ML20090E224

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Advises That on 920120,Train 2A of Emergency Diesel Generator Removed from Svc After Temp Detector Actuated on Connecting Bearing 8.Caused by Poor Solder Connection Made During Mfg.New Temp Detector Installed
ML20090E224
Person / Time
Site: Braidwood 
Issue date: 03/04/1992
From: Simpkin T
COMMONWEALTH EDISON CO.
To: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 9203090314
Download: ML20090E224 (2)


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Ccmmonwcalth Ediscn 1,) 1400 opus Place v'

Downers Grove, Illinois 60515 March 4,1992 Mr. A. Bert Davis Regional Administrator U.S. Nuclear Regulatory Commission Region lli 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Braidwood Station Unit 2 O!eee! Generator 20G01KA Failure NF10_ Docket No _50-457

Reference:

(a) NUREG-1276, Technical Specification (b) November 21,1991, T.W. Simpkin letter to A.B. Davis

Dear Mr. Davis:

Section 4.8.1.1.3 of reference (a) requires that all diesel generator failures, valid or non valid, be reported to the NRC pursuant to Specification 6.9.2. The enclosure provides the report that addresses one valid and one invalid failure 2DG01KA diesel generator. The criteria used to determine valid tests and failures is taken from section C.2.e of Reguiatory Guide 1.108.

Reference (b) is the most recent report addressing diesel generator failures, submitted per Section 4.8.1.1.3.

Please direct any questions concerning this submittal to this office.

Very truly yours, Wh f

T.W. Simpkin Nuclear Licensing Administrator cc:

R. Pulsifer - NRR B. Clayton - Rill Resident inspector - Braldwood NRC Document Control Desk f'90022 i

67M 9203090314 920304 PDR ADOCK 05o00457 5

PDR

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On Monday, January 20,1992, at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, the Braidwood Unit 2, A Train (2A) Diesel Generator (DG) was removed from service for planned routine maintenance. This event caused entry into Technical Specification 3.8.1.1 Action (a). Following completion of the planned maintenance activities, a post maintenance verification run of the 2A DG was performed. The 2A DG was loaded to full capacity,(5500 IGV), unloaded, and taken offline in accordance with Station Operating Procedures with no problems noted. The 2A DG was started on Tuesday, January 21,1992, for an operability surveillance at 2053 hours0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.811665e-4 months <br />. After being loaded to approximately 1425 KW, the 2A DG tripped on

" Main & Conn Rod, Generator Outboard Brg. Temp. High" at 2118 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.05899e-4 months <br />.

Trouble-shooting determined that the temperature detector actuated on the #8 connecting rod bearing. (Lube oil and jacket water temperatures were normal at the time of the trip.) Opening the crankcaso verified that one of the two eutectic high temperature detectors had actuated on the # 8 connecting rod hnaring. A Cooper-Bessemer Field Representative was called to the site.

The actuated temperature detector was removed. Upon inspection of the temperature detector by site personnel, the Cooper-Bessemer Field Representative, and a representative from Commonwealth Edison's System Materials Analysis Department (SMAD), it was determined that a poor solder connection (the eutectic material) had been made dtuing the manufacturing of the temperature detector. The defe::tive detector actuated prematurely due to normal engine operation. As a precaution, the connecting rod bearing cap was removed and the bearing was inspected. No signs of abnormal wear or excessive heating were noted. The Cooper-Bessemer Field Representative judged the bearing as having only signs of normal wear. The 2A DG trip was determined to be spurious due to the failure of the #8 connecting rod bearing high temperature detector. This trip would not have occurred if the 2A DG had been operating in the Emergency Mode.

A new temperature detector was installed. Also, a new bearing was installed in the #8 connecting rod to ensure that a proper wear pattern is achieved. The prescribed Cooper Bessemer procedure for " break-in" was performed. Following the " break-in" run, the normal operability surveillance was successfully performed. The 2A DG was returned to an operable status at 1658 I

hours on January 23,1992.

This failure was determined to be invalid per Regulatory Guide 1.108, Section C.2.e. This is the first failure of this type. As of January 30,1992, the 2A DG has had one valid failure in its last 20 valid demands. The 2A DG has had 3 valid failures and the Braidwood Unit 2B DG has had no valid failures in I

the last 100 U-2 DG valid DG demands.

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