ML20128K597

Monthly Operating Repts for Jan 1993 for Quad Cities Nuclear Station,Units 1 & 2

ML20128K597
Person / Time
Site:	Quad Cities
Issue date:	01/31/1993
From:	Michael Benson, Walsh R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RJW-93-03, RJW-93-3, NUDOCS 9302180221
Download: ML20128K597 (32)

Text

. Commonwealth Edison l l

, ouad Cates Nuclear Power Staton 22710 206 Avenue North Cordova, Illinois 61242-9740 Telephone 309/654-2241 RJH-93-03 february 8, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 2055S

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 l Monthly Performance Report MC_D01kRLEQL__50-21 Land _50-115 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of January 1993.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION h 4*

Robert J. Halsh

'Y Tech Staff Supervisor RJH/HB/dak 6

Enclosure cc: A. B. Davis, Regional Administrator T. Taylor, Ser. lor. Resident Inspector 180103 f

{M23E$i S$h4 ((i

QUAD-CITIES NUCLEAR POWER ST' '9N UNITS 1 AND 2 HONTHLY PERFORRANCE REPORT January 1993 s

COMMONHEALTH EDISON COMPANY AND IOHA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TS14

TABLE OF CONTENTS I. Introduction I!. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary TS 14

I. IRIR0DEIl0N ,

Quad-Cities Nuclear Power Station is composed of two Boiling Hater l Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station-is jointly owned by Commonwealth Edison <

Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Sugply Systems are General Electric Company Boiling Water Reactors, The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971-, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for unit Two.

This report was compiled by Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

TS 14

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1 II. SURMARY OF Of.ERATINCt_EXPIRIINCE A. UniL0Ae

! Quad Cities Unit One ended its refuel outage it. December and began the nonth of January, 1993 at full power. The unit remained on line for i the entire month and performed numerous load drops for the Chicago load j Dispatch (CLD). None of these load drops, however, caused the average daily unit power level to drop below 80% of full power. i

{ B. Unit Two

! Quad Cities Unit Two was transferring reactor protection system (RPS) 1 4

power, at 10:08 on January 7, 1993, when an auto SCRAM was received. i License event report (LER) number 265-93-001 explains that a faulty DC solenoid caused a main steam isolation valve (MSIV) to close suddenly.

The resulting brief pressure trensient caused the unit to SCRAM on high

flux.

l The unit was made critical and synchronized to the grid at 08:39 on January 13, 1993.

A second reactor SCRAM occurred, at 13:40 on January 29, 1993, from a unit 2 reactor high pressure signal. LER number 265-93-005 is currently being written to investigate the cause of this signal. It is 4 suspected that maintenance work near the pressure instruments may have l Inadvertently caused an erroneous signal.

l The unit wcs made critical and synchronized to the grid at 22:39 on January 31, 1993.

I i

'l TS14

III. ELARLOR130CEDURLCHARGESJESIL_EXEERItiERIL AND SAFELYJELATED MAIRII_ NANCE A. Amendmeats_to_Eatility Elcenis_or_lerhnicaLSac11fic.aiLoni There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B. Eacility or Proredure Chanaes Reauiring NRC ADoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Esp.ttJmeati_BeRulring NRC ApproyAl There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Cor r e c t l y.e Ma i n t enance_of_Sa f e t y Re l a.teLEqu i ome n t The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Hork Request Numbers, licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

TS 14

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l UNIT 1 MAINTENANCE

SUMMARY

WORK. REQUEST SYSTEM WORK REQUESTED WORK PERFORMED <

002252 7300 REPAIR ACB ELECTRIC 480 VAC FOUND THE "Y" RELAY WOULD NOT BREAKER. ENERGIZE. THE BREAKER CONTACTS 2 WERE CLEANED AND A NEW CUTOFF SWITCH WAS INSTALLED.

003003 220 REPAIR PENCIL SIZE LEAK IN DISASSEMBLED VALVE AND REPLACED U1 B FEED WATER CHECK VALVE. THE "O" RING.

Q03041- 2500 U1 ACAD TO STANDBY GAS INSTALLED NEW SPRING IN TREATMENT ISOLATION VALVE 1- OPERATOR. LLRT PASSED.

2599-5B FAILED LLRT. REPAIR. ,

003047 2300 REPAIR BAD PACKING LEAK ON REPACKED VALVE WITH CHESTERTON U1 HPCI STEAM SUPPLY TEST PACKING.

4 TAP VALVE 1-2301 16.

I 003166 7800 REWORK BUTT SPLICE ON U1 MCC INSTALLED AN IN LINE SPLICE 18/19-5 CUBICLE El RECIRC BETWEEN THE STARTER AND CONTROL l

PUMP SUCTION VALVE 202-4B. TRANSFORMER. .

Q03200 5400 REPAIR SEVERE AIR LEAK ON FOUND THE ASCO SOLENOID BLOWING 1 SJAE SUCTION VALVE SG BY. ThoTALLED NEW ASCO VALVE I '5401A. AND VERIFIED PROPER OPERATION

, WITH NO LEAKS.

l 003268 1600 REPAIR / REPLACE AND ADJUST REPLACED BOTH SWITCHES.

i BROKEN LIMIT SWITCHES ON DW

, TO TORUS. RING HEADER VACUUM

, BREAKER AO 1-1601-32A. '-

t-Q03284 7800 INVESTIGATE / REPAIR MCC FOUND MOTOR BARS DELAMINATED AND  !

18/19-5 CUBICLE A4, 1A SEPARATED. REPLACED MOTOR WITH i REACTOR WATER MANIFOLD A NEW ONE.  !

CROSSTIE VALVE.

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. . . . - . . . . . ~ . . . - . - . . . . . . . - . . - . ~ . ~ . - . _ - . . . - _ - - - . . - . . - . . - - - . . . . . . . . - . . . - - . . , .

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003335 5700 INSTALL NEW SELECTOR SWITCH INSTALLED NEW SELECTOR SWITCH.

ON A RHR ROOM COOLER SELECTOR 1-5746A.

QO3554 6700 REPAIR BENT AND DISCOLORED REPLACED R'E i.AY.

CONTACT ARM ON RELAY 127-B131X3, BUS 13-1.

003621 760 REMOVE AND REINSTALL IRM #14 INSTALLED NEW DETECTOR.

DETECTOR.

QO3654 1000 REPLACE VALVE STEM AND REPLACED ENTIRE VALVE.

ACTUATOR ON RHR SERVICE WATER 1A HEAT EXCHANGER UPSTREAM STOP VALVE 1-1001-  ;

185A.

QO3790 750 REPLACE BAD PRE-REGULATOR ON REPLACED PRE-REGULATOR AND IRM 18 CHASSIS. ADJUSTED.

QO3934 1000- REPAIR 1A LPCI LOOP UPSTREAM FOUND STEN THREADS COMPACTED, STOP VALVE 1-1001-29A. THE BRASS SHAVINGS INSIDE STEM

. STEM APPEARS DAMAGED. PROTECTOR, AND STEM BENT. ,

REBUILT VALVE AND VERIFIED VALVE  !

WAS OPERATIONAL.

004106 300 REPAIR SCRAM INLET VALVE 1- ADJUSTED SEATING PRESSURE AND 0305-126. ROD DRIFTS PAST CHECKED SPRING TENSION. .

WITH NO MANUAL SIGNAL.

i 004113 901 REPLACE FUSE AND COlu ON U1 INSTALLED NEW RELAY.AND HAD ,

PCI RELAY 595-137. CONTROL ROOM VERIFY OPERATION. t 004124 901 DURING RHR LOGIC TESTING, FOUND. DEFECTIVE TIME DELAY UNIT.

i- THE DELAY UNIT TIMED OUT TOO REMOVED RELAY FROM PANEL AND

SLOWLY. INVESTIGATE PROBLEM REPLACED WITH A NEW RELAY.

, WITH HFA' RELAYS. l i

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, Q04225 30C REPAIR CRD CHARGING WATER FOUND EAR ON WEDGE WAS BROKEN VALVE 1-305-113-5015. OFF. REPLACED STEM AND DISC WAS UNABLE TO MANUALLY OPERATE REPACKED. INSTALLED VALVE AND ,

HCE 50-15 113 VALVE. RETORQUED BONNET.

Q79441 1000 REPAIR MISSING KEY WAY ON MISSING KEY WAS REPLACED WITH A DECLUTCH HANDLE ON 1B RHR NEW KEY.

LOOP MIN FLOW VALVE 1-1001- t 18B.

Q89607 2300 REPAIR HPCI TORUS SUCTION INSTA.LLED NEW OPERATOR.

VALVE 1-2301-56. APPEARS TO t BE BINDING.

Q90017 300 REPAIR OR REPLACE 1A SCRAM CHANGED OUT VALVE FOR NEW.

DISCHARGE VOLUME LT 1-0302-109K HIGH SIDE SHUTOFF VALVE 1-0301-103A. -l t

Q91119 5700 REPAIR SWITCH FOR'THE HPCI FOUND THE SWITCH ACTUATOR ROOM' COOLER. HANGING.UP. APPEARED SvLIETHING WAS WARPED-OR' BENT IN THE COVER '

CAUSING THE' SWITCH TO BIND.  !

REPLACED SWITCH AND BOX WITH I NEW.  :

Q96484 220 REPAIR LIMIT SWITCH ON 1B INSTALLED NEW LIMIT SWITCHES.  ;

RECIRC LOOP UPSTREAM SAMPLE i VALVE AO 1-0220-44.

i Q96599 5400 REPAIR SJAE SUCTION VALVE 1- INSTALLED NEW SOLENOID VALVE.

5401B (BLOWING AIR). STROKED VALVE AND VERIFIED  ;

, PROPER OPERATION WITH NO LEAKS. i 097682 201 REPAIR U1 SHROUD ACCESS HOLE VENDORS INSTALLED A NEW SHROUD .

COVER PLATES. ACCESS HOLE COVER.. i 098164 REPLACE RCIC STEAM LINE HIGH 1300 REPLACED SWITCH LIKE FOR LIKE.  !

FLOW SWITCH 1-1360-1A.

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002611 750 REPAIR IRM 16 CHASSIS, RAN I/V CURVE, TDR TRACES, ~"

SPIKING HIGH.. RESISTANCE TEST AND BCCK TEST.

CALIBRATED IRM 11, 12, 13, 14, 16, AND-18 CHASSIS. ADJUSTED  !

GAINS.

f Q02814 7800 REPAIR MCC 18/19-5 CUBICLE 'FOUND WIRE FROM RED LIGHT TO B1 REACTOR WATER RECIRC PUMP TERMINAL 4 OFF. REPLACED WIRE ,

SUCTION VALVE 1A. AND VERIFIED PROPER LIGHT INDICATION.

Q03162 2300 REPLACE MISSING U-BOLTS ON FOUND U-BOLT ON LEFT SIDE HPCI LINE 1-2304-l'4" HANGER. MISSING ALL' NUTS THAT SECURE IT TO'THE HANGER AND PIPE. -[

INSTALLED 4 NUTS'ON LEFT U-BOLT. '

003265 7800 REPLACE. BROKEN TERMINAL INSTALLED NEW TERMINAL BLOCK, BLOCKS ON MCC 18/19-5 LIFTED AND RELANDED WIRES, AND CUBICLE El RECIRC PUMP PUT CUBICLE BACK IN THE MCC.

SUCTION VALVE'202-4B.

i QO3269 202 REPAIR; HANDWHEEL ON U1 3 FOUND SET SCREW LOOSE ON THE

j. RECIRC' PUMP SUCTION VALVE 1- HANDWHEEL. THE SET SCREW WAS j 0202-4B. TIGHTENET .

003287 1000 REPAIR 1A.RHR TORUS SPRAY FOUND SCORE'ACROSS THE SEAT OF  !

). STOP VALVE 1-1001-37A. DISC AND BODY SEAT. MACHINED

FAILED LLRT. AND POLISHED THE DISC AND BODY

SEATS AND REASSEMBLED VALVE.

Q03288 220 REPAIR FEEDWATER HEADER "A" REMOVED AND INSPECTED TRIM. FW1 INBOARD-CHECK VALVE 1-0220- AND FW2 WERE GROUND AND 58A. FAILED LLRT. MACHINED. VALVE WAS

l REASSEMBLED.

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003324 220 REPAIR FEEDWATER HEADER "A" FOUND'_THE O-RING LAND INADEQUATE IST OUTBOARD CHECK VALVE 1- FOR O-RING SEATING. WELD '!

0220.-62A. REPAIRED AND MACHINED-THE VALVE BODY'AND REASSEMBLED VALVE.

( PASSED LLRT.

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1 m .

t 003397 */800 REPLACE MAIN CONTACTOR COIL FOUND CUBICLE E4 TO BE THE -j IN U1 A RPS MG SET MCC 18-2 CORRECT CUBICLE. FOUND INTERNAL l CUBICLE E3. COIL TO HAVE SEVERAL CRACKS IN r ITS CASING. VERIFIED. i OPERABILITY OF CONTACTOR. NO PROELEMS FOUND. REPLACED COIL WITH NEW.

Q03427 302 REPLACE SCRAM DISCHAPGE REPLACED TRANSMITTER AND SENSOR  !

VOLUME LEVEL TRAN6MITTER 1- BELLOWS ON LT 1-302-109D. ALSO 0302-109D. 'OUT OF REPLACED O-RING AND BACKUP O-TOLERANCE. RING ON BOTH SENSOR BELLOWS.

REPLACED BUTT SPLICES IN LB BOX WITH QUALIFIED SPLICES.

Q03565 2300 RESET COLD LOAD SE'T" RING OF LOOSFNED LOCK NUT AND SET COLD HANGER.2305-W-102. LOAD TO APPROXIMATELY 2900 LBS.

003566 8300 REPAIR MCC 1A CUBICLE Il FOUND BREAKER WITH BROKEN BREAKER. HANDLE. INSTALLED NEW BREAKER WITH NEW HARDWARE.

003611 202 REPACK U1 A RECIRC PUMP FOUND PACKING LEAKING AND STEM DISCHARGE VALVE 1-0202-5A. HAD GROOVES THE FULL LENG"'H OF THE STEM . RETORQUED PACKING GLANDS. AFTER TORQUING, SOME LEAKAGE WAS STILL PRESEh7.

Q03910 1400 REPAIR. I . .AKING FLANGE ON 1A FOUND NUTS AT 60 FT-LBS.

CORE SP..nY DISCHARGE HEADER TIGHTENED NUTS SLIGHTLY.

SAFETY.L.LVE 1-1402-28A. l QO3930 8300 REPLACE 250VDC BREAKER FOR MODIFIED EXISTING BREAKER MO-1-1301-25. M O U h"r I N G B R A C K E T A N D M O U N T E D N E W BREAKER. MOUNTED CLD BREAKER HANDLE. REPLACED BAD JUMPERS ON TERMINALS 1U, 1, 2, AND 6 WITH i NEW JUMPERS. ADJUSTED MOUNTING HARDWARE ON CUBICLE. DOOR TO MATCH UP WITH BREAKER HANDLE.

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Q03980 300 REPAIR SCRAM PILOT AIR INSTALLED REBUILT VALVES. NO SOLENOID 1-0305-117. LEAKS FOUND. ,

BLOWING AIR. }

003997 1000 REPAIR 1A CONTAINMENT SPRAY REPLACED WORN BONNET BOLTING.

LOOP DOWNSTREAM STOP VALVE REPACKED VALVE.

1-1001-26A. FAILED LLRT.

Q04034 8300 REPAIR CRACKED BREAKER REMOVED OLD. BREAKER AND HANDLE ON MCC 1A CUBICLE K2 INSTALLED A-NEW ONE. l FOR MO-1-2301-6. ,

004037 7800 REPAIR COIL IN MCC 18-1A REPLACED MOTOR STA.RTER. >

CUBICLE D2 MAIN STEAM LINE REPLACED LEFT CONTACTOR. COIL

']UTSIDE DRAIN VALVE. WITH NEW.  ;

Q04041 3000 REPAIR BENT HANGER BAR, MAIN CUT, THREADED, AND INSTALLED NEW STEAM 3001D-W-103. HANGER ROD. INSTALLED-NEW ,

BOLTS.

4 004056 30 REPAIR MK483 PENETRATION,. FOUND LEAK ON TOP-SIDE.  !

RHR SERVICE WATER VAULT. TIGHTENED LINK SEAL BOLTS AT LOCATION OF LEAK UNTIL LEAK WAS i i

STOPPED.

004057 30 REPAIR MK699 PENETRATION, FOUND LEAKS ON INSIDE'AND' RHR SERVICE WATER VAULT. OUTSIDE SEALS. TIGHTENED LINK i

SEAL BOLTS AT LOCATION OF LEAKS U!TI'IL LEAKS WERE STOPPED.

004058. 30 REPAIR MK470 PENETRATION, FOUND LEAKS'ON A FEW BOLTS.

RHR SERVICE WATER VAULT. TIGHTENED LINK SEAL BOLTS AT LOCATION OF LEAKf- UNTIL LEAKS I MERE STOPPED. I

! 004059 30 REPAIR MK507 PENETRATION, FOUND LEAKS ON .NSIDE AND

RHR SERVICE WATER VAULT. OUTSIDE SEALS. TIGHTENED LINK 1 SEAL BOLTS AT LOCATION OF LEAKS.

I OUTSIDE SEAL STILL 'AKS BUT.IS i ACCEPTABLE.

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004069 1000 RESET CURRENT COLD LOAD UNLOADED SPRING TO 5978 LBS.

SETTING ON U1 ISI. HANGER LOADED SPRING TO APPROXIMATELY 1012B-W-103, 1ST FLOOR 6883 LBS.

DRYWELL.

Q04077 2300 REPAIR HPCI PUMP DOWNSTREAM POLISHED STEM. LAPPED WEDG' AND TORUS SUCTION VALVE 1-2301- BODY SEATS. INSTALLED PACK 1IiG

35. AND CARBON SPACER. TORQUED PACKING TO 90 LBS. INSTALLED NEW STEM NUT.

004139 2500 A.DJUST FLOW CONTROLLER FI 1- CALIBRATED SQUARE ROOTER AND 2540-10A, ACAD DILUTION. FLOW INDICATOR. FOUND C1 AND C2 ON MAIN BOARD OF FC 1-2540-15A BAD. REPLACED WITH LIKE BOARD.

REPLACED CAPACITORS C1 AND C2 WITH SAFETY RELATED COMPONENTS.

REINSTALLED CONTROLLER.

Q04214- 901 REPAIR "A" RPS MANUAL SCRAM INSTALLED NEW CONTACT BLOCK AND PUSHBUTTON. STICKS. WIRED NEW BLOCK.

Q04321 2300 REPAIR U1'HPCI TESTABLE INSTALLED NEW VALVE, RECONNECTED CHECK VALVE 1-2301-7. BLOWS AIR LINES. CHECKED FOR PROPER BY. OPERATION. OK.

004339 1000 REPAIR. OUTBOARD BOOSTFR. PUMP FOUND WATER IN THE BEARING OIL SEAL ON 1D RHRSW PUMP. AND PARTS OF BEARING IN THE OIL.

DRAINED OIL. REMOVED BEARING AND OIL SEAL. REBUILT PUMP AND REINSTALLED.

Q04371 7800 REPAIR TERMINAL #1.ON MCC CUT OLD LUG OFF TERMINAL #1 AND 18.1A. RELOGGED EACH LEAD WITH ITS OWN LUG AND RELANDED ON TERMINAL #1.

004372 220 REPAIR 1B OISCHARGE VACUUM ALL PARTS WERE INSPECTED AND BREAKER ELECTROMATIC SAFETY CLEANED.

VALVE 1-0220-81B.

a 004397 7800 REPAIR MCC 18-1A COMPAR21ENT INSTALLED NEW MALE TERMINAL E4. BLOCKS. DOCUMENTED ALL LEAD LIFTS AND LANDS. INSTALLED NEW FEMALE TERMINAL BLOCKS.

DOCUMENTED ALL LEAD LIFTS AND LANDS.

Q04431 203 REPAIR OUTBOARD MSIV DC FOUND SEALTITE SMASHED.

SOLENOID SEALTITE. REPLACED SEALTITES AND TIGHTENED ALL CONNECTIONS.

7200 REPLACE DEFECTIVE RMS-9 REPLACED RMS-9 WITH NEW.

Q04432 PROGRAMMER ON BREAKER 5018 BUS 19 CUBICLE 6D.

2300 REBRUSH HPCI MOTOR SPEED INSTALLED NEW BRUSHES.

Q04440 CHANGER MOTOR.

2300 .REBRUSH HPCI TURBINE MOTOR INSTALLED NEW BRUSHES.

004441 GEAR UNIT.

004463 300 REPAIR CONTROL ROD DRIVE E-7 TORQUED ALL ACCESSIBLE BOLTS TO FOUND LEAKING DURING HYDRO. 375 FT-LBS. DRIPPING STILL PRESENT.

203 REPAIR LEAK IN 1A MAIN STEAM REPLACED GASKETS ON PILOT FLANGE Q04464 LINE TARGET ROCK VALVE. AND RETORQUED TO 710 FT-LBS.

1 263 REPAIR REACTOR LT 1-0263-58 DISASSEMBLED VALVE, CLEANED, AND 004469 HI SIDE EF CHECK VALVE 1- INSPEC'"ED INTERNALS. l REASSEMBLED VALVE AND INSTALLED 'l 0263-2-13B.

BACK IN SYSTEM.

243 REPAIR LT 1-0646-A AND PT 1- DISASSEMBLED VALVE, CLEANED, AND>

004470 0647-A HI SIDE EF CHECK INSPECTED INTERNALS.

VALVE 1-0263-2-19A. REASSEMBLED VALVE AND INSTALLED BACK IN SYSTEM.

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l 7800 REPAIR MCC 19-1 CUBICLE H2 REMOVED CUBICLE, REMOVED OLD 004478 BREAKER. REPLACED WITH NEW 1 REACTOR WATER CLEANUP PUMP  !

IB BREAKER. BREAKER WILL BREAKER. PUT CUBICLE BACK IN NOT GO TO OFF. MCC 19-1.

1000 REPAIR RHRSW FROM 1 RHR HEAT FOUND PIECE OF METAL IN VALVE j 004479 BODY BELOW DISC GUIDE. SEAT AND EXCHANGER FLOW CONTROL VALVE l

1-1001-SA. VALVE WILL NOT- DISC WERE SCRATCHED. REPLACED STROKE. LIQUIDTITE CONNECTOR ON SEALTITE AND RETURNED SEALTITE BACK TO VALVE. REPACKED AND REASSEMBLED VALVE.

207 REPLACE MISSING BOLT FOR INSTALLED NEW BOLT AND NUTS ON Q04494 THE SPRING CAN PIPE SUPPORT.

REACTOR VESSEL DRAIN TO REACTOR WATER CLEANUP PIPING SUPPORT 1-207-2.

4700 REPAIR MISSING THREADED RODS MANUFACTURED AND INSTALLED NEW 004496- HANGER RODS.

FORM MSIV ACCUMULATOR PIPE HANGERS..

220 REPAIR / REPLACE CHECK VALVE FOUND VALVE EXTERIOR CORRODED Q04499 AND DISC RUBBER VERY HARD.

V-1, 2A MSIV AIR SUPPLY.

BRAZED IN NEW CHECK VALVE.

[ REPLACED THE MANIFOLD'AND

[ Q04500 261 REPAIR D/P INDICATOR SWITCH

' FOR MAIN STEAM LINE_ FLOW, 1-- CALIBRATED THE. INDICATOR.

0261-2H.

7800 ELIMINATE WIRES AND LUG ON CORRECTED WIRING.

1 004513 l MCC 18-1A COMPARTMENT F4 INTERNAL WIRING.

7800 REdIRE MCC 18-1A CUBICLE A3 RELUGGED TWO WIRES AND RELANDED

j. Q04518 ON TERMINAL ONE.

MAIN STEAM LINE "A" DRAIN VALVE.

. ...m . _ - . - - . ._ .m . . _ _ _ . _ . _ _ . _ _ _ _ . _ . . . . _ _ . _ ._ _ _. .. _ _ _ . _ _. _ _ _ . _ _ _ _ . . . _. _ _ . _ . . . . __

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n R I Q04542 2300 ADJUST U1 HPCI MGU HIGH ADJUSTED LIMIT SWITCH AND g SPEED STOP LIMIT SWITCHES TIGHTENED ALL HARDWARE. l' l

1.8A AND 18C.

Q04543 '800 REPAIR BROKEN CONTROL SWITCH INSTALLED NEW CIRCUIT BREAKER.

ON MCC 19-1 CUBICLE D5 l BREAKER.

l' Q04545 1600 REPAIR DRYWELL TO TORUS RING FOUND TWO BOLTS MISSING FROM HEADER VACUUM BREAKER HOFFMAN BOX. REPLACED TWO BOLTS SOLENOID AO 1-1601-32A. AND TORQUED TO SPECS.

Q04604 901 REPAIR BROKEN INSULATING FOUND BROKEN TERMINAL BLOCK AA ,

DIVIDERS ON TERMINAL BOARD AT POINTS 30, 31, 32, 86, 9, 14, IN CONTROL ROOM PANEL 901-4. 63, AND 35. REPLACED ALL BROKEN TERMINAL BLOCKS. VERIFIED CONTINUITY.

Q04620 7800 REPAIR MCC 19-1 CUBICLE H1 FOUND AUXILIARY CONTACTS HANGING ROOM COOLER BREAKER UP. CLEANED AND LUBED AUX -

CONTACTS.- CONTACT SIDING ARMS.

Q04642 300 REPAIR NITROGEN CYLINDER REMOVED ACCUMULATOR. REMOVED ACCUMULATOR 1-0305-128. OLD O-RINGS AND CLEANED ALL SURFACES. INSTALLED NEW LUBRICATED O-RINGS ON NEW ACCUMULATOR. INSTALLED NEW ACCUMULATOR.

Q04661 2300 REPAIR / REPLACE HPCI GLAND CLEANED DISC, STEM, VALVE BODY, ,

SEAL CONDENSER PUMP CHECK BONNET, AND GASKET MATERIAL.

VALVE 1-2301-76. VERIFIED CHECK VALVE OPERATIONAL.

Q04669 2300 REPAIR OIL LEA 5 ON FLEX LINE FOUND COUPLING SIDE OF HOSE ON HPCI. PUMP 1-2302. CRACKED. REMOVED, CLEAMED, AND e REPLACED WITH NEW HOSE.

a 1

2300 REPAIR HPCI PROCESS FLOW NO PROBLEM FOUND.

004670 INDICATING CONTROLLER 1-2340-1.

ADJUST RELAY IN CUBICLE CHECKED PICKUP VOLTAGES. NO Q04687 8300 250VDC BUS 1A HPCI TURBINE ADJUSTMENT MADE.

GLAND SEAL CONDENSER. WOULD NOT PICKUP.

INVESTIGATE / REPAIR 1A CAM NO PROBLEM FOUND. SUSPECT THE Q04741 2400 TORU" OXYGEN L#.MPLE LOCAL PANEL WAS LEFT-IN SPAN RECO.. )ER . MODE AFTER COMPLETION OF QCCP 1200-4 ON 12/11/92 BY CHEMISTRY.

NO PROBLEM FOUND. REMOVED, Q04746 300 TROUBLESHOOT AND REPAIR SCRAM SOLENOID 118-VALVE. REBUILT, AND REINSTALLED VALVES ANYWAY.

1000 REPAIR INDICATION ON 1B RHR REMOVED CUBICLE A3 AND CLEANED Q04978 STAB AND STAB ASSEMBLY. l PUMP TORUS SUCTION VALVE.

2300 FIX BROKEN PLUG CONNECTION FOUND BROKEN PLUG ON SEALTITE 078596 END. REPLACED WITH hBf STYLE AT LOCAL. JUNCTION BOX ON WEST END OF HPCI TURBINE. PLUG.

7800 REPAIR MCC 19-1 CUBICLE C2 REPLACED BOTH STARTER-COILS.WITH Q78817 I U1 RBCCW' HEADER ISOLATION E.Q. STARTER COILS.

VALVE MOTOR STARTER.

263 INVESTIGATE / REPAIR GROSS CALIBRATED MICTER TRIP UNIT AND Q79531 REINSTALLED IE PANEL.

FAILURE LIGHT AND ANALOG ALARM ON ATWS MASTER TRIP UNIT.

2300 DISASSEMBLE AND-INSPECT U1 DISASSEMBLED, REMACHINED VARIOUS

, - QS2846- PARTS OF THE VALVE, REBUILT I HPCI TUR.BINE INLET VALVE 1-2301-3. VALVE, AND REINSTALLED VALVE.

L--.

_ _ _ .. .._ .. _ _ . . _ . . . .. . . _ . . . __-._.__.___._.-._-.._.._...._m._.m _ . _ . , _ _ . . . < . . . _ _ . . . . .

i Q93436 8300 CLEAN CORROSION FORM BUS BAR CLEANED AND TAPED BUS BARS.

CONNFCTION INSIDE 250VDC BREAKER FOR HPCI TURBINE AUXILIARY OIL PUMP.

UNIT 2 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED 000662 5400 REPAIR IN LINE OILER LEAK ON CHANGED OUT OLD OILER FOR NEW '

SJAE SUCTION VALVE 2-5401B. AND REFILLED WITH OIL.

Q03513 300 INVESTIGATE DRIFTING SCRAM REPLACED AND CALIBRATED ""'E '

DISCHARGE VOLUME FLOW CIRCUIT BOARD. VERIFIt_ l CONTROL INDICATING LEVEL OPERATION. SUSPECT BAD RELAY.

SWITCHES 2-302-82L.

005110 1600 REPAIR SOLENOID ON 2-1601-56 REPLACED THE OLD SOLENOID WITH A '

VALVE. NEW ONE.

005112 203 DURING RPS BUS TRANSFER, THE REPLACED MANIFOLD ON VALVE 2A MSIV WENT CLOSED. JUNCTION BOX CHECKED VOLTAGE i INVESTIGATE SUSPECTED FAULTY OF ALL.THREE COILS. ALL DC SOLENOID. READINGS WERE IN RANGE. ,

i 005181 760 REPAIR IRM 11. INSTALLED NEW PREAMPLIFIER. l 4

a i

i i

.I IV. LLCENSEE. EVFNT REPORTS

{ The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications, i

EU Licensee Event Report Humber Dale Title of Orturience d

There were no Licensee Event Reports for Unit I for thit reporting period.

Uhll_2 Licensee Event ReLort Number Dale litle i occurence i

93-001 01/07/93 Rx SCRAM when MSIV went close during power transfer on RPr 93-002 01/13/93 HPCI MSL failure to run back to LSS93-003 01/14/93 Loss of light indication for HPCI controls93-004 01/15/93 Missed Tech Spec Surveillance for recombiner temperature 93-005 01/29/93 Rx SCRAM from high-Rx 78 14

. - . _ .. _ .. - . - . - . . .- . _ . . - . . . - _ . - . ~ . . .--

4 V. D6IA_IABULAILORS 4

The following data tabulations are presented in this report:

A. Operating Data Report

, i

8. Average Daily Unit Power Level l C. Unit Shutdowns and Power Reductions i

i i

i 4

1 j

)

i 1

N J

e TS t4 1

.i s

i APPENDIX C i OPERATING CATA REPORT ]

DOCKET NO $0-254 . . _ _ _ i

! UNIT One _

DATE febryatLB4_1993_._._

i COMPLETED BY tlaLLBanion l TELEPHONE L1091354.-2241 i

OPERATING STATUS j 0000 010193 i i 1. REPORTING PERIOD: 2400 013193 GROSS HOURS IN REPORTING PERI 00: 744

2. CURRENTLY AUTHORIZED POWER LEW L (HWt): 2511 HAX. DEPEND. CAPACITY: If9 f l DESIGN ELECTRICAL RATING (HWe-Net): 289 _

i i i 3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (HWe-Net): N/A }

l 4. kEASONS FOR RESTRICTION (IF ANY):

< THIS HON 7" YR TO DATE CUMULATIVE i

) 5. NUMDER OF HOURS REACTOR WAS CRITICAL ........... 744.0 744.0 1435DL2 l 1

! 6. REACTOR RESERVE SHUTDOWN HOURS ................... 0.0 0.0 3421.9

7. HOURS GENERATOR ON LINE ......................... ZRD._ _ Z.4LO-. 13.9.135d . l

8. UNIT RESERVE SHUIDOWN HOURS ..................... 0.0 0 0,_ 309 1

]

i (HWH).............

j 9. GROSS THERMAL ENERGY GENERATED 1816022 d 1BlfDZRd_ 291322.0.46 2 . I

10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... J9ZhB4a _12Z(iB4 0._ 9701172LD_

11. NET ELECTRICAL ENERGY GENERATED (HWH)............ _L67894.0 J67894.0 ._91143105 1

12. REACTOR SERVICE FACT 0R........................... 100 00 100JQ 78JB i

i 13. REACTOR AVAILABILITY FACT 0R...................... 100.00 100.00 80.55 I 14. UNIT SERVICC FACTOR ............................. ?0LDQ 100.DQ _ 76 @

f 15. UNIT AVAILABILITY FACTOR ....................... 100 01 100.00 74 23

16. UNIT CAPACITY FACTOR (Using HDC) ................ 92J6 99.26 65.19

17. UNIT CAPACITY FACTOR (Using Design HWe) ......... 96.74 96.74 63.54

$ 18. UNIT FORCED OUTAGE RATE ........................ 0.0Q 0.00 SJ2 L

i 19. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE. AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PER100. ESTIMATED DATE OF STARTUP:

, 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

)

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

, Ts 14 1.16-9 i

i

4 APPLNDIX C OPERATING DATA REPORT DOCKET ho 50-265 UN!T Iwg_ _

DATE f_C.hrkary_Eul221 --

COMPLETED BY MAG Denson TELEPHONE QQ2Lh53-2241 OPERATING STATUS 0000 010193

1. REPORTING PERIOD: _L400 01311L GROSS HOURS IN REPORTING PERIOD: .744

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511_ MAX. DEPEND. CAPACITY' 162 ._

DEStr' ELECTRICAL RATING (MWe-Net): 289

3. POWER LEVEL TO WHICH RESTRIC1ED (IF ANY) (MWe-Net): N/A 1

4. REASONS FOR RESTRICTION (IF ANY):

THIS HONTH YP, TO DATE CUMULAirt E

5. NUH8ER OF HOURS REACTOR VAS CRITICAL ............ .

579J9 529JQ 1191_5L55

6. REACTOR RESERVE SHUTDOWN H0;;RS . . . . . . . . . . . . . . . . . . 0.0

_.__ 0. 0 _ .

2985J0

7. HOURS GENERATOR ON LINE ......................... 544 5A $143.5Q 136185.95 I

8. UNIT RESERVE SHUfDOWN HOURS ..................... D.,_Q. . _. Q,L _702 2Q

9. GROSS THERMAL ENERGY SENERATED (MWH) . . . . . . . . . . . . . 330618LQQ 120110h0.0 E9296952L.ZQ

10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... 429389._Q2 J 19389 Qg .94454650.00.

11. NET ELECTRICAL. ENERGY GENERATED (HWH)............ 4101000Q 310168.00 3944091L30

12. REACTOR SERVICE FACT 0R........................... 77.85.. _ _22.,45 E2A

13. REACTOR AVAILABILITY FACT 0R...................... 77 05._ 77.86 78 9.]

14. UNIT SERVICE FACTOR ............................. 73.19 73.19 75,3.1

15. UNIT AVAILABILITY FACTOR ........................ 7.3J L 73.19- 75.70 in. UNIT CAPACITY FACTOR (Using HDC) . .............. 71 6L 71.69 64.32

17. UNIT CAPACITY FACTOR (Using Design MWe) .......... 69.8L 69.87 __

62 63

18. UNIT FORCED OUTAGE RATE ......................... 162RL ZLal 7.8S

19. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, Ato DURATION OF EACH):

20. IF SHUT 00WN A1 END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTf! CITY' COMMERCIAL OPERATION 1.16-9 TS 14

. APPENDIX B AVERAGE DAILY UNIT P0HER LEVEL DOCKET NO 50-1Ji4 UNIT One DATE EebfMaILL_1993 COMPLETED BY htLBenon

. TELEPHONE 110SL614_-2L41 i

MONTH lanuAr11923 i DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MHe-Net)

1. .184 17. 711

2. 784 __. 18. 784

3. __ l60 19. 784 j 4. 72L 20, 757 1

5. 746 21 . __,. . 752

6. 182. 22. 14L

7. 756 23. 709 j 8. 782 24. 7H7 4

9. 782 25, 755 f 10, 767 26. 781

11. 779 27. 774 i

2

12. 747 28. 727

13. 718 29. 781

14. 779_ 30. 783

- 15. 782 31. 783

16. 127 INSTRUCTIONS a

~

On this form, list the average daily unit power level.in MWe-Net for each day.

in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of.

the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level-line). In such cases, the average daily unit power output sheet should be footnoted to explain the

apparent anomaly. ,

Ts u 1.16-8 f

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Iwo DATE fabryary_S.- I 993 COMPLETED BY. hiait_Benion TELEPHONE (309) 654-2241 MONTH Jinyary 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (hne-Net)

1. 788 17, 761

2. 790 18, 783

3. 7a6 19. 671

4. 762 20. 63 9 5, 787 21. 752

6. 786 22. 795

7. 328 23. 796

8. -8 24. 793

9. ___ -8 25, 793

10. -8 26. 764 I

11. _B 27. 774

12. -8 28. 788 13, 201 ___ 29. 448

14. 729 30. -8

15. 794 31. -3

16. 794 INSTRUCTIONS On this form, list the average daily unit power level . in MWe-Net for each day.

In the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 1001 line (or the restricted power level line). In such cases,-the average-daily unit power output sheet should be footnoted to explain the apparent anomaly, re u 1.16-8 l

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VI. UM10VLREEORllRG_RECUIREMEltT.S The following items are included in this report based on prior commitments to the commission:

A. Main Steam Relief _Valle_0nentions ,

There were no Main Steam Relief Valve Operations for the reporting period.

B. Control Rod Drive Stum Timing Data for Units One and Tgo The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 PSIG.

TS14

. _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ _ _ . _ _ . . . . _ _ . _ _ .__________________J

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/93 TO Q;/31/93 AVERAGE TIME IN SECONDS AT % MAX. TIME INSERTED FROM FULLY HITHDRAHN FOR 90%

INSERTION DESCRIPTION NUMBER 5 1 20 50 90- Technical Specification 3.3.C.1 &

DATE OF RODS 0.375_]_Q,300 2.00 3.5 7 sec. 3.3.C.2 (Average Scram Insertion Time)

H-12 0.30 0.67 1.42 2.15 2.15 For Accumulator Replacement 01/28/93 1 l

! I TS 75 i

VII. PEEUELING_INE0RMAIION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) f rc,m D. E. O'Brien to C. Reed, et al., titled "Dresden. Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

l l

id th t

( TS14

, 4

QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: of Reload: 12 Cycle: 13

2. Scheduled date for next refueling shutdown: 3-14.94

3. Scheduleo sate for restart following refueling: _

6-13-94 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

NOT AS YET DETERMINED 5.

Scheduled date(s) for submitt'n! proposed licensing action and supporting information:

NOT AS YET DLTERMINED 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

NONE AT PRESENT TIME.

7. The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1557 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 3657

b. Planned increase in licensed storage: 0 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2009 APPROVED 14/0395t -l 00T 3 01969

[ __ __ _ _ _ _ _ - - - - - - - - -

Q.C.O.S.R.

Q7P 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: 02 Reload: 11 Cycle: 12

2. Scheduled date for next refueling shutdown: 03/06/93

3. Scheduled date for restart following refueling: 06/05/93

4. Will refueling or resumption of operation thereafter reoutre a Technical Specification change or other license amendment:

NO

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

NO SUBMITTALS REQUIRED.

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

NONE AT PRESENT TIME.

7. The number of fuel assemblies,

a. Number of assemblies in core: 7?4

b. Number of assemblies in spent fuel pool: 2439

8. The present licensed spent fuel pool storage capacity and the size'of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 3897

b. Planned increase in licensed storage:- 0

9. The projected date of the last refueling that can be discharged-to the spent fuel pool assuming the present licensed capacity: 2009 APPROVED ,

(final) 14/0395t DCT30M99 O.C.O.S.R.

.--_-----_-.--____w.m. _ _ _ _ _a____m_

VIII. GLOSSAR1 The following abbreviations which may have been used in the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute APRM - Average Power Range Monitor ATHS - Anticipated Transient Hithout Scram BHR - Boiling Hater Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations facility GSEP - Generating Stations Emergency Plan HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT - Integrated Primary Containment Leak Rate Test IRM - Intermediate Range Monitor ISI - Inservice Inspection LER - Licensee Event Report LLRT - Local Leak Rate Test LPCI - Low Pressure Coolant Injection Mode of RHRs LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio MFLCPR - Maximum Fraction limiting Critical Power Ratio MPC - Maximum Permissible Concentration MSIV - Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCH - Reactor Building Closed Cooling Hater System RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System RHM - Rod Horth Mirimizer SBG15 - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCH ~ Turbine Building Closed Cooling Hater System TIP - Traversing 1ncore Probe TSC - Technical Support Center TS te

-_------_--.__._____-_m.-_. .___.