ML20024C114

LER 83-087/03L-0:on 830527,A Containment H2/02 Analyzers Found to Have Erratic Readings.Caused by Pressure Control Valve & Sample Pump Degradation to Point Where Proper Flow Not Maintained.Failed Components replaced.W/830624 Ltr

ML20024C114
Person / Time
Site:	Susquehanna
Issue date:	06/24/1983
From:	Keiser H, Todd J PENNSYLVANIA POWER & LIGHT CO.
To:	Allan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-83-087-03L, LER-83-87-3L, PLA-1729, NUDOCS 8307120273
Download: ML20024C114 (3)

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l o 12 l lWhile at 40% power, the ' A' Containment H /0 Analyzers were found to have erratic l 1013 l lreadinns. The analyzers were declared inoperable in accordance with Technical Speed 10 I4 l lification 3.3.7.5. Accident Monitorine Instrumentation. There were no adverse con- l l o l5 l l sequences in that the 'B' Analyzers were available and operatinn properly. This l l0lell event is similar to LER 83-053/03L-0. l l0l7ll l 1o1811 l

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l 110 l lUpon insnection of the ' A' analyzer components. the pressure control valve and l 1 l 1 l lsnmple pump were found to be degraded to a noint where proper flow could not be l

[ 1 l 2 l l maintained. The failed components were replaced and the system calibrated and de- l l 1 l 3 l lclared operable. An engineering review has been tasked with determining the long l l 1 l 4 l l term resolution. I STAT S *b POW E R .T HE R ST ATU S ISCOVERY DISCOVERY DESCR4PTION I1lSl W @ l 01 4l Ol@l NA l [_A_j@l Operator Observation l

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8307120273 830624 ig g u E o""'n'.C R i,Tio,. @ PDR ADOCK 05000387 NRC USE ONLY l2101lNlgl S PDR l lllll!lllllll J,M NAME OF PREPARER J.J. Todd PHONE:(717)S42-2181 X3240

....n ATTACHMENT LER # 83-087/03L-0 Pennsylvania Power & Light Company Susquehanna Steam Electric Station Docket Number: 50-387 While at 40% power, the "A"~ Cont':ainment H,/0 2 analyzers were found to have erratic readings. The analyzers were declared inoperable in accordance with Technical ~ Specification 3.3.7.5, Accident Monitoring Instrumentation.

There were no adverse consequences in that the "B" analyzers were operable and operated properly.. This event is similar to LER 83-053/03L-0, which was written about the "B" containment H /0 analyzers.

2 2 Thesuspectcomponents,thepressurecontrolhalveandsamplepump,were inspected and found to be degraded to a point where proper flow could not be maintained. The valve and pump were replaced and the "A" Containment H2/02 analyzers were returned to service and declared operable.

It is believed that previous operation of the H 2/0, analyzers in a non-inerted containment during the Power Ascension testing progran caused accelerated ~ degradation of the system components. With the higher than normal concentration of oxygen in the containment, abnormal- amounts of moisture were pre'sent in the system. This coupled with the amount of outage activities in the containment (grinding , welding, . insulation work, etc.) allowed quantities of particulate to accumulate in various components and restricted flow.

The sample pump will be sent to Comsip-Delphi for failure analysis. The Nuclear Plant Engineering group has been contacted and asked to investigate and eval-uate the life expectancy of the H /02 analyzers 2

sample pumps and other system components. The question of equipment design versus equipment application is also a part of the engineering review.

The method of operation has been changed to keep one channel of analyzers -

in the standby mode while the other channel is kept in continuous analyze.

The information from. the engineering review being made will be applied to both channels of the H2 /02 analyzers. This LER will be updated when the engineering review is completed.

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@ Pennsylvanic Pow::r & Light Company Two North Ninth Street

• Allentown, PA 18101

• 215 1 770-5151 i

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June 24, 1983 )

i Mr. J.M. Allan Acting Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION LICENSEE EVENT REPORT 83-087/03L-0 ER 100450 FILE 841-23 PLA-1729

Dear Mr. Allan:

Attached please find a copy of Licensee Event Report No. 83-087/03L-0.

This event was determined to be reportable per Technical Specification 6.9.1.9.b, in that the ' A' channel of Containment Hydrogen /0xygen analyzers was found to have erratic readings and declared inoperable. This event ,

is similar to LER 83-053/03L-0 and an engineering review is in progress to determine proper system design versus application. An update to this LER "ill be forthcoming.

/!

H.W. Keiser Superintendent of Plant-Susquehanna JTT/pjg attachment cc: G.G. Rhoads Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

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