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Noveiii CnurV O Ev>n as,m,,,an...i r a ison.m. December 14, 1990

ND3MNO:3076

Beaver Valley Power Station, Unit No. 2Docket No. 50-412, License No. NPF-73

LER 90-021-00

United States Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555

Gentlemen:

In accordance with Appendix A, Beaver Valley TechnicalSpecifications, the following Licensee Event Report issubmitted:

LER 90-021-00, 10 CFR 50.73.a.2.iv, "ESF Actuation -

Feedwater Isolation During Main Steam Isolation Valve StrokeTesting".

Very truly yours,

gf. 02%eask.:As.O

T. P. NoonanGeneral ManagerNuclear Operations

JGT/sl

Attachment

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Dacomb2r 14, 1990 l' '

, ND3MNot3076Pr,ge two

cc Mr. T. T. Martin, Regional AdministratorUnited States Nuclear Regulatory CommissionRegion 1

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475 Allendale Road l

King of Prussia, PA 19406

c. A. Rotock, Ohio Edison76 S. Main StreetAkron, OH 44308

Mr. A. DeAgazio, BVPS Licensing Project Manager l

United States Nuclear Regulatory CommissionWashington, DC 20555

J. Beall, Nuclear Regulatory Commission,BVPS Senior Resident Inspector

Larry BeckCleveland Electric6200 Oak Tree Blvd.Independence, Ohio 44101

INPO Records Center'

Suite 15001100 circle 75 ParkwayAtlanta, GA 30339

G. E. Muckle,Factory Mutual Engineering680 Anderson Drive #BLD10Pittsburgh, PA 15220-2773

Mr. J. N. Steinmetz, Operating Plant Projects ManagerMid Atlantic AreaWestinghouse Electric CorporationEnergy Systems Service DivisionBox 355Pittsburgh, PA 15230

Mr. Richard JanatiDepartment of. Environmental Resources

-P. O. Box 2063i

16th Floor, Fulton BuildingHarrisburg, PA 17120

| Director, Safety Evaluation & ControlL Virginia Electric & Power Co.

P.O. Box 26666One James River PlazaRichmond, VA 23261-

_

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* ' Dscambar 14, 1990,

14D3MNO: 3076Page three

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W. 11articyManagement Analysis Company

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112671 liigh Bluff Drive I

San Diego, CA 92130-2025

J. M. RiddleNUS Operating Service CorporationPark West IICliff Mine RoadPittsburgh, PA 15275

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On 11/13/90 at 0001 hours, with the Unit in Hot Shutdown(Operating Mode 4) a plant heatup to less than 3SOF was inprogress. Operatkons personnel were preparing to performpartial stroking of the main steam isolation valves (MSIV) as a-prerequisite to entry to Hot Standby (Operating Mode 3). Theinitial conditions for the surveillance testing required theMSIVs to be fully open. The '! A" MSIV, 2 MSS *AOV101A, was to bestroked first, however the valve was shut. As the operatoropened the valve, to a depressurized steam header, the increasedsteam flow required to pressurize the steam header resulted in a" swell" of the steam generator level in the "A" steamgenerator. The level increased from 34% to greater than 75%causing a Feedwater Isolation Signal (FWI), at 0442 hours. .TheFWI signal caused the closure of feedwater containment isolationvalves. The cause for this event was due to operator error.The main steam header was not pressurized prior to opening ofthe MSIV as. required by procedure. The FWI sinnal was reset andthe foodwater containment isolation valves were reopened at 0448hours. There were no safety implications as a result of thisevent. The feedwater containment isolation valves closed asdesigned upon receipt of the FWI signal. All other componentsactuated by the FWI si-gnal were not in service.

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DESCRIPTION OF EVENT

On 11/13/90 at 0001 hours, with the Unit in Hot Shutdown(Operating Mode 4), a plant heatup to less than 350F was inprogress. The reactor coolant system (RCS) temperature was 305Fand RCS pressure was 400 psig. The pressure in the steamgenerators was 40 psig. Operations personnel were preparing toperform partial stroking of the main steam isolation valves(MSIV), as a prercquisite to entry into Hot Standby (OperatingMode 3). The initial conditions for the surveillance testingrequired the MS1Vs to be fully open. The "A" MSIV,2 MSS *AOV101A, was to be stroked first, however the valvo wasshut. A normal operating procedure is available to guide theoperator in the steps required to pressurize the steam header(opening the bypass valve around the MSIV to reduce the pressuredifferential and increano steam header pressure prior to openingthe MSIV), however this procedure was not consulted. As theoperator opened the MSIV, to a depressurized steam header, theincreased steam flow required to pressurize the steam headerresulted in a " swell" of the steam generator loval in the "A"steam generator. The level increased from 34% to greator than75% causing a Feedwater Isolation Signal (FWI), at 0442 hours.The FWI signal caused the closure of feedwater containmentisolation valves. All other components actuated by the FWIisolation signal (main foodwater regulating valves, bypassfeedwater regulating valves,instartup foodwater pump and mainfoodwater pumps) were not service and therefore did notactuate. The Muclear Regulatory Commission was notified of thisEngineered Safety Features actuation at 0620 hours.

CAUSE OF THE EVENT

The cause for t'his event was operator error. The operator,while attempting to establish the initial conditions for thetest (MSIV fully open), failed to equalizo pressure across thevalve prior to opening the MSIV using the normal operatingprocedure. This resu)+-d in increased steam flow whichpres,surized the steam headu resulting in a " swell" of the steamgenerator level in the "A" steam generator. Specific proceduralguidance, for pressurizing the steam header if the MSIVs werenot open, was not in the surveillance test.

CORRECTIVE ACTIONS

| The following corrective actions have been or will be taken as aresult of this event:

1. The FWI signal was reset and the feedwater containmentisolation valves were reopened at 0448 hours. |

|

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2. The surveillance tests for partial stroking of theMSIVs will be revised to include guidance for openingthe MSIVs to a depressurized steam header.

3. The involved operator was counseled rogarding theactions performed during this event.

4. This event will be covered at a future Retrainingsession with all Unit 1 and 2 Operations personnelemphasizing the requirements for use of procedures.

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5. An engineering evaluation has been performed to addressthe potential for piping damage subsequent to thisevent. No concerns were identified.

REPORTABILITY

This event was reported to the Nuclear Regulatory Commission at0620 hours in accordance with 10CFR50.72.b.2.11. This writtenreport- is being issued in accordance with 10CFR50.73.a.2.iv, anan event involving an Engineered Safety Features (ESP) systemactuation.

PREVIOUS OCCURRENCES

The following similar feedwater isolation events have beenpreviously reported for Unit 2. A review of these events showed-that none of these events were caused by a failure to useprocedures.

.

LER 88-011-00 " Automatic Feedwater Isolation"LER 89-015-00 "Foodwater Isolation During Testing Of

Auxiliary Feedwater Pump"

LER 89-020-00 HInadvertent Start Of Motor Driven AuxiliaryFeedwater Pumps"

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