ML20069J413

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Monthly Operating Repts for May 1994 for Quad-Cities Nuclear Station Units 1 & 2
ML20069J413
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 05/31/1994
From: Michael Benson, Moore K, Scott A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-16, NUDOCS 9406140362
Download: ML20069J413 (23)
v • d • e


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Commonwealth Edison Quad Cities Nuclear Pc. < tr Station i 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654 2241 AMS-94-16

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++har 7, 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 50-261 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 May 1994.

Respectfully, Comed Quad-Cities Nuclear Power Station f/ViGYY Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure ec: J. Martin, Regional Administrator C. Miller, Senior Resident Inspector nruornsucatosuux Riv p i 9406140362 940531 0' I FDR ADOCK 05000254 V

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QUAD-CITIES NUCLEAR POWER STATION j 4

UNITS 1 AND 2 i

MONTHLY PERFORMANCE REPORT l l

May 1994 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY I NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DFy-30  ;

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a TABLE OF CONTENTS I. Introduction II. Summary af 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 j V. Data Tabulations t 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 1

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I. INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable capacity of 769 MWe Net, located in Cc -dova , Illinois. The Station is jointly owned by Commonwealth Edison 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 f f

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 Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One spent the entire month of May 1994 shutdown in Refuel Outage QlR13. The scheduled startup for Unit One is July 2, 1994.

B. Unit Two Quad Cities Unit Two began the month of May 1994 at full capable load and remained on line through out the month.

On May 21, Unit 2 dropped load to 200 MWe for a drywell entry to investigate leakage. Steam leakage was identified coming from HPCI valve. The valve was electrically back seated to reduce leakage and full power was restored.

A few other load drops were performed for administrative reasons but none caused the average daily unit power level to drop by 20% or greater, l

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III. ELANT OR PROCEDURE CHANGES, TESTS. EXPERIMENTS, hND SAFETY RELATED MAINTENANCE A. hmendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B. Eacility or Procedure Chances Reouirino NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Experiments Recuirino NRC ADoroval 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 Unita 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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UNIT 1 & 1/2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q04172 3900 1-3999-98 Repair packing leak on 1A RHR Replaced packing.

room cooler inlet valve.

Packing cannot be adjusted.

Q10326 0020 1-0020 Repair loose conduit going to Removed old conduit and 1-1401A the 1A core spray pump motor, replaced with new, flexible conduit.

Q10475 0261 1-0261-34A Replace 2 bolts missing from DP Replaced bolts.

switch on jet pump riser header.

Q10705 4600 1-4615 Repair air leak on diesel Cleaned union and generator air start motor air resealed pipe.

strainer.

Q10746 8350 1-8350 Repair hardware problems with Replaced battery 250 VDC battery cells 81 and connectors and various

82. other hardware as necessary.

Q11009 0750 1-0750-7H Repair knob on IRM 18 chassis. Replaced panel fastener.

Q11419 1600 1-1601-59 Repair actuator to nitrogen Installed new fittings makeup to drywell stop valve. and tubing.

011515 6700 1-670s-L3 Replace damaged fuse holder in Replaced fuse block.

bus 14, cubicle 13-main feed from transformer 11.

Q12432 3900 1-3999-218 Repair diesel generator cubicle Replaced globe valve.

cooler vent valve. Valve was observed leaking water past its seat.

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q13108 5700 1-5741-130 Investigate / repair drywell Tightened terminal 1-5741-43B environs temperature recorder. screws for point 8.

Indication read normally and alarm cleared.

Q14501 0750 1-0750-7B Repair mode switch on IRM 15 Tightened nut on chassis chassis. and verified proper operation.

Q14669 7200 1-7200-1C Repair Bus 19 cubicle 1C door. Bent door and latch so door could be secured.

Q15433 1600 1-1600-X7B Repair main steam penetration Removed, adjusted, and bellows. Bellows leaked reinstalled bellows cutside the normal range during cover.

testing.

Q15812 7800 1-78192-B1 Replace molded case breaker in Replaced breaker.

MCC 19-2 cubicle Bl.

Q15922 0590 1-0590-109B Replace broken coil on SCRAM Found separation piece relay channel B. of coil broken.

Replaced coil.

Q15923 0590 1-0590-108B Replace aux contact on SCRAM Found aux contacts did relay channel B. not move freely.

Replaced aux contacts.

-C16099 670C 1-6706-1 Replace-secondary disconnects Found broken secondary on bus 14-1 cubicle 1 bus tie disconnect. Replaced to bus 24-1. with new secondary disconnect.

Q16100 6700 1-6706-1 Replace trip /close switch on Found trip /close switch bus 14-1 cubicle 1 bus tie to would not spring return.

bus 24-1. Cleaned switch until switch worked properly.

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NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q16245 0220 1-0220-44 Replace the top cover gasket on Replaced limit switch the 1B recirc loop stop valve gasket.

limit switch. <

Q16297 1700 1-1705-16B Investigate / repair 1B fuel pool Replaced indicator trip radiation monitor spiking hi. unit and sensor / converter.

Q16348 7300 1/2-7300- Repair charging motor brush cap Installed brush cap.

S001 on ACB 480 VAC breaker.

Q16355 6700 1-6704-11 Adjust / repair bus 14 cubicle 11 Adjusted contact.

fuse holder contact.

Q16393 7800 1-78191-C5 Replace contactor on MCC 19-1 Replaced cracked cubicle CS, DG fuel oil contactor with a new transfer pump normal feed. one.

Q76824 6700 1-6706 Replace cracked fuse holder on Installed new fuse Bus 14-1 cubicle 5. holder.

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UNIT 2 MAINTENANCE SUFFARY NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q15720 8700 2-1640-11 Repair nitrogen makeup Found 2-1640-11 2-8741-30 pressure control valve. Valve controller amplifier low 2-8799-20 does not respond properly in limit potentiometer auto. intermittently open.

Replaced potentiometer and proportional amplifier.

Q16256 8700 2-8740-11 Troubleshoot nitrogen flow Cleaned potentiometers 2-8741-30 control system. and reinstalled 2-1640-11 pressure controller.

Q16502 2300 2-2301-4 Electrically backseat HPCI Backanated valve per upstream main steam stop valve interim procedure IP-to reduce steam leakage. 721.

IV. LICENSEE EVENT REPORTS l l

i 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  ;

j 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 Report Number Date Title of occurrence j There were no Licensee Event Reports for Unit 1 for this reporting period.

UNIT 2 Licensee Event Report Number p_a.t e Title of occurrence 94-09 5-22-94 DW Interlock Door Failure.

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V. DATA TABULATIONE The following data tabulations are presented in this report ,

l A. Operating Data Report i l

B. Average Daily Unit Power Level l l

C. Unit Shutdowns and Power Reductions t

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APPENDIX C f OPERATING DATA REPORT DOCKLT NO. 50-254 UNIT One DATE June 7,1994 COMPLETED BY Kristal Moore TELEPIIONE (309) 654 2241 OPERATING STATUS 0000 050194

1. REPORTING PERIOD: 2400 053194 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DMIGN ELECTRICAL RATING (MWo-NET): 789
3. POWER LEVEL TO WlilCH RESTRICTED (IF ANY)(MWs-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTII YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRITICAL 0.00 1706.00 151487.30
6. REACTOR RESERVE SIIUTDOWN llOURS 0.00 0.00 3421.90
7. IlOURS GENERATOR ON LINE 0.00 1682.90 146979.20
8. UNTT RESERVE SilUTDOWN HOURS 0.00 0.00 909.20
9. GROSS TilERMAL ENERGY GENERATED (MWH) 0.00 3865794.10 317558981.30
10. GROSS ELECTRICAL ENERGY GENERATED (MWil) 0.00 1265145.00 102963264.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 1206708.00 97124706.00
12. REACTOR SERVICE FACTOR 0.00 47.09 78.07
13. REACTOR AVAILABILTTY FACTOR 0.00 47.09 79.83
14. UNfr SERVICE FAcrOR 0.00 46.45 75.75 i
15. UNIT AVAILABILrrY FACTOR O.00 46.45 76.22
16. UNrr CAPACfrY FACTOR (Uning MDC) 0.00 43.31 65.09
17. UNIT CAPACrrY FACTOR (Uning Design MWe) 0.00 42.21 63.44
18. UNIT I ORCED OUTAGE RATE 0.00 1.33 6.25
19. SliUTDOWNS SCIIEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACil):
20. IF SHUTDOWN AT END OF REPORT PalOD < ESTIMATED DATE OF STARTUP: 7-2-94
21. UNfr$ IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INrf1AL CRrrICAIJrY INTTIAL ELECTRICfrY COMMERCIAL OPERATION 1.1 +9 TirilOIS\NRCtMONT}iLY.RPT

4 APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNrr Two DATE June 7,1994 COMPLLTED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 050194

1. REPORTING PERIOD: 2400 053194 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AltrilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACirY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVEL TO WlilCII RESTRICTED (IF ANY) (MWo-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMUI.ATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 744.00 3038.40 146939.45
6. REACTOR RESERVE SliUTDOWN HOURS 0.00 0.00 2985.80
7. IIOURS GENERATOR ON LINE 744.00 3010.20 143193.35
8. UNrr RESERVE SHUTDOWN liOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 1771947.50 7074492.40 309855454.30
10. GROSS ELECTRICAL ENERGY GENERATED (MWil) 573451.00 2296587.00 996 % 357.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 55331.00 1705546.00 93848106.00
12. REACIOR SERVICE FACTOR 100.00 83.86 76.34
13. REACTOR AVAILABILrrY FACTOR 100.00 83.86 77.89
14. UNIT SERVICE FACIOR 100.00 83.09 74.40
15. UNrr AVAILABILITY FACTOR 100.00 83.09 74.76
16. UNIT CAPACrrY FACTOR (Using MDC) 9.67 61.22 63.40
17. UNrr CAPACITY FACTOR (Uning Design MWe) 9.43 59.66 61.80
18. UNrr FORCED OUTAGE RATE 0.00 16.91 8.73
19. SlIUTDOWNS SCHEDULED OVER NEXT 6 Mobtrils (TYPE, DATE, AND DURATION OF EACH):
20. IF SilUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STI.RTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY ,

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COMMERCIAL OPERATION

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE June 7. 1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH May 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. - 7 17. - 8
2. - 7 18. - 8
3. - 7 19. - 8
4. - 7 20. - 8
5. - 7 21. - 8
6. - 7 22. - 8
7. - 7 23. - 8
8. - 7 24. - 8
9. - 7 25. - 8
10. - 7 26. - 8
11. - 8 27. - 8
12. - 8 28. - 8
13. - 8 29. - 8
14. - 8 30. - 8
15. - 8 31. - 8
16. - 8 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.

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL ,

DOCKET NO 50-265 UNIT Two DATE June 7. 1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH May 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 766 17. 761
2. 765 18, 758
3. 763 19. 757
4. 764 20. 758 5, 764 21. 743
6. 763 22, 355
7. 757 23. 749
8. 764 24. 754
9. 763 25. 753
10. 762 26. 756
11. 761 27. 756
12. 761 28. 757
13. 763 29. 729
14. 718 30, 750
15. 762 31, 747 16, 762 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 exceedc 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.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Matt Benson DATE June 7, 1994 REPORT MONTH May 1994 TELEPHONE 309-654-2241 M

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$ $ LICENSEE $

DURATION @ EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 94 04 54)i-94 S 744.0 C 4 ---------- --- ---- Continued Refuel Outage Q1R13 I

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS l DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Matt Benson 1

DATE June 7, 1994 REPORT MONTH May 1994 TELEPHONE 309-654-2241 I l M 1

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$M$ LICENSEE O DURATION @ EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 944A 5-21-94 F 16.2 A 5 --------- --- ---- lead drop for drywell entry to investigate leakage.

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VI. UNIOUE REPORTING REOUIREMENTS The following items are included in this report based on prior commitments to the commissions i

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

B. Control Rod Drive Scram Timino Data for Units One and Two There was no Control Rod Drive scram timing data for Units one and Two for the reporting period.

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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.

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QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q1 Reload: 12 CycIa: 13
2. Scheduled date for next refueling shutdown: 3-13-94
3. Scheduled date for restart following refueling: 7-2-94
4. Will refueling or resumption of operation thereafter require a Technica'l' Specification change or other license amendment: '

YES. Safety Limit MCPR to be changed from 1.06 to 1.07 due to l

GE10 Fuel.

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

11-19-93 4

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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:

144 GE10 Fuel Bundles will be loaded during Q1R13.

7. The number of fuel assemblies.
a. Number of assemblies in core: 0
b. Number of assemblies in spent fuel pool: 2441
8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capactty that has been requested or is planned in number of fuel assembiles: .'
a. Licensed storage capacity for spent fuel: 3657

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b. Planned increase in licensed storage. 0 2 i

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The projected date of the last refueling that can be discharged to the' t spent fuel pool assuming the present licensed capacity: 2006 APPROVED ,

crinal) 14/0395t OCT 3 085 l c).c.o.s.R. t

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

1. Unit: 02 Reload: 12 Cycle: 13
2. Scheduled date for next refueling shutdown: 1-29-95
3. Scheduled date for restart following refueling: 4-9-95
4. Will refueling or resumption of operation thereafter require a Technical Speelfication change or other license amendment:

YES - Safety limit MCPR to be changed from 1.06 to 1.07 due to GE10 Fuel.

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

7-28-94

6. Important liceming 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:

144 GE10 fuel bundles will be loaded during Q2R13.

7. The number of fuel assemb11es.
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 spent fuel pool assuming the present licensed capacity: 2006~

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APPROVED 14/0395t (final)

W30N Q.C.O.S.R.

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P n-VIII. GLOSSARY 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 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 - Ineerv'ce 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 RBM - Rod Block Monitor 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 Volume SRM - Source Range Monitor l TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center 11 CHOL %NRC\ MON 1HLY.RIT

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