ML20024A420

LER 83-019/03L-0:on 830422,valve 743,nonautomatic Containment Isolation Valves in RHR Pump Miniflow Line Would Not Operate.Cause Not Stated.Reach Rods Disconnected & Valve Stem & Universal Joints Cleaned & lubricated.W/830522 Ltr

ML20024A420
Person / Time
Site:	Indian Point
Issue date:	05/22/1983
From:	Hinrichs G, Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-83-019-03L, LER-83-19-3L, NUDOCS 8306170271
Download: ML20024A420 (3)

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LICENSEE EVENT REPORT CONTROL BLOCK: l l l I I l (PLEASE PRINT CR TYPE ALL REQUIRED INFORMATION) a lil8 l9 Nl Yl Il Pl Sl 2l@l LICENSEE CODE 14 010 l -l 0 l 0uCENSE 15 l 0 NUMBER l 0 l 0 l- l0 l 025l@l4 26 l1LICENSE l1 l1TYPE l1JOl@l57 CATl 58 l@

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8 60 6J EVENT DATE 74 75 REPORT OATE 60 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h T(Tl l During reduced power operation, Valve No. 743, one of two non-automatic contnirmne I g , isolation valves in ser:Les in the Mm pump miniflow line muld not operate. Since I o ,,, ; repairs could rot be ademnlished within the time period allowed by Tech. Spec. I jo ,3, ; 3.6.A.5.a a plant shutdown was initiated. The shutdown was ternunated when the valve I o,oi l was successfully repaired. he health and safety of the public were unaffected. I g , , y , Previous Event: LER 83-18. l

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43 44 47 l CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i i 10 l lThe reach rods were disconnected, the valve < +cm nna nriinne-en1 jni n+ c- ..

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John D. O'Toole

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May 22, 1983 Re: Indian! Point Unit No. 2 Docket No. 50-247 i LER-83-019/03L-0 Mr.' James M. Allan, Acting Regional Administrator-Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406

Dear Mr. Allan:

The attached Licensee Event Report LER-83-019/03L-0 is hereby submitted in accordance! with the requirements of Technical Specification 6.9.1.7.

This event is of the type described in Technical Specification '

6.9.1.7 2.b.

Three copies of this letter and attachment are encloied as required.

Very ruly yours, ,

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V V $4v .

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cca Mr. Richard DeYoung, Director (30 copies)

Office of Inspection and Enforcement c/o Distribution Services Branch, DDC, ADM U. S. Nuclear Regulatory Commission ,

Washington, D. C. 20555 Mr. William G. Mcdonald, D.irector (3 copies)

Office of Management Information and Program Control ~

c/o Distribution Services Branch, DDC, ADM U. S. . Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Thomas Foley, Senior Resident Inspector U. S.! Nuclear, Regulatory Commission P. O. Box 38 Buchanan, New York 10511 n

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ATTACHMENT Docket No. 50-247 Consolidated Edison Co. of New York, Inc.

LER 83-019/03L-0 Indian Point Station Unit 2 On Friday, April 22,il983 at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br />, a leak was observed in the Isolation Valve Seal Water System (IVSWS) at the socket weld connection between valve Nos. 1870 and 743 in the RHR pump miniflow line. (See LER 83-017) . As part of the investigation of the IVSWS leak, it was determined that Valve No. 743 could not be stroked.

A plant shutdown was initiated in accordance with Technical Specification 3.6.A.5.a. when the repair tro valve No. 743 could not be completed within the allowed time period.

The reach rods were disconnected, the valve stem and universal joints were cleaned and lubricated, the valve handle was tightened and the limit switch was checked. The valve was satisfactorily tested and returned to service at which time the shutdown was terminated.

Valve No. 743 is a 3" globe valve Fig 3-12GS-316 manufactured by Conval with a Limitorque SMB-00 actuator.

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