Text

Forwards Response to 820317 Request for Addl Info on Outages of ECCS Per TMI Item II.K.3.17.Encl Rept Revised to Include ECCS or Equipment Failures Which Resulted in Occurrence Rept
	ML20083P317
Person / Time
Site:	FitzPatrick
Issue date:	01/26/1983
From:	Bayne J; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D; Office of Nuclear Reactor Regulation
References
	RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM JPN-83-05, JPN-83-5, NUDOCS 8302030441
	Download: ML20083P317 (40)
	v • d • e

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POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMaus CIRCLE NEW YORK. N. Y.10019 4212) 397 6200 LEROY S CLAlR cessarsas oer ecs a TRUSTEES dOHN5.DYSON re v em ut va

'J.:l"".'"J ",'.*,,..

GEORGE L. ING ALLS January 26, 1983 JOSEPH R. SCHMIEDER JPN-83-05

'((.*""Ja'*".-

RiewARou.rLvNu STEPHEN L. B AUM RO BE RT I. MILLONZ1

& esasaak counset Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Additional Information on Outages of ECC Systems Item II.K.3.17

Reference:

1)

Letter, D.G.

Eisenhut (NRC) to all Licensees of Operating Plants, Applicants for Operating Licenses, and Holders of Construction Permits dated October 31, 1980.

2)

Letter, D.

B. Vassallo (NRC) to Mr. Leroy W.

Sinclair (PASNY) dated March 17, 1982.

Dear Sir:

In response to Reference 2,

" Request for Additional Information on Outages of Emergency Core Cooling Systems (ECCS)", Item II.K.3.17, a comprehensive ECCS outage report is enclosed.

In our original submittal dated January 8, 1981, we identified ECCS outages for the years 1976-1980 that resulted in FitzPatrick Licensee Event Reports (LER's).

The enclosed report has been revised to include ECC system or equipment failures which resulted in an Occurrence Report (OR).

These outages pd 8302030441 830126 PDRADOCK05000g P

0

_2_

occurred during Preventative Maintenance (PM), Surveillance Tests (ST's) or Instrument Surveillance Tests (ISP's) and are so noted in the report.

In the process of reviewing ECCS outages, several additional instances of system unavailability which resulted in LER's were identified and added to the report.

All outages added to the report have been marked with an asterisk.

Other additions to the report include a separate column identifying the system, and entry of the affected train and component where applicable (i.e., 10-MOV-16A = System 10, Motor Operated Valve 16, Train A).

This report now identifies planned and unplanned outages of ECC systems and the emergency diesel generators which are due to system inoperability, preventative maintenance and surveillance testing and which resulted in LER's or OR's.

Outage durations which are not specified are not available because:

(i) the system or component was not returned to service due to interaction with other ongoing work; or, (ii) the system or component was not accessible or practical to repair until the next scheduled outage.

Should you require any additional information, please do not hesitate to contact J.A. Gray, Jr. of my staff.

Very truly yours, g

J. ' {. NB&yh L

Executive ice President Nuclear Generation cc: Mr. J.

Linville Resident Inspector U.S.

Nuclear Regulatory Commission P.O. Box 136 j

Lycoming, NY 13093 l

l l

r:

1 e'

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC) 1

('

i LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAI g1 76-06 1760321 lRCIC IWhile performing ST-24C RCIC flow rate lManual isi l

l ltest, the turbine was started, exhaust ihaust val' p~

l l

lpressure increased and rupture discs l

l l

l blew out.

I i

l I

l p~

76-10 1760403 LADS /

IDuring surveillance testing (ST), the lInstrumen l

lHPCI Ifollowing switches were found to be a l

I l

Imaximum of 0.05 psig higher than I

p" I

l ITechnical Specification requirements l

l l

lof 20 psig:

10-119A, C, 101D, 100B, l

l l

lC, D, 5-17A, B, & D.

l p"

l l

i I

76-12 1760405 l ADS lDuring ST, pressure switch 2-3-55D l Mechanics 1

1 Iwould not function.

lbourdon S OI-1 I

I I

76-30 1760414 lHPCI lDuring ST-4E the HPCI gland seal con-l Normal wc; l

I ldenser cooling side gasket blew out.

I p"

1 I

I I

76-33 1760420 lHPCI lDuring ST-4E, the motor for 23-MOV-57 lShort in l

l l(HPCI tous suction valve) burned up I

p" i

I lwhen given an open signal.

I I

I l

I I

ST - Surveillance Testing gn" PM - Preventive Maintenance g;

TS - Technical specifications ISP - Instrument Surveillance Procedure p'

790327 - Year-Month-Day 0!:

t':

4; e:.

41 l

0 f, page 1 1

ENSEE REPORT DATE EQUIP-g RETURNED MENT TO DOWN JSE CORRECTIVE ACTION SERVICE TIME g

)lation ex-l Removed and replaced rupture discs.

IBe t IN/A 72 was closed. I lestimate I

g l

imade 760327 I

I I

g b drift.

IRecalibrated immediately.

1760403 11 hr.

I l

l I

I I

g I

I I

I l

i I

g i

I L stop on lAdjusted mechanical stop so micro 1760406 lN/A bbe.

Iswitch contact could be made.

I 1

g 1

l l

ar.

l Replaced gasket.

1760414 16 hrs.

I I

Limitorque.

IReplaced motor.

In the interim, kept 1760514 IN/A Ivalve open to perform function.

I I

g'h l

I I

l 9) 65 9'

9 9:

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j II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC C

LER/

EVENT

(;

OR NO.

DATE SYSTEM DESCRI PTION CA 76-38 1760424 lRCIC lDuring ST-1C, primary containment valve lLimitorg

('

l I

lexercise, 13-MOV-15 failed to close.

l i

l IDuring the test, the outboard isolation l l

I ivalve 13-MOV-16 did operate.

I (j

l l

I l

76-45 1760713 IRHR lDuring ST-2G, 10-SOV-263B, RHR process (IncorrecG l

I isample line failed to isolate when I

(;

I l

lsignaled to do so.

I I

I l

l 76-35 1760504 lRHR lRHR pump "C" breaker was racked out for IOperator

(;

I I

imaintenance thus disabling a portion of I l

l Ithe RHR system. ST was not performed l

l 1

lon remaining components of system as I

(

I l

frequired by Tech. Specs.

l I

I l

76-21 1760519 IEDG IDuring ST-98, when initiating "B" and IFailed sg

('

l I"D" emergency diesels, the "D" diesel Irelays.

l l

lwould not start.

l I

I I

I

(.

76-24 1760611 IHPCI l Annunciator alarmed on HPCI valve over-l Fire in g I

l fload or loss of control power.

Ivalve 23-I l

lInvestigation revealed fire in BMCC 6.

I l

i I

I 76-25 1760616 lEDG JDuring ST-9B (EDG full load test) it l Problem it l

l lwas noted that they were unstable, al-Icircuit.

I I

Ithough they did perform properly.

I I

l IFound that the droop circuit had I

i l

Idrifted, causing the instability.

I I

i (Droop is necessary for testing only, l

I l

Inot for emergency operation.

I I

l l

I I

I l

s:

m i

b

,~

4

l i

ENSEE REPORT DATE EQUIP-RETURNED MENT TO DOWN JSE CORRECTIVE ACTION SERVICE TIME e torqued out. lAfter several attempts, valve closed 1760424 lN/A lwithin the snecified time frame and l

l levent.could not be duplicated.

I I

test signals. ICorrected procedure.

1760713 lN/A I

I I

l I

trror.

ISurveillance testing was immediately 1760504 lN/A linitiated.

I l

l l

l I

i i

trd tach IReplaced.

1760519 14 hrs.

l i

I I

l l

l

'eaker for IFire extinguished and breaker replaced. 1760612 112 hrs.

')

IOV-16.

l l

l 1

1 I

I I

I

3 idroop IAdjusted droop circuit.

1760616 lN/A I

i l

l l

l I

I I

I l

l l

l I

I I

l i

I I

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9 9

9

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s; II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICE j tb l

LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAL 4b 76-37 1760619 lRCIC lRCIC turbine would not trip due to ISteam leah l

l Irusty linkage. This event would not I

l l

lhave posed any particular problem as l

l l

lthe turbine would start and the system i j

I l

loperate as required.

l I

I I

l 76-90 1760630 LADS IFailure of 02-RV-71E relief valve to l Unknown.

I I

Ireset following a turbine trip and I

8D I

I lsubsequent scram.

I I

I 76-42 1760703 lRHR lDuring ST-2C, MOV operability test, lLarge diff 8D l

l 110-MOV-25A motor burned up.

lpressure a j

l i

l I

76-97 1760714 lRHR IDuring refueling, while attempting to IMotor burr 8'

l I

lopen 10-MOV-18 to utilize shutdown l

l l

Icooling, the breaker repeatedly tripped.1 i

i l

I 8'

76-98 1760714 lRHR IDuring refueling while attempting to lAppears um l

l lutilize shutdown cooling, could not Idriving.

I I

lopen 10-MOV-17.

I 8'

I I

76-46 1760721 l ADS lDuring normal operation, relief valve lExcessive I

i 102-RV-71E opened, lpart of o lRockvalv dP l

l l

a i

I I

i 76-53 1760815 lHPCI IDuring normal operation, 23-INV-79, lInverter f d'

l I

linverter power supply for HPCI tripped I

l l

land could not be reset.

1 I

I I

l 8P 76-80 1761119 lHPCI 123-MOV-57 motor burned up while auto-l Apparent t l

l Imatically transferring HPCI suction to lload cause l

I ltorus on torus high level.

land failua C2 l

l l

l windings.

C7 0

0 0

0 l

b5 f

1, dp

%_c, page 3 8

TSEE REPORT DATE EQUIP-RETURNED MENT TO DOWN TE CORRECTIVE ACTION SERVICE TIME on 13-MOV-32.IFreed up and lubricated linkage. Reset 1760619 IN/A land tripped linkage for approximately I

l 11 week.

I l

l l

1 I

I I

l l

1 IValve reset at approximately 500 psig 1760630 IN/A Icoincidental with removal of fuses l

l 4D Ifor 02-RV-71E solenoids.

l l

1 1

I brential IMotor replaced.

1760703 120 hrs.

4D sross valve.

I l

l I

I I

Qd out.

IRemoved and replaced with rewound motor-1761126 IN/A g

Ivalve kept in closed condition until I

I lthen.

1 I

I I

I e

Sor not IReplaced motor.

1760716 IN/A I

I I

l l

I e

i I

I pilot leakage IValve closed with no operator action.

1760722 IN/A

$ Target l Proceeded with plant shutdown for I

l gb problems.

Iinspection and changed valve with spare.I I

l I

ailure.

lInverter was immediately transferred 1760815 14 hrs.

e lto alternate supply.

Inverter was l

l Ireplaced.

I l

I I

I 4

Erque over-IManually opened 23-MOV-57 and replaced 1761119 112 hrs.

$ ovarheating imotor.

I l

of motor l

l I

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i O

4 L

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a TI.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICI O

LER/

EVENT g

OR NO.

DATE SYSTEM DESCRIPTION CAI 76-65 1761011 lEDG IFire in "A" Emergency Diesel Generator ILoss of 1:

O l

l lturbo-charger during ST-9B.

lTurbocharc I

l l

I 76-67 1761026 lLPCI lDuring ST-2H, valve 10-MOV-24A failed IMotor burr g

i i

Ito open.

I I

i 76-69 1761101 IRCIC IWhile stroking 13-MOV-16, outboard l Normal wee O

I I

IRCIC isolation valve to verify limit Iswitch net I

l iswitch operation, the valve bound up iment.

I l

land the increased torque burned up the l

C l

l Ivalve motor operator.

I I

I 76-72 1761109 IHPCI lFollowing scram with subsequent HPCI lApparenti O

I I

Iinitiation, HPCI started and then l

I I

lisolated.

I I

I O.

76-76 1761115 ILPCI/ IDuring ISP-5-3 found pressure switch IInstrumeni l

ICORE 12-352C low out of Technical Specifica-1 l

l SPRAY ltion requirements.

1 O

I l

l l

76-77 1761117 lEDG lDuring ST-9B, "B" EDG failed to start.

lGenerator i

l I

linoperabl<

O I

I I

I 76-78 1761117 IEDG lDuring ST-9B, Fuel oil transfer pump (Worn out.

I i

193-P-C2 would not pump.

l l

O, I

I I

i I

I i

l I

I I

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l I

I l

1 I

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i l

p-1 I

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p, page 4 i

g WSEE REPORT DATE EQUIP-S RETURNED MENT TO DOWN

@E CORRECTIVE ACTION SERVICE TIME S

9xa oil to lReplaced turbo-charger.

1761025 IN/A Gr.

I I

I g

I l

l ed up.

lManually opened valve so system would 1761026 IN/A lfunction in LPCI mode - replaced motor. l l

g I

I I

e cnd torque IThe inboard valve was closed providing 1761101 IN/A dhd adjust-lPCIS and 13-MOV-16 was manually opened. l l

g lThe valve motor was replaced.

I I

t i

i l

iigh flow rate.lStarted HPCI manually and installed 1761109 11-1/2 lateam signal snubbing pins.

I thrs.

g i

l I

l sdrift.

IPecalibrated immediately.

1761115 lN/A 1

i I

1 I

I I

g-Gcch relays

("A & C" EDG's run with ECCS loads. The 1761117 18 hrs.

7.

Itach relay was replaced.

I I

I l

I g.

ITested remaining pumps - OK and replacedl761119 IN/A Iwith spare pump.

1 I

I l

l l

i l

I I

l l

I i

g6 l

1 1

I I

i tl 4

b II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICI O'

LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAT 76-82 1761122 LADS l Relief valve 02-RC-71E lif ted resulting l Relief va:

l l

lin reactor scram from low pressure.

liifted.

76-88 1761201 l ADS l Loss of bellows monitoring on relief lFound DC (

i l

Ivalve 02-RV-71A.

lpressure r g

I i

l I

I I

i I

I I

I i

I I

76-93 1761212 LADS IBellows leakage alarm on relief valve ICrimped wj l

l 102-RV-71E.

la false si l

I i

I 76-94 1761215 lEDG lDuring ST-9B, "A" EDG failed to start l Relief vaJ I

idue to low lube oil pressure.

lon soak bc I

I I

I 76-55 1760821 IRCIC lDuring ST-24C, noticed steam coming IRupture di O

i l

I from leak-of f between RCIC rupture l

l l

Idiscs 13-2-3.

I I

I O

76-64 1761014 lRHR lWhen shutting down "B"

RHR pump, found l Discharge l

I l check valve 42B leaking and unable to Ifailed.

l l

Ikeep "B" RHR pump filled without l

I I

icausing the pump to rotate in the re-l I

lverse direction and increasing the l

l I

ltorus water level.

I O

l l

76-90 1761203 LADS IIt was discovered that the error im-l Setting th l

I Iposed by nitrogen setting was beyond +

twith nitro I

I 11% for relief valve 02-RV-71G.

laccurate t l

l l

lsetting.

I I

ADDITIONS O

O O

O

~O N

l O

u

/

L r, page 5 I

8

NSEE REPORT DATE EQUIP-RETURNED MENT TO DOWN 7SE CORRECTIVE ACTION SERVICE TIME

.va 0 2-RV-71E lThe valve was removed and replaced 1761123 lN/A twith a spare valve.

1 I

dP l

l i

Iround on IThe bellows leak detection was discon-1761201 122 hrs.

witch.

Inected and thus inoperable on this 1

I dP Ivalva. This condition is permitted by I

l ITechnical Specifications 4.6.E.3.

l l

lDuring a subsequent outage, the groundedl I

lwire was replaced.

I l

i I

I Te produced IReplaced wire.

1761212 lN/A gnal.

l l

1 1

va lifting I"A" EDG was manually started and repeat l l

ek pump.

lof ST-9B was successfully completed on l

l

!next start (lube oil low pressure not ini l

leircuit for emergency start).

Relief I

l 4>

Ivalve was replaced.

I I

I l

l Ic cracked.

IDisc was replaced.

1760821 lN/A (p

I I

l I

I I

e check valve IOverhauled discharge check valve.

1761016 IN/A I

I I

I e

1 I

I I

I l

l 9

I I

I e ccturtion lRelief valve was reset to required 1761203 lN/A

'en is less Ivalue.

I I

e g

h;n steam l

l l

I I

O S

O O

!O

l II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICI e

LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAL

~

77-06 1770114 lEDG lDuring routine surveillance, EDG "D" lOn emerge l

I lon low lube oil pressure, tripped, ltrip is b3 I

I I

I 77-10 1770224 lHPCI lDuring routine surveillance, HPCI level lOperator I

l lswitches were found valved out of I

I I

lservice.

I I

l 77-17 1770314 iRCIC lDuring routine tests, RCIC turbine 1 Low oil le I

I Itripped while being started.

I l

I I

I 77-21 1770420 lEDG IDuring routine surveillance test, ITachometer l

l lEDG "A" failed to start.

Ifailed.

I l

l l

77-28 1770521 lRCIC lRCIC turbine damaged by overspeed.

1011 line l

I I

I 1

1 1

I l

I I

l 77-30 1770528 LADS lDuring normal operation, a ground on IDC ground.

I l

102-RV-71L was discovered which pr e-1 g

I l

l vented the bellows failure indicators I

1 I

Ifrom working.

1 77-35 1770611 IHPCI lDuring surveillance testing, 23-MOV-58 l Unknown.

I I

lfailed to open.

l I

I I

i 1

I I

I 77-49 1770928 lRCIC lDuring surveillance testing, RCIC steam IImproper s I

l lsupply valve 13-M0V-131 would not open. Itorque swi-l I

1 l

77-52 1771008 lHPCI lDuring surveillance testing, HPCI steam IImproper s I

l l isolation valve would not fully close, lof torque J

l I

I I

9 9

9

=

f m

rp 6

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iSEE REPORT DATE EQUIP-RETURNED MENT TO DOWN 3E CORRECTIVE ACTION SERVICE TIME O

Jy start, lEDG started on second start. No 1770114 11 hr.

l3assed, lequipment defect was found.

l l

I l

1 ror.

IRedundant switches were found operable. 1770311 IN/A I

I I

I l

l I

fel.

lAuxiliary oil sump was installed. Oil 1770319 lN/A Iwas added to turbine oil sump.

l I

l l

l relay ITachometer relay was replaced.

1770425 lN/A 1

1 1

I I

l tilure.

ISite personnel installed a support 1770531 IN/A l bracket for oil line. HPCI system l

l lwas verified operable. RCIC turbine l

1 loverhauled.

I i

4h l

I I

IGround was repaired.

1770916 lN/A I

lDuring Refuel l

tb l

lOutage I

l l

l I

l l

lAll electrical circuits were checked.

1770611 11/2 hr.

IValve was cycled and returned to l

l lservice.

I l

I I

I

-tting of ITorque switch was reset.

1770930 lN/A

ch.

I l

l i

tting of ITorque switch was reset.

1771008 lN/A witch.

1 I

l 1

1 1

b g

O P

e i

e II.K 3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICE

- w 9

LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAU

~

j 77-61 177116 lRHR lInstrument setpoint change for l Operator e l

i 110-PS-120A-H was implemented prior to l

l l

lNRC approval.

l I

I I

I

=-

77-67 1771129 1RCIC lDuring ISP-9-1, instrument channel IDrift.

1 I

lwas found high out of I

I I

Icalibration.

I I

l 77-71 1771228 lRCIC 1RCIC pump 13-P-1 was made inoperable l Filter clo i

l Ifor 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to clean cuno filters.

I I

I

77-0021770112 lRHR/

lWhile performing ISP, found setpoint IFormer set l

lLPCI lof RHR and LPCI for isolation on Imade on de I

I lincreasing pressure was too high.

lpressure.

I I

77-0241770404 lHPCI lHPCI test valve failure.

IBurned coi

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l l

I lfor test v 1

I I

l 1

I I

l I

ADDITIONS o

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DATE EQUIP-(g RETURNED MENT TO DOhW r

lE CORRECTIVE ACTION SERVICE TIME (g

i ror.

110-PS-120-A-H were reset.

1771117 lN/A I

l l

I (g i l

i l

I I

I t

ll3-DPIS-84 was calibrated.

1771202 lN/A

g [

l I

I I

I l

l lg ged.

IFilter was cleaned.

1771228 17 hrs.

1 I

I I

lg

ing was Iset isolation trip within specified 1770112 lN/A reasing frange.

l l

1 jg i

I in breaker IReplaced coil.

Failed coil did not 1770404 11/2 hr.

ilve.

Idisable HPCI.

Operator removed power l

l

-l 4 Ito locate coil, but could have i

I Irestored power at any time.

l l

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II.K.3.17 REPOPT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICE O

LER/

EVENT 09 NO.

DATE SYSTEM DESC P I PT ION CA 78-08 1780210 IRCIC IDurino norral plant operation, IElectrical i

l ismcke was being emitted f r om I

I I

lbreaker 13-MOV-131 (RCIC turbine I

I I

Isteam inlet valve motor breaker).

I I

l l

l O

78-04 1780215 IEDG IDuring ST-98, "A"

emergency diesel IBlown fus I

loenerator tripoed.

l I

I I

I

' O 78-18 1780404 ILPCI ILPCI Loop "A"

inoperable, to repack l Packing gl l

I Ivalve 10-MOV-27A.

I I

i l

l 78-34 1780508 ICORE IFailure to run required ST on redundant lOperator e l

ISPPAY lsystem before de-energizing core spray l

I I

ldischarge valve motor to adjust i

I I

Itorque switch.

I I

l 78-40 1780518 ILPCI IDurinq normal plant operation, LPCI IFailed SCR I

I linverter/ charger tripped resulting in linverter.

I I

l loss of "B"

LPCI independent power.

I l

l l

l 0

78-56 1780722 ICOPE IDurino normal op9 ration, while per-lLimitorqu I S P RAY lforming ST-lC on 14-MOV-11B (core spray Ishaft key I

I Isyrtem outboard isolation valve) the I

g7 f

I Ivalve would not close when qiven a l

l I

!close signal by the operator.

I I

l C

78-58 1780805 IRHP l Du r i n'1 ST-2A, "A"

loop RHR flow IElectrical I

lindicator 10-FI-133A failed.

I I

l l

I g

78-60 1780806 IHPCI I Dur ing rout ine testing, HPCI torus lLimitorque l

l I

l suct ion valve 2 3-MOV-57 would not Iwas burned 1

i l

loperate electrically.

I g

I I

O 4

0 9

I o

9

?

1 1

y' 0

-6 O

_- g-i l

M

(, page 8 O

NSEE REPORT N

DATE EQUIP-RETURNED MENT g

TO DOWN SE CORRECTIVE ACTION SERVICE TIME O

overload.

IReplaced 74 coil, 42xC coil and several !780210 l13 hrs.

Iburned wires.

1 I

e M

I I

I W

I I

I 9

1 i

e Y

IReplaced blown fuse, performed 1780215 11 hr.

loperability tests.

I I

l l

1 e

_a and leak.

IValve was repacked.

1780406 140 hrs.

.M i

i i

l I

I e

tror.

lMotor controller was immediately re-1780508 13 min.

O lenergized after readjusting torque l

l Iswitch.

I I

e l

i I

g i

i i

m

's in the IFailed SCR's were replaced.

1780519 118 hrs.

C l

I l

M l

i I

1 I

I e

6 operator 1 Replace limitorque operator shaft key.

1780723 18 hrs.

7 sheared.

I l

I r

I I

I t

M i

l 1

1 I

I 1

I l

4

.M

short, lThe short was cleared and instrument 1780805 14 hrs.

Ireturned to service.

1 I

I I

I e

q motor IReplaced limitorque motor.

1780807 136 hrs.

M up.

I l

i N

I I

I t

-m i

I l

6

-6 7

4 M

N M

e 4

~6 M

N g

,4 3

m

t l

l 1

r II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC.

s LER/

EVENT OR NO.

DATE SYSTEM g

-DE SC R I PT ION CAi

~

78-70 1780828 lEDG IDurinq normal 07eration, operator IPump misa l

l Inoted noisy operation of "A"

E DG lube i

I I

loil soak back pump causing " A" E DG to i

I I

lho placed out of service.

I I

I 78-75 1780902 ICORE IDurinq normal operation, while per-lHigh diffe i

ISPRAY Iforming ST-3D, 14 -M OV-12 B (inhoard Ipressure.

I I

Icore spray injection valve) would not I

I I

lopen electrically.

I l

I I

l 78-R]

1780915 ILPCI IDu.ina ST-2H, circuit breaker for RHR l Power fuse-t I

Irump 10-P-3C would not charge, I

I I

fronderina pump inoperable.

I I

I l

l 78-83 1780923 LADS /

ILogic power for "B" LPCI subsystem IOperator I

ILPCI lde-energized for ADE maintenance.

l i

l l

l 78-97 1781215 IHPCI/

IDuring ISP-10, eight temperature IOper ator r i

IRCIL lswitches used for HPCI line ruptute l

I I

Iwere found improperly set.

I I

78-48 1781205 IEDG IDuring start-up "A"

EDG tripped while IMisadjust, i

lbeing paralleled.

lengina gos I

I I

I 78-109 17Al224 IRHR lDurino s t a r t-u p " A " RHR loop could not IDischarge l

I lhe maintained full of water.

Ivalve fail I

I I

e AP O

- - =

' ~

+[

,l ;

..4 a.

t v.

p S.

&{l $

-' ~ / -l' c,d't*, page 9 (NSEE REPORT

'~

DATE EQUIP-j.

RETURNED MENT

.e.. f, ' ';

TO DOWN

^.S..,',,,,,

]SE CORRECTIVE ACTION SERVICE TIME f[ '. '

,ignment.

lAligned motor and pump.

1780828 15 1/2 A ~"' '

+

l l

lhrs.

I l

l

.',j...

' g*

I l

l

.- v a

i l

I

,. T irential ll4-MOV-12V was cycled manually, 1780902 IN/A land declared operable.

I i

.q g

},

i 1

1 a

- E.. /..,

4 l

l 1

.r..

I I

l ei.

.s holder IStraightened fuse holder clip.

1780915 11/2 hr.

1 I

l I

l l

)..;

.?

I I

I eror.

IPower restored.

1780924 120 hrs.

- r.

4, 1..

1 l

l p

_ ~j _...

gror.

ITemperature switches readjusted.

1781215 12 hrs.

f' 4.'

l l

l 5..-

m~*

l l

l r;

l l

l

., e.4 y...

ant of IGovernor properly adjusted.

1781205 13 hrs.

%~ [ *' ' ' '

1I.

5rnor.

I l

l

-[, '

l l

l 3

- 7;., 9

-s.

pheck I"A" RHR pump was placed in operation 1781225 138.8

'g 7

~

ure.

lin the Torus cooling mode to comply I

lhrs.

' ~ ;1 1- ( '.

.I Iwith Technical Specifications.

I l

v.p> b..,

)

l l

l e,

,[

\\

..'d

' ?e '.

A?

i.. -

}; *.,._l,k '.*.', [ '

~

s..

,.w4 m

-e

..I 4

7.A

,e

. ^',3

, t -

g;.,.

k

'~~

h

.l c.

s h

p.

'* ^

l

.,>__7.

[ r -;

w a

g

.c,

.y. 7,:

- u, s,._,.

'.:. ' _ y;7.

l. ',

J%'._ -:

Q

%.Oib -C'[ ', [.'

.. ~

t

~

.Q a.

.? r ~..

o

\\

I II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC

{

LER/

EVENT OR NO.

DATE SYSTEM DE SC RI PT ION CA

78-020l780408 lHPCI IDuring normal operation, whi'e per-l Fasteners i

I i

Iforming ST-4C, valve 23-MOV-14 motor

! attached l

I loperator separated f rom valve body voKe. l plate to i

l i

I

78-0211780410 I PC I C lDuring ST, a malfunction of limit IDirt on C I

I lswitch on P-MOV-131 resulted in loss Icaused lo.

I I

lof speed control on RCIC turbine in lcontinuiti i

l I" test" mode.

I I

i

78-0221780410 ILPCI IWhile performing ST, LPCI valve ILow torqu I

I 110-MOV-25A failed to open.

Isetting.

I I

l

78-0261780429 IHPCI IDuring reactor start-up and after in-IThe torqu l

I Icreasing pressure to greater than lassociate I

I 1150 psig, the HPCI steam isolation valvel"open val I

123-MOV-15 would not open.

Peactor lwas out o l

I Ipressure was lowered to less than l'O I

I I

Ipsig, where HPCI is not required to be l

l I

looerable (Tech. Specs.

3.5.c.1).

I I

l

78-0521780719 ILPCI ITech. Spec. amendment increased the low ITech. Spe I

I Ipressure coolant injection from 50 to INo. 37 Ju l

l 1125 psig for ADS permissive.

ISP-46 ILack of C l

I lwas revised to reflect the new value lin recali l

I lbut the pressure switch was not I

I l

limmediately recalibrated.

I I

I

7 8-0 6 5 l 7 8 0 81f> ILPCI lDuring normal operation, valve operator IControl I

I l(02-MOV-54B) lost power.

Loss of con-l blown.

A I

I Itrol power renders the valve incapable Igrounding l

I lof automatic closure or remote manual linside pr I

Iclosure i.i event of LPCI system initia-Itainment.

I I

Ition as required by TS-A-3.5.A.5.

I I

l l

l I

I l

I

ADDITIONS e

O 9

WP

~

l, E

..,. ;.. e _,r.

4,,,..p.

s...-

g.

.,...q.

.;...., y m -

.s

e....

_, 'w.

3 -: 1. ;.. - ;. %.m p {,.: W,-c) vs W s',py;v,s.\\- f G..*6

" : +..,Q.L i...y _s.

p i

',. i.. (. J. -... -

.s:

.y

$~'E

., page 10

.c NSEE REPORT s

r f

e DATE EQUIP-RETURNED MENT l,+**

TO DOWN 4..'

r).

lE CORRECTIVE ACTION SERVICE TIME

',.s '-1 which IFasteners were replaced.

1780410 (48 hrs.

+

idapter l

l 9.

'ok e failed.

I I

l I

7 I

l 4

intacts IContacts jumpared and system in opera-1780410 14 hrs.

,1 ~ ~ "

ls of Ition while contacts were cleaned.

I I

,4 I

I I

~ '

1,, *.*

l l

l p

Q.:.

I I

'g.

switch ISwitch setting was readjusted, and ST 1780410 12 hrs.

i TV -

Icompleted satisfactorily.

I I

V I

1 I

I switch IThe torque switch was reset.

1780419 12 hrs.

"b

~.' I with the l

I I

a 7. ~ ~

,.. t e" circuit l

I I

f.,.,.

.'A adjustment.

I I

I

' i l

p

.y :

I I

l I

..r',.

+

I I

~.

1 I

I Amendment ISwitch was recalibrated to the new 1780719 IN/A s

e 14, 1978 Ivalue on 780719 I

I i-mmunication I

I l

e 4

rating same.

I I

i

~^

I l

j '

f%

i en 1

I I

e f,

I l

l 1

.... ~=

ser fuse was IFuse was replaced and the valve was 1780816 12 hrs.

'-ll' O,

l parent Iclosed to preclude the need for auto-1 I

...?

or a short loperation.

Ground was found in control I l

i.

I.

mary con-Icircuit and repaired on 10/03/78.

I I

e i

e

- (.-+ fWe<

I 9

I I

6 --

r..

1 k

s.

l

[

i e

~. ~

.y

".e

f. :<. -

. Ly e

4' N

e

's

_e av g e 1

.g,.,, pm d

4

,;s., = -.,; -p o

.: :. - y g

e s

l f?

.A 3'

,-l i

\\

p e-r

(

1 a

I o

=

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIc_

e,

~~

W w

LER/

EVENT a

g OR NO.

DATE SYSTEM DESCRIPTION C.*

" ]"

79-20 1790327 lEDG lDuring ST-98, air compressor 93-AC-B1 l Dirt in u l

l ldid not load.

I l

l l

l M

i l

l I

3 i

79-23 1790411 lHPCl IDuring inspection of HPCI turbine l'UCI turt Z

I l

Ipiping for fixed fire suppression 1

l l

lsystem, turbine must be disassembled 1

=

1 I

l violating Technical Specifications.

I 9

p'-

I l

I i

79-24 1790428 IEDG lEmergency service water pump failed to l Normal wt C

g i

l Imeet shutoff head requirements of I

l l

ITS-4.ll.D.l.6.

I g

i l

79-35 17906C7 lRCIC lRCIC low pump suction pressure switch lout of ca C

l I

lsetpoint too high (15.7" of mercury).

I d

g i

l ITechnical specifications require I

1 I

i 15".

I l

l l

l I

l l

l d

g-79-39 179062 7 lLPCl lDuring ST-35A, "B" loop LPCI injection IFailure o f

I I

lvalve failed to open (10-MOV-25B).

Iswitch in I

I I

loperator.

(*'

I i

l I

m t

k.

~

m 3

1 7

~

M

-d g

-=

M i

g M

1 I

A h

S-

i

/

ENSEE REPORT, page 11 DATE EQUIP-RETURNED MENT TO DOWN ISE CORRECTIVE ACTION SERVICE TIME tloader.

IUnloader was disassembled and cleaned.

1790514 lN/A l

IPipe Stress I

I lOutage l

l I

l Lne inspection.lNone.

1790615 lN/A l

l Plant in cold l

I lshutdown for I

l lpipe stress.

I e

1 I

l nr.

loverhaul and minor modification of 1790803 13 mos.

limpeller.

IPlant in cold I

I lshutdown for i

I l pipe stress.

1 I

I I

e

.ibration.

II&C personnel recalibrated pressure 1790607 12 hrs.

iswitch.

In addition, the surveillance IPlant in cold I

ltest frequency has been increased from Ishutdown for i

e lmonthly to weekly until satisfactory lpipe stress.

I lperformance has been demonstrated.

1 i

i i

I s,

" torque IReplaced torque switch assembly.

1790702 IN/A motor i

IPipe stress l

I loutage.

I e

i I

I

's o.

9 O

O O

i i

6

i k l

()

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC

('

LER/

EVENT gl OR NO.

DATE SYSTEM DESCRIPTION CA 79-40 1790630 lRHR lDuring ST-2A, reverse rotation of RHR l Discharge g[

l l

l pump (10-P-3A) was noted.

Inot fully I

l l

I 79-42 1790713 lRHR lDuring ST-2R, RHR service water pumps lOrifice i I

I Icould not meet required Technical lline was g-l I

ISpecification 4.5.B.1 l

I I

79-46 1790830 LADS /

l Deficiencies in the design of cable lHPCI and gp l

lHPCI lseparation between ADS and HPCI.

lin the sa i

I I

l I

I I

l g;

79-58 1790903 lHPCI lDuring plant heatup, the HPCI turbine ITechnical i

I lwas intentionally uncoupled from the Itions req l

I ipump (for overspeed test) violating loperable gj l

l ITechnical Specification Appendix A lto startu l

l 13.5.C l.a.

Icommencem I

I I

lstartup, g;

I i

l Ido overs I

I I

79-64 1790906 lHPCI lDuring normal operation, while per-IInadequat g;

l I

lforming ST-4E, the motor on the con-ltion.

l l

ldensate storage tank HPCI suction I

i 1

Ivalve failed. The motor from 23-MOV-57 l g;

l l

l(HPCI torus suction valve) was to be l

l l

lused to replace it.

However, when the I

1 1

Imotor of 23-MOV-57 was removed the 1

y i

l Ivalve was not checked in the open i

I I

1 position as per technical specifica-I l

I ltions.

I gi I

I I

I 79-71 1791004 lEDG IDuring normal operation, emergency IBulletin l

l lservi e water pipe support H15-124 was leffort.

th '

1 I

lfound inoperable.

I I

I O

O O

e 4F 4

I

()

8 H, page 12

NSEE REPORT DATE EQUIP-I RETURNED MENT TO DOWN ISE CORRECTIVE ACTION SERVICE TIME I

check valve IValve disassembled and repaired.

1790630 lN/A closed.

I l

l I

i discharge IOrifice in discharge line temporarily 1790823 lN/A

oo small, fremoved, after resizing hole.

IPipe stress l

l loutage l

i I

I

,DS cables l Rerouted HPCI and ADS cables with 1800804 IN/A p

ie tray.

Itermination performed during refuel l

I loutage.

I l

j l

I l

Specifica-l Reactor pressure was maintained below 1790903 lN/A ire pumps 1150 psig.

1 I

rior to l

l I

p

- after I

l I

. nt of I

l I

lant can I

l l

ed test.

I I

i 1

I I

! communica-123-MOV-57 was placed in the open 1790906 15 hrs.

W.

Iposition as soon as the improper l

I leondition was discovered.

I I

I l

l 1

I l

I I

I p,

I I

l a

l i

I 9-02, 07, 14 IH15-124 was modified.

I791007 13 days I

l l

l I

I I

I O

O O

9 e

O

0

(

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC O

LER/

EVENT RN ATE SYSTEM DESCRIPTION CA O

79-73 1790914 lEDG lDuring ST-9B, EDG "C" tripped on over-l Loose con i

i lspeed during the engine start sequence, loverspeed g

79-81 1791018 lRHR/

14 RHR pipe supports H10-135, H10-140, IBulletin l

lLPCI lH10-4CB, and PPSK-727 found to be 114 effort O

i I

linoperable.

lation to r I

I I

Ithan furt o

l l

l lac-79-86 1791025 IRHR/

!? pipe supports H66-62, H46-1, H46-2 1

IEDG lH46-3, H46-27A, H10-175 and H10-177 l

O I

I Idetermined inoperable.

l I

I I

I 79-87 l791029 lRHR I3 RHR pipe supports determined 1

0 i

iinopere31, i

l I

I I

79-91 1791020 lRHR lDuring ST-2B, RHR pump "C" f ailed to l Limit swi g

l l

Istart properly, lsuction v i

l i

l improperl O

79_90 i791o11 iHPCI lAs a result of hanger modification lBulletin 7 l

l ifor PSA, the cable for 23-MOV-17 re-114 effort.

I I

Iquired rel ati n, disabling the valve. l O

l l

lThis caused the HPCI system to et ar l

l l

la degraded mode.

l 79-92 l791013 iHPCI lDuring normal operation, an inter-l Loose lead l

I imittent isolation signal to 23-MOV-15 larea tempe l

l l(HPCI system steam isolation valve)

Iswitch.

O I

I Iwas noted.

I I

O O

h

Q y

.f 0

O

-, page 13 NSEE REPORT DATE EQUIP-g RETURNED MENT TO DOWN SE CORRECTIVE ACTION SERVICE TIME ection on l Loose connection was repaired.

1790915 124 hrs.

load switch.

I l

l g

i I

I 9-02, 07, &

IModification to the supports was com-1791024 lN/A

- determin-Ipleted within the 7 day time frame.

I l

g epair rather I

l I

er analysis l

l l

l 1

l g

i l

l lModification and upgrading of the 1791101 IN/A isupports was completed within the I

g 17 day time frcme.

I l

l l

l IUpgrading of the 3 supports was 1791105 lN/A g

Icompleted within the 7 day time frame.

I l

l l

I ches for iLimit switches for 10-MOV-13C were 1791020 14 hrs.

lve) were Ireadjusted properly.

l l

adjusted.

l l

9-02, 07 &

ICable for 23-MOV-17 was rerouted.

1791014 150 hrs.

I I

I e

i I

I I

I e

on HPCI lConnt.ction was tightened.

1791013 12 hrs.

cature I

i l

l I

I 4

I I

I l

4 4

9 i

h 1

8' i

9

6 2

3 4

(

=

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICI G

7 e

~

LER/

EVENT q

e M

==

79-97 1791030 IEDG lDuring normal operation while perform-lHigh resi m

I l

iing ST-9D, EDG "C" would not parallel lon relay E

'G l

l lwith EDG "A".

l 79-100 1791108 lHPCI lDuring normal operation, in order to ILeak in hi m

l l

l complete maintenance, the HPCI system l control vi y

l I

lwas intentionally made inoperable.

lgasket.

I I

==

e 79-103 1791205 lRHR, 1 '.HR pipe hanger H10-539 was determined IBulletin /

T l

l l inoperable.

I14 effort.

]

79-105 791114 [EDG lDuring normal op ration, EDG "C" was Bad bearir l

l l declared inoperable due *o a noisy I

I I

Ilube oil recire pump.

l

]

l l

l i

N 79-108 1791206 lRCIC lDuring normal operation, the RCIC lCould not I

l lsystem was declared inoperable to Idetermine l

I linspect turbine bearings due to linitially.

1 l

loperator smelling smoke.

lexcessive l

l l

ltemperatur l

l l

lto inspect d

l l

l lbe sure.

I l

l l

M 79-110 1791214 lHPCI lDuring normal ci. ration, HPCI steam lExtensive D

l l

Isupply inhard isolation (23-MOV-15)

Ishooting c

.J l

i Iclosed as a result of a spurious ltion of tb I

l lisolation signal.

Icontainmer j

i l

I isystem ase I

l l

I23-MOV-15

~7 I

I I

land no cau 6E I

I I

lspurious s I

I I

Ifound nor 1

I i

i Idition be 1

I I

I O

.D o

M 7

o

-nii M

o 4 -w O

==ti m

_=__:....

I

, page 14 WSEE REPORT DATE EQUIP-RETURNED MENT TO DOhH

$E CORRECTIVE ACTION SERVICE TIME O

tance contactslContacts on relay ESR-400 were cleaned. 1791030 19 hrs.

BR-400.

I l

l e

I I

draulic l Gasket for hydraulic control valve 1791108 14 hrs.

d>

Ive seat lseat drain was replaced.

I l

i I

I I

e 0-02, 07, l Modification to H10-539 was completed.

1791206 124 hrs.

I l

i I

I I

e g in motor.

I"C" EDG Recirc lube oil pump motor 1791114 112 hrs, lwas replaced.

I l

l l

l e

I i

I psitively lWelding in the area was finally 1791209 148 hrs.

bause Idetermined as the cause.

l l

4D Suspected I

l l

pearing I

l l

't. Decided l

l l

9 bearing to l

l l

l 1

I i

i i

e trouble-lNone 1791214 IN/A f the por-l l

l primary i

l l

e isolation 1

1 I

ciated with l

l l

as conducted,I l

l 4

e for the i

l l

ignal could bel l

l pould the con-I l

I e

Buplicated.

I l

l I

I I

e Y

S O

3 O

l

f)

(

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICE o

LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAU 1

79-1131791221 l CORE IDuring normal operation, while con-lThe motor j

l l SPRAY l ducting ST-3D isolation valve 14-MOV-lassociated 1

1 IllB would not reopen following closure, llimitorque l

i l

lworked loo i

I I

Ishaft.

1 I

I I

79-0561790926 IHPCI IDeficiencies in the design of cable IHPCI & ADS l

l lseparation between ADS & HPCI.

This lin same tr, l

l Icould affect the control of the in-l l

l lboard isolation valve for HPCI system l

l l

l steam supply (23-MOV-15).

1 1

I I

I i

l l

l

79-0571790927 lRHR/

lDuring normal operation, 2 RHR pipe

! Pipe stres:

l l CORE lsupports (H10-533 and PFSK-503) and 1 lby architei l

ISPRAY Icore spray (H14-46) were found to be INRC letter l

I linoperable.

Idated 8/14, I

I l

l

ADDITIONS

/

1 9

s l

b

)

1

Oi 7, page 15 3

DATE EQUIP-RETURNED MENT TO DOWN 3E CORRECTIVE ACTION SERVICE TIME

> inion gear IMotor pinion gear was replaced.

1791222 113 hrs.

with MOV-llB l l

1

(%

operator had i l

I la from its l

l l

}

l l

l

(%

1 I

I cible in lIn order to preclude spurious closure 1790926 lN/A ty.

lof 23-MOV-15, the valve motor has been l

l ideenergized (locked open). The out-1 I

lside isolation valve (23-MOV-16) was I

l Ichecked daily as required by I

l ITech. Spec. Appendix A, Par 3.7.D.

l I

g luntil rerouting of cables.

I I

I l

I i reanalysis IModifications done within seven (7)

IN/A INone

t-engineer Iday time frame.

1 I

I I

I i%

'79 I

I i

1 I

I t %

1%

i is i I

Ir Os!

a l) Dr I

u!

u U

'U Y

e ei t

v y

y_

1b

(

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICI Qi LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAL (3

80-04 1800107 l CORE IDuring surveillance testing, one of the lInstrumeni 1

ISPRAY

[four core spray injection permissisive l

g.

l l

lswitches 02-3-PS-52A was found I

l l

lincorrectly set.

I I

I es 80-06 1800108 l CORE lDuring a review of work requests, it ITorque lir l

ISPRAY twas noted that core spray injection limproper13 l

l l valve "A" had not operated properly on land excess C3 I

l l December 21, 1979 (14-MOV-12A) while lential pre l

l lundergoing surveillance testing.

Ivalve.

I I

80-07 1800109 lRHR lDuring normal operation, "B" RHR loop lH10-28 hac l

l lwas declared inoperable while hanger itest requi l

I (H10-28 was inoperable.

l Bulletin 1 th 80-08 1800109 iCORE lDuring normal operation, while doing IImproper t l

ISPRAY lsurveillance testing 3D, "B" core spray ladjustment i

l lloop injection valve (14-MOV-12B) l I

l ifailed.

I I

I 80-12 1800111 lEDG lDuring ST-9B, EDO "A" tripped on low l Partial fa l

i llube oil prescure.

lengine imn l

I I

Iresulting 4b l

l l

loil and sl I

l I

l sure build I

l l

lengine sta i

l l

l 80-15 1800123 ILPCI lDuring normal operation, LPCI l Failure of I

l lindependent power supply "A" inverter Icapacitors l

l ltripped.

I i

l l

I 80-18 1800201 l CORE IDuring normal operation, core spray l Receipt of l

l SPRAY l pipe break detector was outside ISpecificat I

l l'rechnical Specification limits in lafter rego I

l l Table 3.2-2.

Imentation q,

I i

i I

80-24 1800213 lHPCI IDuring normal operation, HPCI steam l Defective I

l lisolation valve (23-MOV-15) closed iconnectior I

i las a result of a spurious signal.

I l

l l

l e

e

'ap I

C)

\\

t

,s I

L-

, page 16 MSEE REPORT DATE EQUIP-RETURNED MENT TO DOWN gE CORRECTIVE ACTION SERVICE TIME drift.

ICorrective action recalibration 1800107 11/2 hr.

limmediately.

l l

1 1

I I

I st switches lAdjust torque and limit switches.

1791221 124 hrs.

>cdjust;d ISurveillance testing increased to I

l

,Ava dif fer-lonce every two weeks to monitor l

I a

ecure ceross Ivalve performance.

I I

I l

l I

e i failed pull l Hanger H10-28 was repaired.

1800109 132 hrs.

Red for l

l bO2.

I l

l 3

I I

I srque switch IReadjust torque switch.

1800109 12 1/2 I

I thrs.

dP l

l l

l I

I I

i 1

e ilura of l Heater was replaced.

1801113 148 hrs.

rsion heater i l

i n cold lube l

l

[

e sw oil pres-l l

l Ep during i

l i

Jt.

I I

I e

i I

I filter IReplaced two failed capacitors.

1800124 19 hrs.

I I

I e

1 I

I I

Tzchnical lRecalibrated detector to new Technical 1800201 14 hrs, gp ion chnnge ISpecification value.

l l

ired imple-I l

I fcts.

I I

I e

i I

I El;ctrical IConnector was reconnected (23-TE-92A).

1800214 120 hrs.

1 l

l e

I I

I l

I i

?

5 l

i

?

d

[ -4

(

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC1 of LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAI 80-27 1800322 lHPCI lDuring normal operation, the HPCI l Bulletin 1 1

I isystem was degraded to allow for pipe leffort.

l l

lhanger repair.

I i

l 80-29 1800325 lHPCI IDuring IFP-75, 23-LS-74A was found set IDrift I

I Ito a less conservative value than l

I l

l allowed. This switch initiates l

l l

IHPCI suction transfer to the torus l

i i

lon condensate storage tank low level.

I I

I 80-34 1800410 lHPCI lDuring surveillance test, HPCI minimum ICocked brt l

l Iflow valve failed to close.

IDC motor c I

I I

I 80-35 1800415 l R'IR lDuring normal operation, primary lOpen torgt I

I lcontainment isolation valve was made llimit swit l

l linoperable for preventive maintenance l

I l

lof valve operator.

I l

l l

80-38 1800418 lRHR lDuring normal operation, valve.0-MOV-ISeat and c I

i 157 was found incapable of fully closing.I I

I I

i 80-40 1800422 lLPCI IDuring normal operation, the "A"

IGate timir I

l lLPCI independent power supply inverter lfailures.

1 I

ltripped.

l 80-47 800501 IRCIC lDuring normal operation while surveil-l Broken wir l

l llance testing to satisfy T.S.

l I

I ITable 4.2.2, RCIC high l

l l

lambient temperature switch l

I I

ll3-TE-89B failed to operate.

I 80-56 1800510 IEDG IDuring normal shutdown and ST following High resis i

l lpreventive maintenance, EDG "C" tripped lvoltage re I

I lon high circulating current.

Idroop swit I

I I

80-62 1800717 lRHR lDuring normal shutdown, testing RHR lOrifice in i

l lservice water pumps A and C flow was lline was t l

I lless than required by Technical I

l l

l Specification 4.5.B.l.

I I

i i

O l

O

~C i

l o

v Enr20sure 1, page 17 DATE EQUIP-(

RETURNED MENT TO DOWN 5E CORRECTIVE ACTION SERVICE TIME f-02,14 l Pipe hanger was repaired.

1800322 14 hrs.

I I

l 1

1 I

l l Remove, clean and calibrate 1800325 11 hr.

dP l23-LE-74A.

Surveillance was increased l

l lfrom once each month to once each week.-l l

l l

i I

I I

l ph hold r on IMotor was replaced.

1800410 18 hrs.

dP

$1va.

l l

l 1

I gbyp;ss I Adjusted limit switches.

1800415 18 hrs.

O sh l

l l

l i

I I

l I

I Acc wrar.

loverhauled valve and refurbished seat 1800610 IN/A land disc.

IRefueling i

dP f

I lOutage.

I I

I hccrd IReplaced gate timing card, filter cap-1800423 15 hrs.

lacitors and internal power supply.

I l

i I

l I

I I

p.

lRepaired broken wire.

1800501 110 hrs.

I I

I knca l Replaced switch.

I800610 lN/A yulator i

l l

ph contacts.

l l

l I

i I

ldischtrge IOrifice was removed.

1800717 13 hrs.

oo small.

1 I

I e

l l

i l

I I

I

}

l I

I

~

O s'

i

,1

O l

f O

I I. K. 3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LICI O

LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CAL g

80-66 1800805 l CORE lDuring instrument surveillance pro-l Drift.

i ISPRAY lcedure (ISP-8), the core spray sparger l

g l

l lbreak detection differential pressure i

l I

ltransmitter (14-PPIS-43A & 43B) was I

l l

Iset out of calibration and beyond l

g I

I IT.S. limits.

I I

I l

I 80-67 1800805 lHPCI/

lDuring ISP-12, HPCI and RCIC low IDrift.

l lRCIC l Nessure switches 23-PS-68A and 13-S-I l

l 1878 were found set higher than I

i i

lallowed by Technical Specification l

g l

l ITable 3.2-2.

I I

I 80-69 1800807 lADC lDuring ST-22A, ADS timer was set lower l Drift.

O I

I Ithan allcwed by Technical Specifi-I l

l Ication Table 3.2-2.

I 80-71 1800810 lRCIC lDuring plant startup, RCIC turbine l Failed amp i

l Ispeed would not control in manual.

l 80-72 800812 LPCI During plant startup, "B" LPCI inverter lElectronic l

l ltripped. Trips also took place on Ifailure du l

l 18/22/80, 9/5/80 and 9/6/80.

Icontrol bo e,

I I

I i

80-75 1800913 lLPCI lDuring normal operation, "B" LPCI l Failure of g

I i

-l inverter tripped.

1A -

2 I

I I

80-79 1801008 IRCIC IDuring normal operation, RCIC system l Normal wea g

l l

Iwas made incperable to allow repair of I

l l

lsystem drain valve steam leaks.

I I

l I

80-80 l801011 lRHR lDuring normal operation, while con-l Motor oper I

l lducting ST, the primary containment lwas diseng I

I lisolation valve (10-MOV-57) from RHR lscaffold i g

i l

lto radwaste would not close when i

i l

frequired to be operable by TS 3.7.D.

1 I

I I

O O

O e

i r0 1

1' 0

O O, page 18 SEE REPORT O

DATE EQUIP-RETURNED MENT TO DOWN E

CORRECTIVE ACTION SERVICE TIME O

IInstruments were calibrated and 1800805 11/2 hr.

Ireturned to service. Surveillance l

l 4D lfrequency was increased.

l I

I I

I i

i 1

9 I

I I

l l

l lInstruments were calibrated.

1800805 11/2 hr.

gb I

I I

4 I

I I

I ITimer was adjusted.

1800808 13 hrs, e

l l

1 1

I I

I e

ifier.

IAmplifier was replaced.

1800810 111 hrs.

I l

i I

I I

4 control ICauses of trips were repaired and the 1800812 lN/A 2 to one lcentral control board which created l

l rd.

lproblem was finally identified and l

l t

lcorrected.

l l

1 logic card ILogic card was replaced.

1800917 196 hrs.

g i

i i

i I

I l Replaced valve body to bonnet gaskets.

1801008 124 hrs.

g i

I I

l I

t itor clutch IRemoval of scaffolding in the area 1801011 11 br.

,8 ged due to irestored the valve to operable status.

I l

stallation.

l l

l 4

8, I

l l

I I

in 3..

(

i i

\\

II.K.3.17 REPORT ON OUTAGES OF EMERGENCY CORE-COOLING SYSTEMS LIC l

l LER/

EVENT OR NO.

DATE SYSTEM DESCRIPTION CA

80-28 1800324 lRHR lDuring normal operation, "B" loop of II&E Bulle l

l ltorus cooling was declared inoperable I

l I

lwhen required by T.S. 3.5.B.

The base l

l l

lplate for hanger H10-49A failed the i

I I

Iflexibility requirements of I&E l

l l

IBulletin 79-02.

I l

l l

l

80-35 1800415 lRHR lDuring normal operations, personnel l Bypass li i

l lnoted that the RHR system discharge Inot set p l

l l valve (10-MOV-67) to Radwaste would I

i i

Inot open. The valve was closed as re-l g

l l

Iquired by T.S.3.7.D.2.

The other i

l l

l primary containment isolation valve l

l l

l(10-MOV-57) in the same line was fully I

I I

loperable.

I I

I

80-85 1801208 lHPCI lDuring normal operation, while con-lMechanica 3

l I

lducting S.T. required by TS.4.5.C. the lthe torqu l

l loutside isolation valve motor failed, lassembly.

I I

IThe inside I.V. was closed to satisfy l

I I

IT.S.3.7.D. and other systems were I

l i

lverified operable as required by I

I I

IT.S.3.5 C.9.

I I

I

80-2151801110 lEPD lDuring normal operation, while per-I Low oil t:

l l

Iforming surveillance testing EDG l

l l

I"B&D" tripped on low oil pressure.

I I

I IThis would not occur on ECCS start.

I l

l ITrip is bypassed on ECCS start.

I I

I

80-93 1800507 IRHR lDuring shutdown, RHR shutdown cooling IValve mote l

l lsuction cooling isolation valve would lburned up=

l I

lnot open.

Redundant system was l

1 I

lavailable.

I

ADDITIONS 6

O

,t 4%a o

L S

'l i

ENSEE REPORT, page 19 DATE EQUIP-RETURNED MENT TO DOWN USE CORRECTIVE ACTION SERVICE TIME tin 79-02.

I A temporary repair restored the system 1800325 124 hts.

Ito operable status on the following i

i Iday. Permanent repairs were completed l

I lin 15 days.

1 I

I I

I nit twitch IPeformed P.M. on operator which 1800415 18 hrs.

operly.

lincluded adjustment of limit switches.

l l

l 1

I I

I l

i I

I I

I failure of lThe valve motor was repaired and 1801211 14 days

> twitch ltorque switch assembly parts l

I Ireplaced.

I i

l l

l

)

l I

I I

l I

I i

p.

IRaise thermor:at setting.

1801110 11 1/2 I

l ihrs.

I I

l i

I I

r operator iMotor replaced.

1800508 124 hrs.

1 I

I I

I i

~

1 V

e Y

=

M r:

5 t

s

ML20083P317

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