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James A.MtaPatrick*Nuclear Power PlantP.O. Box 41

*,Lycoming. New York 13093 j

e 315 342-3040,

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& Authon.Ity nesident uanagerHarry P. Salmon, Jr. .

December 4, 1992JAPP-92-0828 <

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United States Nuclear Regulatory Commission'

Document Contrr' r,e skMail Station P1 437Washington, D.C. 20555

SUBJECT: DOCKET NO. 50-333 -

LICENSEE EVENT REPORT: 92-047-00 - Automatic ShutdownCooling Isolation Due toVoltage Transient

Dear. Sir:

This updated report is submitted in accordance with 10 CFR =

50. 73 (a) (2) (iv) .

Questions concerning this report may be addressed toMr. Verne Childs at (315) 349-6071.Very truly yours,

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HAR)RYP./<'

SALMON, JR.p<

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NAME TE LtPMONE hvM98 2 [' ' ' ' ' IMr. W. Verne Childs, Senior Licensing Engineer

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The plant was shutdown and in the cold condition for maintenance andrefuel. Fuel loading and reactor reassembly had been completed. .On11/4/92 at 1420 hours Residual Heat Removal / Low Pressure CoolantInjection (RHR/LPCI) (BO) Syctem shutdown cooling suction isolation- ,

. valve 10MOV-17 automatically alosed due to a loss of power'to ReactorProtection System _(RPS) (JC) electrical bus (EE) B when a protectivedevice tripped on undervoltage. The transient'undervoltage' conditionwas caused by the starting of a'large (4,500 horsepower) electricalload. Shutdown cooling was returned to service approximately 13

! minutes aftcr isolation ~and the indicated reactor coolant temperature| increast was less than two degrees. Corrective actionsEinclude

'. proceduce revisions and evaluation of the protective device set point.-1 >

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DescriotionThe plant was shutdown and in the cold condition for refuel,maintenance and modification. Refueling and reactor vessel reassemblyhad been completed. One Residual Heat Comoval/ Low Pressure CoolantInjection (RHR/LPCI) (BO) pump was operating in the shutdown coolingmode. Reactor coolant temperature was approximately 160F. Reactor ;

core (AC) decay heat was at a low level because the plant had been 'i

shutdown for approximately 340 days. It was known that reactorcoolant heat losses to ambient were greater then decay heat production

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for reactor coolant temperatures above approximately 150F.

Plant electrical power was being provided from the offsite 115KVsystem through the reserve station service transformers. The ReactorProtection System (RPS) (JC) Electrical Bus (BE) B (Division 1) waspowered from the alternate power source. The alternate power sourceis provided with undervoltage, overvoltage and underfrequency-protection by two Electrical Protection Assemblics (EPAs) arranged inseries Reactor Protection. System Motor Generator (MG) B was out ofservice to allow maintenance work to be performed on an EPA associatedwith RPS MG B. RPS electrical bus A (Division 1) was in a normalelectrical lineup with power to the RPS bus being provided by RPS MGA. Operations-personnel were conducting post work testing ofcondensate system (KA) booster pumps to verify proper electrical andmechanical operation following modification and maintenance work. Thecondensate booster pumps are driven by 4,500 horsepower motors and,except for the reactor water recirculation system (AD) motor generatordrive motors are the largest electric motors connected to the plantelectrical distribution system.

At 1420 hours on November 4, 1992, operations personnel startedcondensate booster pump 33P-9B. RPS B was immediately deenergized dueto trip-of an EPA on the RPS Bus alternate power source. DeenergizingRPS B resulte.d in automatic closure of RHR/LPCI shutdown coolingoutboard suction valve 10MOV-17; automatic isolation of ReactorBuilding (NG) (secondary containment) ventilation and automatic.starting of the Standby Gas Treatment _(SGT) System (BH). Theautomatic actuations were in accordance with design.

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Apprcximately two minutes after the starting of condensate booster i

pur.p B, the tripped EPA and the Engineered Safety Feature (ESP) ,

Act stion System (JE) trips were reset. Valve 10MOV-17 was opened andone RHR pump was started to restore shutdown cooling approximately 13

.'

minutes after the event was initiated. The indicated reactor coolanttemperature increase was less than 2 degrees F. Reactor-Buildingventilation was restored to service and SGT was returned to a normalstandby status approximately 35 minutes after the initiating event.

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The event was caused by the voltage drop associated with starting the :*large (4,500 horsepower) condensate booster pump motor when RPS Bus E

vas being provided power from the alternate source. Starting of *

condensate booster pump A for similar post-work testing did not cause ;

a loss of power to RPS Bus A because RPS Bus A wss provided with power t

from the normal source. That is, RPS Buu A was powered from the motorgenerator set. The rotating inertia of the motor generator set and >

the Generator Voltage Regulator allowed the motor generator _to operatethrough the voltage transient without a significant effect on RPS Bus :A voltage. t

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Examination of strip chart recorder traces of non-safety related 4KV ,

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Bus (EA) voltages recorded in 1982 during starting of condensatebooster pump B reveals a voltage drop of equal to or greater than 10 |percent (with a maximum voltage drop of 11.1 percent) for <

approximately 3.6 seconds.

Technical Specifications 4.9.G.2 requires'an EPA under voltage tripsetting of equal to or greater than-108V with a maximum time delay of i

4.0 seconds. A voltage of 108V is 10 percent below the normal'120V.:-

Examination of the test and calibration procedurec reveals that the ,

-EPA was set to trip at 109.5 +/- 1.5 volts with a time delay setting- '

of 3.5 +/- 0.2 seconds.

Operating procedures do not contain any precautions to inform theoperator that starting a condensate booster pump (or.other largeelectrical load).while an RPS bus is being powered from the aB ernatesource may result in a transient undervoltage trip condition un theRPS.Dus. This deficiency is' considered to be a contributing cause.

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Analysis !

The event requires a report under 10CFR50.73 (a) (2) (iv) due to the"

unplanned automatic actuation (closure) of RHR/LPCI shutdown cooling- '

suction path primary containment (NHJ isolation-valve 10MOV-17. Theautomatic isolation of Reactor Build:.ng ventilation and the automatic

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starting of Standby Gas Treatment due to the " invalid" actuationsignals do not require reporting under 10CFR50.72 or 10CFR50.73.

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The event was not safety significant due to the long time period sincereactor shutdown (340 days) and the resulting low level of decay heat.

Events which result in loss of shutdown cooling during time periods. ;

when significant core decay heat ir. present, such as shortly after ;plant shutdown from power operation, can result in significant

,

increases in reactor coolant temperature. The magnitude of the "

temperature increase is generally dependent on the amount of time that - i

has passed since shutdown, the availability of alternate means ofremoving decay heat and how quickly shutdown cooling can be returnedto service. For this event, as with others that occur as part ofplanned work activities, shutdown cooling can be returned to servicewithin a short time period. The resulting coolant temperatureincrease would be small and would not be safety significant.

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Corrective Actions'

.1. Shutdown cooling was returned to service approximately 13 minutes

after the isolation.'

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2. Procedures will be reviewed and revised as-necessary to provideoperators with precautions concerning the starting of loads whichcause significant RPS Bus voltage transients when the RPS is

_

being powered from the alternate source. Due date, March'30,1993.

| 3. An evaluation will be conducted to determine whether or not RPS'

power source EPA undervoltage and time delay setpoints can beadjusted to values that are closer to the Technical Specification-limits without incurring significant-risk-of exceeding the limits

,

due-to instrument drift. Due date, July 30, 1993.

4. An evaluation will be conducted to determine the bases for the IRPS power-source EPA undervoltage and time delay setpoints todetermine whether or not Technical Specification changes areappropriate. Due date, December 30, 1993.

MRCfare3864(H 91

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Additional Informat_lQD

Failed Components's ilone

Similar Events: There have not been any previous evento in which I . iI

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the starti g of large clectrical londs has causedprimary centajrmont isolation or loss of shutdowncooling. ;

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