ML20045G514

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Monthly Operating Repts for June 1993 for Quad-Cities Nuclear Station,Units 1 & 2
ML20045G514
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/30/1993
From: Michael Benson, Scott A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-93-02, AMS-93-2, NUDOCS 9307140065
Download: ML20045G514 (30)
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9 O Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654 2241 AMS-93-02 July 2, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washintiton, D.C.

20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 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 June 1993.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 4"

7y Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc: A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector 1 1 A } TECHoPrJ4RC310NTHLY.RP1 44 g. 9307140065 930630 3 iVU PDR ADOCK05000254hy! R 'i PDR f

=. t 4- ? 9 QUAD-CITIES NUCLEAR POWER STATION' UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JUNE 1993 COMMONWEALTH EDISON COMPA!U AND IOWA-ILLINOIS GAS rs ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 [ LICENSE NOS. DPR-29 AND DPR-30 i P TECHOPJWRC410NTHLY.RPT

- ~ _ - ~. ~ s t. TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance I A. Amendments to Facility License or Technical Specifications B. Facility or Proceduz. 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 i VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data i VII. Refueling Information I VIII. Glossary j ( i i i TErHOPNiRCatONTHLY.RFr -d- -.c-y -. --,

' t-t I. INT]tODUCTIOR Quad Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Depr. le capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jc_utly owned by Commonwealth Edison 1 Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply 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. r f b l TEOlOPENRC%MONTilLY.RPT ....~..m.

... ~.. -. - - l 4 4 i l II. SUKHARY OF OPERATIE9 EXPERIENCE J l A. Unit One i Quad Cities Unit One began the month of June 1993 at full power. Numerous load drops were performed on orders from Bulk Power Operations (BPO). Three of these load drops caused the. daily average not power generation to drop below 20% of full load. These occurred. on June 6, 7 and 12 with an average load of 580 MWe, 666 MWe, and 654 MWe respectively. On July 9, during a HPCI t'est a rupture disc failed resulting in-five injuries. The unit was shut down on 6/20/93 in anticipation of exceeding the LCO on HPCI system unavailability. Unit One remained off line for the rest of the month. For additional information on this event see License Event Report (LER) 254/93-005. B. Unit Two Quad Cities Unit Two completing its forced outage for repairs to the feed water system on June 1, 1993. The unit was made critical at 05:35 hours and the generator was synchronized to the grid at 18:52 hours. On June 5, Unit Two was reduced to 300 MWe for repairs to overheated reactor feed pump stator windings. A few load drops were i performed on orders from DPO but none caused the average daily power level to drop by more than 20% of full load. On June 13, at 06:24 hours, an automatic SCRAM occurred on Unit Two from a generator load reject. An investigation concluded that an internal fault had occurred in the main transformer. The transformer was replaced in 20 days causing Unit Two to remain off line for the rest of June. For additional information on this event see License Event Report (LER) 265/93-013. TECHOPANRCWONTHLY.RPT

i i III. PLANT OR PROCEDURE CHAEGES, TESTS, EXPERIMENTS, M R.fgAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specificationg Technical Specification Amendment No. 142 to Facility Operating License No. DPR-29 and Amendment No. 137 to Facility Operating License No. DPR-30 were issued on May 20, 1993 for Quad Ciies Nuclear Power Station, Units 1 and 2, respectively. The amendments revise the surveillance interval for the channel functional test of the Reactor Protection System Electrical Protective Assemblies (RPS-EPA units) per the guidance provided by Generic Letter 91-09, " Modification of Surveillance Interval for the Electrical Protective Assemblies in Power Supplies for the Reactor Protection System." The proposed change would eliminate the potential for inadvertent reactor trip caused by testing the RPS EPA units during power operation. D. Facility or Procedure Changes ReJuirina NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period. C. TeJts and E_xJeriments Reauirino NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period. D. Corrective Maid _tenance of Safety Related Ecuipment 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: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition. l TECHOPP.NHC410NTitLY.RPT

i. UNIT 1 & 1/2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFOPl4ED 006563 6700 1/2-6700-084 Repair broken Found left secondary disconnect secondary disconnect broken. Replaced with a new one. on 4kV breaker. l Q06735 6700 1/2-6700-057 Investigate / repair 4kV Found charging motor mounting breaker charging motor bracket too low to allow driving running continuously. pawl to advance racket wheel for l d a full stroke. Moved charging motor mounting bracket up about 3/16". t Q06751 6700 1/2-6700-077 Repair broken brush Installed a new charging motor. holder on 4kV breaker charging motor. 007208 300 1-0305-130 Investigate / repair CRD Found pressure switch tripped accumulator pressure about 200 psig higher than its switch alarm light. setpoint. Recalibrated pressure switch. Q07567 7300 1/2-7300-S014 Repair Unit 2 reactor Replaced flux shifter with a new building lighting #2 one. Reinstalled and tested, breaker. breaker in cubicle. } i t R t i .i 4 E I r + l e-._,v m 4 -y.- ~ a .y ,-r..

r E i ,+ UNIT 2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q00581 2300 2-0220-62A Repair valve seal Disassembled valve, cleaned, ring. performed a weld build up of o-ring area. Reassembled valve and performed a pressure test. Valve passed. l Q00838 902-17 2-902-17 Investigate high Removed fuse, cleaned holder, and temperature at 902-17 reinstalled fuse. panel fuse. i Q01589 2300 2-2301-18 Repack or adjust HPCI Removed Furmanite clamp and 4 discharge header Furmanite from valve. Cut out pressure test inboard valves #18 and #19 and installed stop valve. new valves. QO2161 1000 2-1001-65C Investigate high Machined outer bearing cover to vibrations in RHRSW allow for gasket and 0.012" end pump. play. Reassembled and reinstalled pump. i l QO3416 2300 2-2301-7 Repack HPCI testable Installed new hinge pin gasket. check valve. Repaired fitting at the coil. I Found a broken pipe nipple in the top of the valve. Replaced i nipple. Reassembled valve. 003719 300 2-0305-126 Reset limit switch and Found actuator arm rotated out of i actuator arm. alignment from its switch. Rotated actuator arm back into alignment. Q04437 1700 2-1734-A Investigate main steam Removed detector, reinstalled line rad monitor detector, taped cap to detector reading higher than and taped cables. the other detectors. 4 l l i i

Q04668 2500 2-2501 Repair / replace ACAD Replaced valve with a new one. air compressor discharge pressure i regulator. 004960 1700 1-1705-2C Investigate main steam Replaced detector with a new one. line rad monitor reading lower than the others and decreasing i over time. i Q05246 2500 2-2599-5B Repair ACAD vent to Found some scale in the bottom of SBGTS flow control the valve. Installed a new stem valve. Opened too and disc. slowly and showed. evidence of binding. 005524. 1000 2-1001-182A Replace RHR pump seal Found inner valve body heavily cooler service water corroded above the seat. side isolation valve. Disassembled valve, lapped disc and seat, cleaned interior, reconfigured packing, and reassembled valve. Q05525 1000 2-1001-182B Repair RHR pump seal Disassembled' valve.and repacked f' cooler service water with ARGO packing. side' isolation valve. Q05597 300 2-0305-111 Repair valve. Blows Changed out old valve for a new i by stem. one. i Q05604 1600 2-1601-59 Investigate flickering Cleaned I.O. contact and adjusted + indication light on actuating arm on the limit 902-3 panel. switch. [ Q05630 1000 2-1002A Perform' permanent Removed cooler from system and repair to gasket leak. disassembled valve. Reinstalled i on 2A-RHR pump seal with new gasket. cooler. i t -.- m. m.. - + .-.=m-e -e

e 005650 1600 2-1601-57 Nitrogen makeup inlet Found bad switch. Replaced valve to drywell will switch. not open with control switch. Repair. Q05822 902-3 2-0902-3 Replace socket on Replaced old socket with new closed light socket. indication for 902-3 panel. Q06135 3000 2-3036E Repair piping for 3E Found_ leak off line sheared. electromatic pilot Refabricated drain line and discharge / leak off. reinstalled. Fabricated and installed piping support. Q06197 203 2-0203-2B Repair 2B outboard Disassembled valve and operator. MSIV. Valve failed Excavated three cracked welds and LLRT. made weld repairs. Reassembled valve and operator. Q06307 1600 2-1600-X14 Repair / replace reactor Cut out old bellows. Replaced water clean up inner bellows. bellows. 006310 220 2-0220-2 Repair broken Replaced cable. insulation on main steam line outboard drain valve limitorque power cable. Q06334 1000 2-1001-47 Repair open button for Raised switch so button could RHR reactor outboard make contact. suction valve. Q06339 261 2-0261-16A Replace main steam Installed new switches after 2-0261-18D line temperature calibration. switches. 1..- .a.. .w# w

1 i r ' I Q06363 2400 2-2499-1A Repair loose CAM Tightened retainer nut and set i i solenoid valve and screw. switch housing. Q06427 7800 2-78281A125 Investigate MCC 28-1A-Replaced breaker. 1 cubicle 3. Could not get accurate j reading or set amps. 006428 1300 2-1301-17 Replace motor power Found wire conductors exposed l cable for main. steam through cable insulation. t j to RCIC downstream Replaced old cable with new. stop valve limitorque. Q06493 7800 2-7828295B4 Replace broken Installed new lockwasher. [ lockwasher on MCC i l 28/29-5 cubicle B4, inboard LPCI injection valve. Q06613 1400 2-1404-10A Adjust spring can load Adjusted spring can. to 1685 pounds. i 006684 7800 2-78292--B1 Repair MCC 29-2 Replaced shorted light socket f cubicle Bl. with a new one. Q06786 8300 2-832A---F1 Repair cracked stab Replaced stab assembly with a assembly on MOV like part. l controller for 2-2301-49 valve. l Q06808 2400' 2499-2B Repair CAM monitor Tightened set screws and solenoid I 2-2499-3B solenoid valves. retainer nuts. L 2-2499-4B I l Q06866 2300 2-2300 Replace HPCI turning Found one of the brushes cracked gear motor brushes. and a broken wire on the heater. Removed old heater and brushes. Installed new heater and brushes. b

Q06922 7800 2-7828295A4 Repair broken terminal Installed new terminal strips and strip on MCC 28/29-5. rewired. Q06943 1000 2-1001-19A Replace RHR cross tie Removed old motor and installed j north stop valve new one. Installed new breaker limitorque. and overload heaters. Q07005 201 2-0201-JP18 Replace jet pump; Mixer was moved back into appears to be skewed position. A new swing gate was or bent. installed. Q07033 1000 2-1001-58 Repair major air leak Replaced old diaphragm with a new on head spray pressure one. control valve = diaphragm dome. Q07091 300 2-0302-82E Investigate excess Replaced 82H and 82E relays. 2-0302-82H chatter in SCRAM discharge volume level switch relays. Q07106 1000 2-1001-20 Repair "Open" Found socket broken, cover gasket indicating light on extremely brittle, and some water RHR crosstie valve to in the control station. Replaced radwaste. socket and cover gasket. 007137 1000-2-1056B Repair leak in RHRSW Replaced piping. return line from seal coolers. Q07148 1600 2-1601-23 Repair position Found open' limit switch out of indication for drywell adjustment. Adjusted the limit vent valve. switch. Q07165 590 2-590-2A2-B11 Repair 2A2 RPS EPA Installed new breaker. breaker. Q07168. 7800 2-78293-E3 Replace MCC 29-3 Installed new breaker. cubicle E3 turbine turning gear piggy back breaker. i 1

(' Q07175 1000 2-1002D Repair leaking cooling Repaired with new nipple. Added coil connection on 2D a bushing and a 90 degree "L". RHR motor. 007183 1400 2-1402-38A Repair core spray pump Found what appeared to be an old min flow valve. Dual pencil dosimeter in the valve indication is shown in body. Reassembled and repacked i the control room. valve. Q07219 203 2-0203-1A Repair broken terminal Replaced terminal block and lugs strip. at the 1A and 1C NSIV pilot j solenoid junction-box. Q07235 1000 2-1000 Replace small bore Installed a new rod to the spring spring can pipe can. t hanger. Q07295 1000 2-1001-43B Investigate / repair Found a bad lug. Relugged the 3 2-1001-7B RHRSW pump suction wire. i valve operator. Would i not open from control 4 room. Q07338 263 2-0263-139B Investigate cause of Found switches for trip output i reactor level master logic reversed. Changed switch trip unit LED position to normal. remaining lit when relay was de-energized. 007377 5700 2-5746A Investigate and repair Found red wire landed on wrong 2A RHR room cooler terminal. Lifted red wire and failure to start in landed it on the correct " Hand." terminal. Q07393 30 2-0030-247 Repair-broken door Re-welded latch handle. e catch-on watertight Reinstalled and tightened door..to 2D RHRSW pump packing. room. l ~.

{ r-r Q07396 263 2-02064-12A Troubleshoot B loop Found bad regulator and blown indications for fuse. Replaced with identical l reactor temperature parts and reinstalled circuit. equalizing column. Q07422 263 2-0263-72A Repair leak on reactor Found access plug leaking. level ECCS switch. Removed, reinstalled, and tightened plug. No leaks noted. Q07433 1400 2-1402-9A Repair leak on 2A core Tightened cap' screws on inner f spray testable check plate. l i valve. l Q07434 1400 2-1402-9B Repair leak on 2B core Tightened allen screws on inner spray testable check plates. valve. I Q07475 2300 2-2301-75 Repair leak at HPCI Installed new gasket. lube oil cooler discharge check valve. Q07498 7800 2-78292-D1 Replace light socket Replaced transformer. and transformer at MCC 29-2. Q07510 8800 2-8803A Repair leak between Replaced pipe. t penetration and FCV 8801C found during IPCLRT. Q07535 203 2-0203-2C Replace flex hose air Installed a new hose using old line to 2C MSIV. fittings. I Q07538 2300 2-2301-6 Repair indication for Found torque switch held open by HPCI pump CCST suction motor cable. Moved motor cable valve. and torque switch closed. 007547 756 2-0756-3 Investigate APRM #3 Found LPRM card 2B giving hard 2-0756-48-49B hard downscale. ,downscale signal. Installed new LPRM card. i ,,+,4 --r- ,n ~ ~ 4 m ~,

4 a Q07555 220 2-0220-52 Repair operator Installed new diaphragm after diaphragm for reactor inspection and cleaning. head seal upstream sample valve. Q07573 220 2-0220-1 Repair main steam line Found closed torque switch inboard drain valve. contacts open. Replaced torque i Valve would not close. switch. t Q07575 203 2-0203-1A Investigate / repair 1A Found air supply valve knob to 2 inboard MSIV. Valve the pilots loose and spinning on would not open. valve stem and air valve closed. Opened valve and MSIV stroked l satisfactorily. 007590 203 2-0203-2C Repair air leak at the Found leaking brass union. j coupling connection to Replaced brass union with 2C outboard MSIV stainless steel and tightened. i solenoid assembly. i Q07747 2300 2-2340-1 Troubleshoot and Adjusted programming on repair HPCI. Required controller in 902-3 panel. flow reached in 52 Cleaned threads on motor speed seconds. Acceptable . changer motor. Installed new time to reach required motor. Required flow was reached flow is 45 seconds in 30 seconds. Q81326 1400 2-1402-6A Replace pressure seal Attempt to. disassemble valve j. ring on 2A core spray failed. Furmanite glued the stop valve. valve bonnet into the valve. Q84316 1600 2-1601-32E Repair / replace vacuum Replaced seat,.all o-rings and breaker. gaskets in stuffing boxes. Q89759 1000 2-1001-65C Repair 2C RHRSW pump Replaced wear rings, machined and booster pump casing rings and shaft sleeves, inboard and outboard balanced shaft, and replaced seals. mechanical. seals.

C 094761 5400 2-5402B Repair SJAE south Replaced cracked' oil fill cap suction valve oil with a new one. leak. Q95256 1000 2-1002B Investigate / repair 2B Installed new seal. RHR pump inboard bearing seal leak. i Q96076 756 2-0756-40-25D Troubleshoot / repair Replaced detector under 003066 LPRM 40-25 detector D. during Q2R12. 097358 902-4 2-902-4 Replace broken Installed new terminal block. + insulator on 902-4 panel terminal board ZZ. Q97360 902-4 2-0902-4 Replace broken Found two fuse holders damaged. insulator on 902-4 Installed new fuse holders. panel terminal board MM. Q97780 1000 2-1001-182C Repair RHR pump seal Found stem bent, top threads on water cooler inlet yoke damaged, and pitting on stop valve. stem. Lapped seat, installed new stem and disc, and repacked with ARGO packing. Q97851 300 2-0301-106B Repair south CRD bank Cleaned seat and disc. Repacked SCRAM discharge volume with ARGO packing. level transmitter isolation valve. Q97852 300 2-0301-102A Repair north CRD bank Cleaned seat-and disc. Repacked 2-0301-103A SCRAM discharge volume with ARGO packing. level transmitter' isolation valves. i u.

4. 098784 2300 2-2301-49 Repair crushed conduit Found sealtite for motor cable to HPCI cooling water crushed at the MOV housing. pump test valve Installed new sealtite. actuator. I~ 099149 1000 2-1001-28A Repair LPCI outboard Disassembled valve. Cleaned injection valve seal valve internals. Installed disc, i ring leak. stem, bonnet, pressure seal ring, and torqued to 750 ft-lbs. i 099323 203 '2-0203-2B Repair 2B NSIV limit Spliced new cable to old cable switch junction box and installed new lugs in MSIV cabling. junction box. Replaced old terminal block with new safety related terminal block. Q99371 220 2-0220-45 Repair air leak on 2B Replaced air line. recirc loop downstream sample stop valve. i Q99410 1000 2-1001-19A Repair leak at north Lapped seat and wedge, polished RHR crosstie valve. stem, cleaned all sealing surfaces, repacked valve. 4 i Q99766 220 2-0220-118A Replace missing stud Found packing follower stud j and packing nut at broken off. Installed bracket ATWS-header isolation and block for the stuffing box l root valve. follower. Q99782 1000 2-1001-68A Investigate cause of Found air leaking out of actuator check valve housing. Disassembled-actuator. malfunction. Installed new seal and o-ring. Reinstalled bottom half of actuator with new gaskets. 1 Q99794 220 2-0220-45 Repair damaged cable Removed old splice and respliced on 2B recirc loop cable. sample downstream stop valve solenoid. i e - -- --. t

s. IV. LICENSEE EVENT. REPORTS The following is a tabular summary of all licensee event. reports for Quad-Cities Unita 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. UNIT 1 Licensee Event Repor_i_ Number Date Title of occurrence 93-005 06-09-93 During HPCI Testing Rupture Disc failed. 93-007 06-24-93 Control Room Vent TGA Sample Pump found off. UNIT 2 Licensee Event Rgoort Number Date Title of occurrence 93-011 06-02-93 HPCI declared INOP when it failed to meet flow requirement during manual initiation test. l 93-012 06 01-93 DGCWP INOP from an inadequate oil j supply to the bearing, j 4 93-013 06-24-93 RX Scram from fault on U2 Main Transformer. i i TEO K)PLNRO.MoNDILY,RPT 2.. ~

.. -. ~.. =- - .. -.. ~... _ - - 1 V. DATA TABULATIONS The following data tabulations are presented in this report: 2 A. Operating Data Report i B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions f b b 1 4 7 4 TECitOPEN RC410N11tLY.RPT. r .~. -....,.4-..

e, e, APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNTT One DATE July 3,1993 COMPLITED BY Matt Benson TELEPIIONE (309) 654-2241 OPER ATING STATUS 0000 060193

1. REPORTINO PERIOD: 2400 063093 GROSS IlOURS IN REPORTING PERIOD: 720 i
2. CURRENTLY AUTilORIZED POWER LEVEL (MWO: 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL R.ATING (MWe-NET): 789 6

3, POWER LEVEL TO WillCli RESTRICTED (IF ANY) (MWe-Net)' N/A

4. REASONS FOR RESTRICTION (IF ANY):

Tills MONTil YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRrriCAL 460.60 4028.90 146789.80
6. REACTOR RESERVE S11UTDOWN ilOURS 0.00 0.00 3421.90
7. IlOURS GENERATOR ON LINE 459.50 4006.60 142398.20 8 UNIT RESERVE SilUTDOWN llOURS 0.00 0.00 909.20
9. GROSS TilERMAL ENERGY GENERATED (MWII) 999309.60 9498427.20 307080251.00
10. GROSS ELECTRICAL ENEROY OENERATED (MWil) 325088.00

' 3094755.00 99513845.00

11. NET ELECTRICAL ENEROY GENERATED (MWil) 307362.00 2968706.00 93844218.00
12. REACTOR SERVICE FACTOR 63.97 92,77 78.92
13. REACTOR AVAILABILITY FACTOR 63.97 92.77 80.76
14. UNIT SERVICE FACTOR 63.82 92.25 76.56 t

15, UNIT AVAILABILTTY FACTOR 63.82 92.25 77.05 i

16. UNTT CAPACTTY FACTOR (Uning MDC) 55.51 88.89 65.61
17. UNIT CAPACITY FACTOR (Using Design MWe) 54.11 86.64 63.95
18. UNIT FORCED OUTAGE RATE 36.18 7.75 5.87
19. $11UTDOWNS SCllEDULED OVER NEXT 6 MONTils (TYPE, DATE AND DURATION OF EACil).
20. IF SilUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

.j

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

FORECAST AcillEVED INiflAL CRrflCALrrY INTTIAL ELECTRICITY COMMERCI AL OPERATION

7. I6-9 i

l TECHOPANRC4tONTHLY.RFT =

~ ~... .e4 APPENDIX C OPER ATING DATA REPORT DOCKET No. 50-265 UNrr Two DATE July 3,1993 COMPLETED BY Matt Benson TELEPilONE 0 09) 654-2241 OPER ATING STATUS 0000 060193

1. REIORTING PERIOD: 2400 063093 GROSS IlOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTilORIZED POWER LEVEL (MWt): 2511 M AX > DEPEND > CAPACITY.: 769 DESIGN ELECTRICAL RATING (MWo-NLT): 789 3, POWER LEVEL TO WillCil RESTRICTED OF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICrlON (IF ANY):

Tills MONTil YR TO DATE CUMULa.T!VE

5. NUMBER OF llOURS REACTOR WAS CRrrlCAL 288.80 1780.00 140955.25
6. REACTOR RESERVE SIIUTDOWN llOURS 0.00 0.00 2985.80 7, ilOURS GENERATOR ON LINE 275.50

!649.00 137340.45 8, UNir RESERVE SillfrDOWN llOURS 0.00 0.00 702.90

9. GROSS TilERMAL ENERGY GENERATED (MWII) 549204.00 3917400.00 296580809.20
10. GROSS ELECTRICAL ENEROY GENERATED (MWil) 176223.00 1277105.00 95302366.00 11, NET ELECTRICAL ENEROY GENERATED (MWII) 163876.00 1206897,00 90237640.00
12. REACIOR SERVICE FACTOR 40.11 40.99 76.43
13. REACIOR AVAILABILITY FACTOR 40.11 40,99 78.04
14. UNrr SLRVICE FACTOR 38.26 39.12 74.47
15. UNIT AVAILABILITY FACTOR 38.26 39.12 74.85
16. UNrr CAPActrY FACTOR (Uning MDC) 29.60 36.14 63.62
17. UNIT CAPActrY FACTOR (Uning Design MWe) 28.85 35.22 62.01
18. UNir FORCED OUTAGE RATE 61.74

.-28.69 8.11

19. SilVTDOWNS SCHEDULED OVER NEXT 6 MON'111S (TYPE, DATE, AND DURATION OF EACll):
20. IF SIIUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21 UNTIS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FOR.ECAST AClllEV ED INrrlAL CRITICALrrY INTIIAL ELECTRICIrY COMMERCI AL OPERATION i 16-9 TECHOPANitCWONTHLY.RPT

a, APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE July 2. 1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH June 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' (MWe-Net) (MWe-Net) 1. 782 17. 738 2. 708 18. 749 3. 773 19. 22 4. 789 20. -10 5. 790 21. - 9 6. 580 22. - 8 7 666 23. -9 8, 702 24. - 9 9. 705 25, -10 10. 724 26. -10 11. 719 27 -11 12. 654 28. -10 13. 679 29. - 9 9 14. 724 30. 15, 700 31.

16. __

703 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 j 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 i cutput sheet should be footnoted to explain the apparent anomaly. 1.16-8 TEcHOP3WRC*a10NTELY,RFT 4 v y-. -,w.,, -#,~-.e .m .i.c-,,,,, .ym.e, e._ g.

i,

  • APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two l

DATE July 2. 1993 i COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH June 1993 .J l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) l 1. 38 17. -8 2. 444 18. -9 3. 484 19. -11 4. 685 20. -10 5. 592 21. -8 a 6. 375 22. -8 7. 659 23. -8 8. 673 24. -8 9. 705 25. -9 l 10. 736 26. -10 11. 784 27. -10 .12, 680 28. -10 2 13. 128 29, -9 i i 14. -9 30. -9 1 15. -9 31 16. -9 i 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. _ there Note that when maximum dependable capacity is used for-the net electrical rating of the unit, 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. 1.16-8 TECHOP3bN RC4tONT1{LY.RPT

~.. tj 4 l APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY-Matt Benson DATE July 7, __1993 REPORT MONTH June, 1993 TELEPHONE 309-654-2241 m Z O E M

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Z sa o O 0 MO mO 0 P 3 30 QU L1 M An m M $i LICENSEE O .i DURATION 8 EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 93-32 06-02-93 70 F 5 12lad Drop Per Bulk Power Operatiora l 93-33 060493 5 35.3 F 5 Load Drop Per Bulk Power Operations 93 34 06-08-93 S 7.1 F 5 Load Drop Per Bulk Power Operations _ 35 v6-09-93 S 9.5 F 5 Lead Drop Per Bulk Power Operations 93 93-36 06-10-93 S 6.9 F 5 Load Drop Per Bulk Power Operations 93-37 06-11-93 5 7.3 F 5 Load Drop Per Bulk Power Operations 93 06-12 S 9.1 F 5 Load Drop Per Bulk Power Operations 93-39 06-13-93 S 10.2 P 5 Load Drop Per Bulk Power Operations 93-40 06-14-93 S 6.2 F 5 Load Drop Per Bulk Power Operations 93 Do 15-93 5 7.2 F 5 load Drop Per Bull Power Operations 93 42 06 16-93 S 10.3 F 5 Load Drop Per Bulk Power Operations 93-43 O&l7-93 5 6.6 F 5 Load Drop Per Bulk Power Operations 93-44 06-19-93 F 2tio.5 D 2 HPCI Repairs could not be cornpleted in the LCO Window. p,.-- l-l r l P l l MTECHOPEN RCMPPD.R t -~r su- + i z E.

_e APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 5_0-265 UNIT NAME Two COMPLETED BY Matt Benson DATE Julv 7, 1993 REPORT MO!TITI June, 1993 TELEPHONE 309-654-2241 x r4 Z M 3 NN' N O gW ad A O Q o MO o O hO m 3 NU hU px$ w m o $M LICENSEE u DURATION 8 EVENT CORRECTIVE ACTIONS /COIGIENTS NO. DATE (HOUkS) REPORT 93-04 06-05-93 F 16.9 A 5 2B & 2C RFP Stator Winding High Temperature i 93-05 06-08 83 S 7.3 F 5 Load Drop per Bulk Power Operations 93 06 06 09 93 S 9.4 F 5 Load Drop per Bulk Power Operations 93-07 06-10 93 S 5.4 F 5 Load Drop per Bulk Power Operations 934)$ 06-13-93 F 425.6 A 3 Auto SCRAM Due to Internal Fault on Main Transformer 4 1 i l l l L\\TEGIOPJWRC\\APPD.R i i I

- ~.. s. e VI. UNIOUE REPORTING REOUIREMENTS The following items are included in this report based on prior commitments to the commission: A. Main Steam Relief Valve Operations Relief valve operations during the reporting period are summarized.in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation. Unit: One

Date, June 19, 1993 Valve Actuated:

No. & Tvoe of Actuation: 1-203-3A Scheduled Surveillance - 1-203-3B Routine Testing. 1-203-3C 1-203-3D 1-203-3E Plant Conditions: 915 psig Rx, Pressure Descrintion of Events: All valves functioned properly. B. Control Rod Drive Scram Timina Data for Units One and Two There was no Control Rod Drive scram timing data for Units One and Two for - I the reporting period. i a r l f i TECH 0PENRCiMONDILY.RPT ~,,..

_m m VII. REFUELING INFORMATION The following information about' future reloads at Quad-Cities Station was ] requested in a January 26, 1978, licensing memorandum (78-24) from 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 9 a t F i 6 3 t a i 1 6 TECHoPMROMONTHLY.RPT n n -,,,e 4 r --r-

i -- - $ lQTP 300-532 Revision 2 QUA0 CITIES REFUELfNG October 1989 INFORMATION REQUEST 1. Unit: 01 Reload: 12 13 Cycle: 2. Scheduled date for next refueling shutdown: 3-14-94 3. Scheduled date 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 submitting proposed licensing at. tion and supporting information: NOT AS YET DETERMINED t 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysts methods, significant changes in fuel design, new operating procedures: 160 GE10 Fuel Bundles will be loaded during Q1R13. 7. The number of fuel assemblies. a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 1557 e 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 pocI assuming the present licensed capacity: 2009 APPROVED (final) 14/0395t DCT 3 0 M9 C1.C.O.S.R. . i.

QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1, 1. Unit: Q2 Reload: 12 Cycle: 13 2. Scheduled date for next refueling shutdown: 09-24-94 3. Scheduled date for restart following refueling: 12-04 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 submitting proposed licensing action and supporting information: NOT AS YET DETERMINED. 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. p 7. The number of fuel assemblies. 1 a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 2583 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 l spent fuel pool assuming the present Ilcensed capacity: 2009 APPROVED 14/0395t NE Q.C.O.S.R.

VIII. GLOS 9ARY 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 ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CPB - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations Facility GSEP - Generating Stations Emer ency Plan HER - 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 RBCCW - Reactor Building Closed Cooling Water System kBM - Rod Block Monitor i RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System RWM - Rod Worth Minimizer SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Voleme SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center TEcHOP1WRCMONTHLY.RPT ..}}

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