Text

Monthly Operating Repts for Jan 1994 for Quad Cities Nuclear Power Station Units 1 & 2
	ML20063H320
Person / Time
Site:	Quad Cities
Issue date:	01/31/1994
From:	Michael Benson, Scott A; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	AMS-94-04, AMS-94-4, NUDOCS 9402170315
	Download: ML20063H320 (29)
	v • d • e

,

Commonwzith Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, tilinois 61242 Telephone 309/654-2241 AMS-94-04 February 1, 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, 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 January 1994.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

$$arlkf Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc:

J. Martin, Regional Administrator T. Taylor, Senior Resident Inspector TEG10MWRCWONELY.RFT

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j QUAD-CITIES NUCLEAR POWER STATION i

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MONTHLY PERFORMANCE REPORT i

i January 1994 1

COMMONWEALTH EDISON COMPANY 1

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IOWA-ILLIN0IS GAS & ELECTRIC COMPANY i

NRC DOCKET N05. 50-254 AND 50-265 i

1 LICENSE NOS. DPR-29 AND DPR-30

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TABLE OF CONTENTS 4

i I.

Introduction 4

II.

Summary of Operating Experience 1

A.

Unit One B.

Unit Two

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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 TLCIOP3\\NRC4f0N1MLY.RPT 4

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INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water i

Reactors, each with a Maximum Dependable _ capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison N

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 Douket Numbers 50-254 and 50-265. The date of initial Reactor criticalitiei 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.

TFfHOP3\\NRC\\MONDILY.RPT

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SUMMARY

OF OPERATING EXPERIENCE i

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A.

Unit One I

Quad Cities Unit one began the month of January 1994'with the reactor.

critical and the generator off-line. The generator was._ synchronized to the grid at 22:36 hours on January -1 and load was. increased to full on request by Bulk Power Operations (BPO).

i On January 11 at 21:43 hours, Unit One reduced load to 250 MWe to work' 4

on the #2 main. steam stop valve. The unit was returned to full power j

by 11:00 January 12.

t On January 29 at 00:25 hours, Unit one. reduced load to 540 MWe to i

replace a seal on a condensate booster pump.. The administrative load l

j drop was exited at 21:00 hours the.same day.

J Two load drops were performed for the BP0 and a. turbine surveillance-

~

J-but neither caused the average daily unit power'1evel to drop by 20%

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or greater.

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B.

Unit Two 1

Quad Cities Unit Two began the month of' January 1994 in' cold shutdown.

i The maintenance outage,.which began in December, ended on January 25 at 08:36 hours when the reactor was made critical. The generator was synchronized to the grid at 12:45~ hours on January 26 and held 140 MWe i

for scram timing. The unit was brought to' full power on January 29:

where it remained through the end of the month.

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical SDecifications Amendment No. 139 to Facility Operating License No. DPR-30 was issued on January 19, 1994 for Quad Cities Nuclear Power Station, Unit 2..

The license amendment dispositions'Unreviewed Safety Questions (USQ)~

related to proposed plant modifications associated with the reactor-i vessel water level instrumentation. These modifications -have been ~

)

. initiated to mitigate the circumstances outlined:in NRC Bulletin 93-03, " Resolution of Issues Related to Reactor Vessel Water Level.

Instrumentation in BWRs."

These amendments are issued. pursuant to the requirements'of.

10CFR50.59(c) because the review by Commonwealth Edison Company identified the changes as an Unreviewed Safety Question.. No' change to the Technical Specifications'is required by.this amendment.,

B.

Facility or Procedure Chances Reauirina NRC ADDroval There were no racility or Procedure changes requiring NRC' approval for the reporting period.

C.

Tests and Experiments Reauirina NRC ADDroval There were no Tests or Experiments requiring NRC approval for the.

reporting period.

D.

Corrective Maintenance of Safety Related Eauipment -

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, System Component Description and work performed.

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o UNIT 1 & 1/2 MAINTENANCE

SUMMARY

NWR#

SYSTEM EPN#

WORK REQUESTED WORK PERFORMED Q04876 1600 1-1601-62 Repair / replace damaged Replaced solenoid valve.

electrical connector on solenoid valve.

Q05431 7300 1/2-7200-Replace relay because Replaced relay.

S009 of broken relay body.

Q06526 2500 1-2599-4B Repair air leak on Replaced pressure gauge and ACAD vent to SBGTS crushed tubing.

valve.

Q08343 1000 1-1001-66B Repair 1B RHR pump Torqued bonnet bolts to 375 discharge valve leak.

ft/lbs.

Q08571 2300 1-2399-52 Replace missing Installed new handwheel and handwheel on HPCI lube fastener.

oil to pump inboard bearing stop valve.

Q08876 750 1-0750-7A Repair under NWR Replaced detector, retainer, and Q06354 failed.

receptacle.

Investigate / repair IRM 11 erratic indication.

Q09031 1600 1-1602-1 Replace broken Replaced sealtite and performed 1-1623 sealtight going to calibration.

transmitter of suppression chamber vent header to reactor building pressure indicator.

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Q09047 1000 1-1001-189B Repair broken Replaced handwheel with a new handwheel on 1B RHRSW one.

pump room cooler outlet valve.

Q09737 1000 1-1001-37B Repair bonnet bolts on Adjusted engagement and retorqued 1B torus spray stop to 150 ft/lbs.

valve.

Q09921 2300 1-2301-64 Repair HPCI turbine Replaced actuator diaphragm, above seat inboard spring operator, and installed i

drain valve.

new studs.

Q09922 2300 1-2301-65 Repair HPCI turbine Replaced packing and installed above seat outboard new studs.

drain valve.

Q10105 2300 1-2301-20 Repair leak on HPCI Rebuilt valve using original CCST suction check parts, a new gasket, and new valve.

washers.

Q10258 263 1-0263 Repair leaking union.

Seal Welded check valves and collars on unions.

Q10477 2300 1-2365 Repair steam leak at Replaced gasket.

magnetrol connection to HPCI turbine inlet drain pot level switch.

Q10520 1000 1-1001-65D Replace sightglass Removed sightglass, cleaned assembly on 1D RHR threads and gaskets, and service water pump.to reinstalled.

repair oil leak.

Q10549 2500 1-2599-2B Repair 1B ACAD drywell Replaced solenoid valve.

discharge valve solenoid.

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Q10634 300 1-305-117-Troubleshoot / repair Rebuilt scram pilots using repair 1451 scram pilot valves for kits.

1-305-118-CRD 14-51.

1451 Q11013 220 1-220-45 Troubleshoot 1B recirc Found "Never-seize" caked on the loop sample downstream stem.

Removed "Never-seize" and valve.

Valve took tested operator with outside air.

over 30 seconds to Stem was lubricated with grafoil close during paste.

surveillance.

IST requirement is 0.9-2.7 sec.

Q11080 9400 1/2-9400-Repair control room Replaced 4 actuator o-rings.

103 HVAC analyzer.

Q11394 263 1-263-72B Repair ECCS reactor Adjusted needle so it wouldn't level indicating hang up on the cover and switch.

calibrated switch.

Q11522 2000 1-2001-16 Header isolation Replaced scienoid valve and coil.

drywell sample discharge to waste collector tank valve will not close.

Repair.

Q11601 300 1-305-127 Replace or repack CRD Repacked valve.

26-31 scram outlet valve.

Q11604 1400 1-1402-38B Install correct gear Installed new worm shaft gear and ratio in the 1B core motor pinion.

spray pump min flow valve limitorque.

Q11640 7300 1/2-7300 Repair the secondary Replaced secondary disconnect.

disconnect on 480 VAC breaker #S024.

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Q11687 300 1-305-126-Repair packing leak on Replaced packing.

5027 scram inlet valve.

Q11750 1000 1-1001-23B Replace bent stem on Replaced stem.

1B containment spray loop upstream stop valve.

Replaced t'rque switch and finger Q11780 1000 1-1001-43B Investigate RHR pump o

shutdown cooling base sub-assembly.

suction valve limitorque tripped thermals.

Q11915 1000 1-1003D-12D Repair 1A RHR service Replaced piping.

water pump cross connection piping.

Q11941 1400' 1-1467-A Replace test fitting Replaced test tap fitting on on 1A core spray pump switch.

discharge pressure switch.

Q11942 1000 1-1054 Replace test fitting Replaced test tap fitting on on RHR discharge low switch.

pressure switch.

Q11950 261 1-261-23A Replace test taps Replaced test fittings.

1-261-23B associated with reactor pressure switches.

Q11990 2300 1-2301-65 Investigate / repair Adjusted the open limit switch.

lack of open indication in control room for HPCI turbine stop valve above seat outboard drain valve.

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Q11998 7800 1-78181A-C4 Investigate / repair RHR Recalibrated switches.

room cooler.

Q12027 300 1-305-111-Repair packing leak as Replaced valve cartridge.

3815 soon as possible on CRD nitrogen block valve.

Q12047 750 1-750-7C Investigate / repair Replaced pre-regulator.

frequent spiking on IRM 12.

Q12048 700 1-702-18 Replace IRM 18 Replaced switch.

selector switch as soon as possible.

Q12122 263 1-263-2-12A Repair leak on RVWLIS Repacked valve.

isolation valve.

Q12179 756 1-756-7 Repair drifting APRM Sent trip reference card to reference on RBM.

vendor for repair.

Q12314 300 1-305-117-Rebuild 117 and 118 Rebuilt both valves.

4635 valves for CRD 46-35 due to failure to scram.

Q12714 263 1-263-145B Investigate / repair Replaced DP transmitter and 1-263-58B cause of 1/2 scram fuseholder.

from reactor level indicating switch master trip unit oscillations.

Q12848 203 1-203-1B Investigate / repair B Replaced control switch on MSIV DC solenoid power breaker.

breaker failure to reenergize when group 1 logic was reset.

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1 Q13453 9400 1/2-9400-Troubleshoot and Replaced starter.

102 repair "B" train compressor.

Q13926 1600 1-1640-200A Repair torus Installed new recorder.

temperature recorder.

Q13950 2000 1-2001-245B Troubleshoot / repair Found aux contact sticking at 1-78183--C3 drywell equipment breaker (MCC 18-3 cubicle C3.)

drain sump pump.

Replaced aux contact.

Q76135 220 1-220-48 Repack reactor head Replaced packing and T-handle.

vent outboard bypass valve.

Q89082 20 1-0020 Repair supports for Installed new anchors.

division II cable pans.

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UNIT 2 MAINTENANCE

SUMMARY

NWR#

SYSTEM EPN#

WORK REQUESTED WORK PERFORMED QO3423 20 2-20-119 Replace broken glass on Replaced broken window and reactor building sealed edges.

interlock door.

Q08498 2300 2-2200 Replace missing Replaced mounting hardware.

mounting hardware in HPCI console.

Q08645 2300 2-2315 Repair broken left A new hinge was fabricated and hinge on HPCI turbine installed.

lube oil sump access hatch.

Q09219 756 2-756 Investigate LPRM Ran I/V curve.

25D spiking.

Q09692 2500 2-2540-6A Repair ACAD vent flow Calibrated indicator and 2-2541-2A indicator.

transmitter.

Q09926 1000 2-1053D Replace isolation valve Replaced valve.

for RHR pump discharge pressure switch.

Q09954 30 2-0030 Repair MSIV room Removed all existing grout from missing grout on-behind base plates and regrouted support grid.

all 10 plates.

Q10451 1000 2-1001-65D Repair inboard bearing Replaced sightglasses.

oil sightglasses on 2D RHRSW pump.

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NWR#

SYSTEM EPN#

WORK REQUESTED WORK PERFORMSD Q11121 2400 2-902-56 Investigate / repair Found plug and socket improperly 2-2419-B cause of "Drywell High aligned.

Realigned plug and Rad Conc" alarm failure

socket, to come in during surveillance.

Q11190 1300 2-1360-9B Repair / replace Replaced valve.

isolation valve for RCIC reactor low pressure switch.

Q11556 750 2-750-7F Troubleshoot / repair IRM Replaced pre-regulator.

17 not responding to range switch.

Q11557 3900 2-3900 Repair service water Installed new rod and nuts, pipe hanger.

Q11610 300-2-305-111-Replace nitrogen Installed new valve.

5447 charging isolation.

valve.

Q11745 263 2-263 Repair leaks at tdua Seal welded threads-on check RVWLIS sensing line valves and unions.

unions on the "A"

loop.

Q11746 263 2-263 Repair leaks at the Seal welded all threaded joints.

RVWLIS sensing line unions on the "B" loop.

Q11799 756 2-756-7 Troubleshoot / repair rod Replaced quad trip card..

block monitor 7.

Q12280 263 2-263-55A Repair leaking Disassembled valve and cleaned isolation valve for internals.

reactor high pressure switch.

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NWRf SYSTEM EPN#

WORK REQUESTED WORK PERFORMED Q12316 220 2-220-81E Repair stuck shut 3E Cleaned valve bonnet, seat, and ERV vacuum breaker disc and installed new gasket.

check valve.

Q12556 1000 2-1001-16A Repair broken light Found socket smashed.

Replaced socket on local control socket.

station.

Q12651 5200 2-5200 Replace diesel fuel Fabricated new tubing and tubing.

replaced the old tubing and fittings.

Q12687 6600 2-6641-CPS Replace flange gaskets Repl' aced gaskets.

on diesel generator lube oil crankcase pressure switch.

Q12932 6600 2-6666A Repair seal leak on 2A Replaced water pump shaft, seal, engine driven coolant and seal ball bearings.

pump.

Q13098 2300 2-2301-14 Repair indicating Replaced indicating light base light.

assembly.

Q13169 1000 2-1001-193B Troubleshoot / repair RHR Installed new MTU.

2B minimum flow bypass valve dp switch.

Q13268 1700 2-1705-8B Investigate / repair 2B Replaced sensor and converter.

reactor building-vent monitor.

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'IV.

LICENSEE EVENT 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.ti B.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1

. Licensee Event Report Number Data Title of occurrence 94-001 01-24-94 Rod drifted in to position 14.94-002 01-04-94

- B" control room vent. inoperable.

94-003-01-21-94 Missed continuous fire watch.

' UNIT 2 Licensee Event Report Number Date Title of occurrence 94-001 01-26-94 RCIC failed to meet flow and pressure

)

requirements, i

94-002 01-28-94 Mispositioned control rod.

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V.

DATA TABULATIONS The following data tabulations are presented in this' report:

A.

Operating Data Report-B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions I

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNTT One a

DATE February 7,1994 COMPLETED BY Matt Benson a

TELEPHONE (309) 654-2241 3

OPERATING STATUS l

0000 010194 l

1. REPORTING PERIOD: 2400 013194 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPAMY: 769 l

DESIGN ELECTRICAL RATING (MWe-NET): 789 a

3. POWER LEVELTO WlHCH RESTRICTED OF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION OF ANY):

1 THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 744.00 744.00 150525.30

6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 3421.90 4

7. HOURS GENERATOR ON LINE 721.40 721.40 146007.70

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1696503.50 1696503.50 315389690.70 l

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10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 554672.00 554672.00 102252791.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 530637.00 530637.00 96448635.00

12. REACTOR SERVICE FACTOR

'100.00 100.00 78.74 i

13. REACTOR AVAILABILTTY FACTOR 100.00 100.00 80.53

14. UNTT SERVICE FACTOR 96.96

' 96.%

76.38

15. UNTT AVAILABILTTY FACTOR 96.%

96.96 76.86

15. UNIT CAPACTTY FACTOR (Using MDC) 92.75 92.75 65.61

17. UNTT CAPACTTY FACTOR (Using Design MWe) 90.40 90.40 63.95

18. UNTT FORCED OUTAGE RATE 3.04 3.04 6.31

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

t

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP:

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

FORECAST ACHIEVED INTTIAL CRTTICALTTY INTTIAL ELECTRICTTY COMMERCIAL OPERATION j

TECHOP3\\NRC\\ MON'lHLY.RPT

d APPENDIX C OPERATING DATA REPORT DOCKET NO.

50 265 UNTT Two DATE February 7.1994 COMPLETTED BY Matt Benson TELEPIIONE (309) 654-2241 OPERATING STATUS 0000 010194

1. REPORTING PERIOD: 2400 013194 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY ALTTIIORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTII YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 159.40 159.40 144060.45

6. REACTOR RESERVE SHITrDOWN HOtT,tS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 131.20 131.20 140314.35

8. UNrr RESERVE SHUTDOWN HOURS

.0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 179521.90 179521.90 302%0483.b0

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 54563.00 54563.00 97364333.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 46718.00 46718.00 92189278.00

12. REACTOR SERVICE FACTOR 21.42 21.42 75.98

13. REACTOR AVAILABILTTY FACTOR 21.42 21.42 77.56

14. UNrr SERVICE FACTOR 17.63 17.63 74.01 i

15. UNrf AVAILABILTrY FACTOR 17.63 17.63 74.38

16. UNTT CAPACfrY FACTOR (Using MDC) 8.17 8.17 63.23

17. UNTT CAPACITY FACTOR (Using Design MWe) 7.96 7.96 61.63

18. UNTT FORCED OtTTAGE RATE 82.37 82.37 8.89

19. SHtTTDOWNS SCHEDULED OVER NEXT 6 MOffrHS (TYPE, DATE AND DURATION OF EACH):

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

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

FORECAST ACHIEVED INITIAL CRTTICALrrY INITIAL ELECTRICfrY COMMERCIAL OPERATION l.159 TIrHOP3\\NRC\\ MONTHLY.RI"r

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE February 1. 1994__

COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH January 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-4 17, 760 2.

591 18.

762 3.

721 19.

761 4.

700 20.

759 5.

761 21.

761 6.

765 22.

757 7.

764 23.

757 8.

765 24.

757 9.

762 25.

758 10.

763 26.

753 11.

748 27.

758 12.

571 28.

754 13.

757 29.

550 14.

762 30.

757 15.

758 31.

751 16.

759 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 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 1TfHOP3\\NRC\\MONntLY.RFr

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE February 1. 1994 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH January 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(HWe-Net) 1.

-8 17.

-8 2.

-8 18.

-8 3.

-8 19.

-8 4.

-8 20.

-8 5.

-8 21.

-8 6.

-8 22.

-8 7.

-8 23.

-8 8.

-8 24.

-8 9.

-8 25.

-8 10.

.-8 26.

50 11.

I 27.

123 12.

-8 28.

118 13.

-8 29.

349 14.

-8 30.

751

)

15.

-8 31, 758 16.

-8 INSTRUCTIONS l

On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearast whole megawatt.

These figures will be used to plot a graph for ec'h reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, tbare may be occasions when the daily average power level exceeds the 100% line (or I

the restricted power level line).

In such cases, the average daily unit power l

output sheet should be foetnoted to explain the apparent anomaly.

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1.16-8 TECilOPJ\\NRC\\ MONTHLY.RFT

{

4 APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Matt Benson DATE Februarv 7.

1994 REPORT MONTH January 1994 TELEPHONE 309-654-2241 SE k

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS EO.

DATE (HOURS)

REPORT 94-01 01-01-94 F

22.6 B

4 Exited forced maintenance outage.

9442 01-12-94 F

7.3 B

5 Imd drop for #2 stop valvewort 9443 01-29-94 7

20.6 B

5 Load drop to 7Me seal on condensate booster pump.

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APPENDIX D UNIT SNUTDOWUS AND POWER REDUCTIONS i

DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Matt Benson DATE February 1994 REPORT MONTH January 1994 TELEPHONE 309-654-2241 a

SEE E

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LICENSEE O

DURATION 8

EVENT CORRECTIVE ACTIONS / COMMENTS 20.

DATE (HOURS)

REPORT C4-01 0141-94 F

612.8 B

4 Continued forced maintenance outage.

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TEQ10P3\\NRC\\ MONTHLY.RPT

VI. UNIOVE REPORTING RE0VIREMENTS The following items are included in this report based on prior commitments to the commission:

A.

Main Steam Relief Valve Ooerations 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 1.,

its actuation.

i Unit: Two Date: January 26, 1994 l

Valve Actuated:

No. & Tyne of Actuation:

2-203-3A 1 Manual 2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual Plant Conditions: Reactor Pressure - 920 psig Description of Events: Normal surveillance testing. All tested satisfactory.

J B.

Control Rod Drive Scram Timina Data for Units One and Two

'l The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Controla Rod Drive Scram timing for the reporting period. All scram timing as performed with reactor prr :sure greater than 800 PSIG.

TECHOP3\\NRC\\ MONTHLY.RIT

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/94 TO 12/31/94 ll l

AVERAGE TIME IN SECONDS AT %

' MAX. TIME ll INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION NUMBER 5

20 50 l

90 Technical Specification 3.3.c.1 &

DATE OF RODS 0.375 1 0.900 2.00 3.5 7 sec.

3.3.C.2 (Averace Scram Insertion Timel I

01-27-94 1

l 0.31 0.69 1.45 2.53 H-1 U2 for Maintenance 2.53 01-29-94 1

0.33 0.73 1.51 2.58 M-10 U1 for Maintenance 4

2.58 01-29-94 177 0.32 0.69 1.46 2.56 H-3 U2 SEQ A & B for Tech Spec & Maintenance 2.92 I

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I VII.

REFUELING INFORMATION The following information about future reloads at Quad-Cities Station.was requested in a January 26, 1978, licensin1 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.

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TFrHOP3\\NRC\\ MONTHLY.RIT c.

3 Revision 2 l.

QUAD CITIES REFUELING October 1989 INFORMATION REQUEST-l 1.

Unit:

Q1 Reload:

12 Cycle: 13 i

2.

Scheduled date f.)r next refueling shutdown:

.3-12-94 3.

Scheduled date for restart following refueling:

7-2-94.

4.

Will refueling or resumption of operation thereafter require a Technica'1' Specification change or other license amendment:

j YES.

Safety Limit MCPR to be changed from 1.06 to 1.07 due to GE10 Fuel.

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

11-19-93

~

6.

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

160 GE10 Fuel Bundles will be loaded during Q1R13.

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l 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 sforage 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

- 'l b.

Planned increase in 11 censed storage:

0 I

9.

The projected date of the last refueling that can be discharged to the' i spent fuel pool assuming the present licensed capacity:2009 APPROVED 14/0395t,

'C).C.O.S.R.-

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QTP-300-532~

, Revision 2 QUAD CITIES REFUELING-October.1989-INFOsuMTION REQUEST 1.

Unit:

Q2 Reload:

_12 13 Cycle:

2.

Scheduled date for next refueling shutdown:

09-24-94 3.

Scheduled date for restart following refueling:

12-04-94 4.

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

YES - Safety limit MCPR to be changed from 1.06 to'1'.07 due to GE10 Fuel..

5.

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

5-13-94 6.

Important Ilconsing 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:

GE10 Fuel will be loaded duringQ2R13.

7.

The number of fuel assemblies.

~

Number of assemblies in core:

724 a.

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 1s-planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

'O 9.

The projected date of the last refueling that can be discharged;to the spent fuel pool assuming the present licensed capacity: 2009 4

APPROVED cfinai)

OCT 3 0 WW 14/0395t Q.C.O.S.R.

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