ML20113B399

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Final Potential Significant Deficiency Rept SD-74 Re Design & Const of Auxiliary Feed Pump Lube Oil Pressure Switches Mfg by Bingham-Willamette.Initially Reported on 850201. Switches Replaced W/Qualified Class 1E Switches
ML20113B399
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/08/1985
From: Counsil W, Sears C
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
F0681A, F681A, SD-74, NUDOCS 8504110171
Download: ML20113B399 (2)


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March 8,1985 Docket No. 50-423 F0681A

' Dr. Thomas E. Murley -

TRegional Administrator Region i U.S. Nuclear Regulatory Commission 631 Park Avenue

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King of Prussia, PA 19406

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Dear Dr. Murley:

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Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies

. In Design and Construction:

Auxiliary Fee ~d Pump Lube Oil Pressure Switches (SD-74)

In a February 1,1985 telephone conversation between your Mr. T. Rebelowski and our Mr. P. J. Quinlan, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the construction of Millstone Unit No. 3.

The potential significant deficiency involves auxiliary feedwater pump lube oil pressure switches.

An engineering evaluation determined that the pressure switches were not seismically qualified or mounted as required.

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. Each auxiliary feedwater pumgi includes a ' lube oil system pressure switch

,. provided by the pump manufacturer, Bingham-Williamette.

The function of these switches is to provide a start /stop signal to the main pump based on tube oil system pressure. Failure of the pressure switch will prevent the auxiliary feedwater pump fror.i starting or will cause a trip if the pump is already running.

Hence, this is a significant deficiency for Millstone Unit No. 3.

All safety-related pumps manufactured by Bingham-Williamette, as well as other vendors, were reviewed for a similar problem and it was determined that this problem is limited only to the auxiliary feedwater pumps. Corrective actions have been initiated and will involve replacement of these switches with new seismically qualified class IE pressure switches.

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' We consider this to be our final report for 5D-74. As discussed with the NRC Senior Resident Inspection, Mr. T. Rebelowski, this report is being provided on March 8 rather than March 1,1985.

We trust that the above information satisfactorily responds to your concerns.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY W. b. bwr W. G. Counsil Senior Vice President By: C. F. Sears Vice President cc:

Mr. 3. M. Taylor, Director Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Q

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