 1 l reactor water inventory control. If an event had occurred which I would have challenged HPCI, the other ECCS systems and RCIC would have fulfilled this safet.y function.

Based upon the availability of adequate ECCS and RCIC, this event did not impact the safe operation of the plant, or the health and safety of the public.

Corrective Actions:

Initial investigation of t.he failed Division I channel revealed that one or both circuit boards internal to different.ial pressure transmitter E41-N057A had failed. The suspect circuit boards were replaced. The effectiveness of the repair work was verified by post maintenance surveillance testing. Along with the failure analysis, I Rosemount Inc. reviewed data relating to similar transmitter I failures and concluded that this capacitor failure was randon. I hRC f me 365A 44t0

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Previous Similar Events:

This is the only reportable event due to a failed circuit twaard on a i differential pressure transmitter. 1 Failed Component Data:

E41-N057A, Rosemount Inc. Differential Pr essure Transnitter, Model No.

1153DB6Rc serial No. 413862.

hkC f oem M6A 164W

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