ML19327C267

LER 89-013-00:on 891019,reactor Tripped Due to lo-lo Level in Steam Generator 2C.Caused by Operator Incorrectly Transferring Steam Generator Level Control to Main Feedwater.Involved Personnel counseled.W/891114 Ltr

ML19327C267
Person / Time
Site:	Farley
Issue date:	11/14/1989
From:	Hairston W, Dennis Morey ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-013, LER-89-13, NUDOCS 8911220055
Download: ML19327C267 (4)

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, J Alabama Power Company -

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• 40 inverness Center Parkway

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,; Telephone 205 868-5581 >

i. W. G, Hairston,111 Senior Vice Prosident - ,

p Nuclear Operations AlabamaPower thesodhem electrcsyste:n November 14, 1989,

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10 CPR 50.73

. Docket No. 50-364' 2 V i U. S. Nuclear Regulatory Commission '

ATTN: Document Control Desk

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Washington, D.C. 20555 i L

-Dear Sire f

Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report No. LER 89-013-00 i

Joseph M. Farley Nuclear Plant, Unit 2, Licensee Event Report No. LER 89-013-00 is being submitted in accordance with 10CFR50.73. ,

If you have any questions, please advise.

Respectfully submitted, k.)b*

V. G. Hairston, III VGH,III/ JAR:md 8.49  ;

Enclosure i' cc: Mr. S. D. Ebneter j Mr. G. F. Maxwell ,

l 8911220055 891114 PDR ADOCK 05000364 s PDC J

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.J:seph M. Farley - Unit 2 o isio;oio; S i6;4 i jopl 0,3 l Personnel Error Causes Reactor Trip On Lo-Lo Steam Generator Level IVGNT Daft (El LtR NUMetR 461 REPORT DATE (7) OYMER f ACILITIES INVOLVID 40)

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NACE TELEPHONE NUM$tR ARI A CODE D. N. Morey, General Manager-Nuclear Plant 2i O5 i 499-i i i Si )S6 i COMPLETE ONE LINE FOR SACM ComePONENT F AILURE DESCRISED IN TMit REPORT 1131 CAUSS SYSTEM COMPONENT M AC. yo "* s CAust systtu COM*0NE NT * *"N AC' "fo **RN8 l I I I i 1 l l l 1 I I I i i l l I I I I I I I I I I I SUPPLEMENTAL REPORT ExeteTEo H4. MONTH DAv vtAR L ,

O vu in P . a.-P uurcreo svowssios oA rts Tl o.o l l l AesTR ACT <L-, r ua aa.o . . , wP r 1ew, e.,M wu, nP. ,,,.. u.,1 o e, At 1823 on 10-19-89, with the unit operating at approximately two percent power, the reactor tripped due to lo-lo level in the 20 steam generator. The Unit Operator improperly transferred from auxiliary feedvater (AFV) to main feedvater (MFW)~during a plant startup.

This event was caused by personnel error in that the Unit Operator incorrectly transferred steam generator level control from AFV to MFV.

A contributing cause was that the personnel involved failed to properly restore air to the 2C MFV bypass valve.

The personnel involved have been counseled concerning improper feedvater transfer and restoration of air to feedvater valves. A training change notice describing this event will be issued to all licensed personnel.

NRC Perm 3041649)

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' Plant and System Identification Westinghouse - Pressurized Vater Reactor Energy Industry Identification System codes are identified in the text as [XX].

Summary of Evenj ,

At'1823 on 10-19-89,- with the unit operating at approximately two percent power, the reactor [AB] tripped due to lo-lo-level in the 2C steam generator. The Unit ,

Operator. improperly transferred from auxiliary feedvater (AFV) [BA] to main feedvater (MFV) [SJ) during a plant startup.

[ Description of Event l

On 10-19-89, the unit was being started up following a reactor trip. At j approximately 1817, the unit was operating at approximately two percent power l and feedvater was being supplied by the AFV pumps. At this time, the Unit l

. Operator began transferring the source of feedvater to the steam generators from the AFV pumps' to a main steam generator feedvater pump. The procedure for this transfer involves verifying that the steam generator level increases by automatic action of the bypass valve prior to decreasing AFV flow.

The Unit Operator did not verify that steam generator level was increasing prior to decreasing the AFV flow. As the Unit Operator decreased the AFV flov to the 2C steam generator, he saw the position demand for the 20 MFV bypass valve l increasing and assumed that steam generator level vould start increasing.

However, the steam generator level continued to decrease. The Unit Operator "

then increased demand on the 2C steam generator bypass valve. Since level was still decreasing, the operators decreased reactor power and increased AFV flov 1 in an attempt to restore the steam generator level. However, these actions j failed to restore steam generator level prior to the 2C steam generator level ,

decreasing to the lo-lo level setpoint. A reactor trip occurred at 1823 on l 10-19-89. Subsequently, it was found that the 2C steam generator bypass valve ]

failed to open since air had been erroneously isolated to the valve. 1 Following the trip, the operators implemented FNP-2-EEP-0 (Reactor Trip or l.' Safety Injection) and FNP-2-ESP-0.1 (Reactor Trip Response), ensuring that the unit was safely in Mode 3. The unit was maintained in a stable condition. ]

Cause of Event This event was caused by cognitive personnel error in that the Unit Operator '

failed to properly transfer from auxiliary feedvater to main feedvater. A contributing cause was that the personnel involved failed to properly restore air to the 2C MPV bypass valve.

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Reportability Analysis and Safety Assessment t This event is reportable because of the actuation of the reactor protection system. After the trip, the following safety systems operated as designed: main feedvater was isolated as required, the auxiliary feedvater pumps (which were ,

ciready running) provided flow to the steam generators, source range nuclear instrumentation automatically energized, and pressurizer heaters and spray valves operated automatically as required to maintain system pressure. There was no effect on the health and safety of the public.

Corrective Action The personnel involved have been counseled concerning improper feedvater transfer and restoration of air to feedvater valves. A training change notice describing this event will be issued to all licensed personnel. ,

Additional Information The unit returned to power operation on 10-20-89 at 0659.

The following LER's reported reactor trips caused by operators failing to maintain proper steam generator water level: LER 87-009-00, LER 84-001-00 (both Unit 2).

No components failed during this event.

This event would not have been more severe if it had occurred under different operating conditions.

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. NRC Po,m 30SA (649)

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