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Callaway Plant Unit 1 o[s[o|o|og |g|3 i joFlo hIITLE tel

Reactor Trip and Engineered Safety Features ActuationsEVINT DATE (S) LOR NutISER (g) REPORT DATE (M OTHER FACILITIES INVOLVED ISI

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LaCENSEE CONTACT POR TMit LER liti

NiME TELEPHONE NUMSER

ARE A CODEMichael E. Taylor - Superintendent, Operations

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SUOMISSION

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On 11/14/84 a Reactor Trip, Feedwater Isolation, Auxiliary FeedwaterActuation, and Steam Generator Blowdown Isolation occurred as a resultof a high steam generator (S/G) level. The high S/G 1evel was receivedduring S/G level oscillations initiated while attempting to runback themain turbine. The operators attempted the turbine runback in responseto a decrease in condenser vacuum caused by the tripping of acirculating water pump.

The operators recovered from the Reactor Trip via plant procedures andstabilized plant conditions. The circulating water pump had tripped onlow lubrication water pressure. To prevent recurrence of this incident,the low lube water flow and pressure trips were changed to alarmfunctions.

,There was no damage to plant equipment or release of radioactivity as a

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result of this incident. At no time was the public health or safetythreatened.

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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION ' an aovso one =o maceo.exe. ass. see ,

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At 1451 CST on 11/14/84, a Reactor Trip, Feedwater Isolation (FWIS),Auxiliary Feedwater Actuation (AFAS), and Steam Generator Blowdown Isolation(SGBIS) occurred as a result of a high level in steam generator (S/G) "B."The high S/G 1evel was received during S/G 1evel oscillations inadvertentlyinitiated while attempting to runback the main turbine'. The operatorsattempted the turbine runback in response to a decrease in condenser vacuumdue to the tripping of Circulating Water Pump "A."

Prior to the incident, the plant was in Mode 1 at 73% reactor power withCirculating Water Pumps "A" and "B" in operation. Circulating Water Pump "C"was not available du'e to maintenance being performed on the pump. At 1449Circulating Water Pump "A," P-DA2-101A, tripped on low lubrication waterpressure. The low lubrication water pressure was due to the Y strainer beingfilled with silt.

The decrease in circulating water to the condenser caused the condenser-vacuum to decrease. In response,'the Reactor Operator attempted to runbackthe turbine to decrease reactor power. Shortly after the steam dumps opened,a lack of sufficient condenser vacuum (Condenser Available Interlock C-9)caused the steam dumps to shut. The closing of the steam dumps resulted inthe lifting of the S/G atmospheric relief valves. As sufficient condenservacuum was regained, thus clearing the C-9 interlock, the steam dumpsreopened. The C-9 interlock cycled the steam dumps five times throughout theevent thus causing S/G 1evel oscillations. At 1451, a S/G Hi-Hi LevelTurbine Trip (P-14) was received on S/G "B."

The P-14 signal also initiated a FWIS and the turbine trip coupled withreactor power greater than 50% (P-9) caused a Reactor Trip. Reactor powerhad been reduced to 56% at the time of the Reactor Trip. The FWIS trippedboth Main Feedwater Pumps which resulted in an AFAS and SGBIS. TheEngineered Safety Features equipment performed as designed.

The operators recovered from the Reactor Trip via Emergency OperatingProcedures E-0, Reactor Trip on Safety Injection, and ES-0.1, Reactor TripRecovery. The Reactor Trip Breakers were closed at 1535. The FWIS was resetand the Feedwater Isolation Valves opened at 1540.

An evaluation was made of the circulating water pump low lubrication waterflow and pressure trips and it was determined that the trips were notnecessary for pump protection. The low lubrication water flow and pressuretrips were changed to alarm functions. The alarms will thus allow theoperators to evaluate pump problems and secure the pump while reducing power

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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION areaoveo case ao mso-oio.CXPe=ES S/3196

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so that. unnecessary runbacks are eliminated. The trips were changed toalarma on 11/17/84 by a temporary modification. The design change has beenreviewed and was approved on-12/5/84. A Callaway Modification Package iscurrently being developed to implement the change permanently.,

The change from circulating water pump low lubrication water flow andpressure trips to alarm functions provides a means of preventing unnecessarychallenges of the Reactor Protection System and Engineered Safety Features.Therefore, no further corrective action is deemed necessary.

There was no damage to plant equipment or release of radioactivity as aresult of this incident. At no time did this event pose a threat to thepublic health or safety.

Previous occurrences: none

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UNION EtecTnic COMPANYCALLAWAY PLANT "

MAILJNG ADDRESS:5 p.o. nox eso

rutros. uo. e s a si.,-

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a December 13, 1984'

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U. S. Nuclear Regulatory Commission e

D eument Control Desk9Washington, DC 20555

ULNRC-994

DOCKET NUMBER 50-483CALLAWAY PLANT UNIT I

FACILITY OPERATING LICENSE NPF-30 k

LICENSEE EVENT REPORT 84-060-00REACTOR TRIP AND ENGINEERED SA7ETY FEATURES ACTUATIONS

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Gentlemen: s

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The enclosed Licensee Event Report is submitted pursuantt'

to 10 CFR 50.73(a)(2)(iv) concerning a Reactor Trip and automatic

actuations of Engineered Safety Features.

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S. E. Milten ergerManager, Callaway Plant

MET /WRR/JWK/drsEnclosure

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cc: Distribution attached

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' ec distribution for ULNRC- 994.1.

Mr. James G. Keppler+- . Regional Administrator

Office of Inspection & EnforcementU.S. Nuclear Regulatory CommissionRegion III '

.799 Roosevelt RoadGlen Ellyn IL 60137

American Nuclear Insurersc/o Dottie Sherman, Library.The Exchange Suite 245-270 Farmington AveuneFarmington, CT 06032

Records CenterInstitute of Nuclear Power OperationsSuite 15001100 Circle 75 ParkwayAtlanta, CA 30339

NRC Resident Inspector,

Missouri Public Service CommissionD. F. SchnellJ. F. McLaughlin

J. E. Davis (Z40LER)D. W. Capone /R. P. WendlingF. D. FieldR. L. PowersA. C. Passwater/D. E. Shafer/D. J. WalkerG. A. Hughes

W. R. Robinson (QA Record)J. M. PriceM. E. TaylorW. H. StahlG. L. RandolphR. A. McAleenanL. K. Robertson (470)(NSRB)Merlin Williams, Wolf CreekSEM Chrono3456-0021.6

i 3456-0260240ULNRC,

G56.37N. Date

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