ML20024D914

Updated LER 83-035/03X-1:on 830228,during 4 H RCS Unidentified Leakage Test,Pump B of Drywell Sump a Continued to Operate for 4 H W/O Change in Sump Level.Caused by Clogged Pump Impeller.Pump cleaned.W/830726 Ltr

ML20024D914
Person / Time
Site:	Susquehanna
Issue date:	07/26/1983
From:	Keiser H, Piemontese A PENNSYLVANIA POWER & LIGHT CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-83-035-03X, LER-83-35-3X, PLA-1763, NUDOCS 8308080418
Download: ML20024D914 (3)

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s Update Report - Previous Report Date 03/30/83

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y e 69 el 80 49 F4 70 TE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o2 l During performance of a four hour reactor coolant system unidentified leakage testl, 1011 l l the "B" pump of the "A" drywell sump continued to operate for four hours with no l l o l4 l l change in sump level (25%). Leakage calculations were run prior to and af ter the l l 0 l 5 l l four hour period in question and leakage rates were .38 and .4 nom (5 nom limit) . l l o j e l l There were no consecuential effects to public health and safety. l l0l7ll l .

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et 45 44 I zlO Iz 1919191 47 CAUSE DESCRIPT ON AND CORRECTIVE ACTIONS h l 1 l 0 l l The "B" pump was shut down and the "A" pump was us_ed for leakage calculations. l l 1 l 1 l l Investination revealed the "B" pump impeller was clogged with foreign material. l l i l 2 l l The pump and entire cump were cleaned. A preventive maintenance activity has l l1l3ll been added to the plant maint. system to insoect the drvwell sumpe durina outages l l 114 l l of suf ficient duration. l

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NAME OF PREPARER A.P. Piemontese PHONF- 717-542-2181

ATTACHMENT LER # 83-035/03X-l' Pennsylvania Power & Light Company -

Susquehanna Steam Electric Station Docket Number: 50-387 The reactor coolant system unidentified leakage is calculated from the drywell floor drain sumps. There are two pumps in each sump. Each sump has one level transmitter that feeds one level recorder. The calculations are made from the last time the calculation was performed until the present.

For each calculation, the total percent that the sumps were pumped down is determined and then multiplied by a constant which converts this total percent to gallons. The total gallons are then divided by the total minutes from the last time the calculation was performed and this result in the average in-leakage.

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Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101 = 215 / 770 5151 July 26, 1983 Dr. Thomas E. Murley Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 83-035/03X-1 ER 100450 FILE 841-23 PLA-1763

Dear Dr. Murley:

Attached is Licensee Event Report No. 83-035/03X-1. This event was determined to be reportable per Technical Specification 6.9.1.9.b, in that a reactor coolant system leakage surveillance could not be performed as required.

This provides an update go the previously submitted report, No. 83-035/03L-0.

, L/_.4441 H.W. Keiser Superintendent of Plant-Susquehanna APP /pj g attachment cc: G.G. Rhoads Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655 i

Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 h

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