ML20065S182

Monthly Operating Repts for Apr 1994 for Quad Cities Nuclear Station Units 1 & 2

ML20065S182
Person / Time
Site:	Quad Cities
Issue date:	04/30/1994
From:	Michael Benson, Scott A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-12, NUDOCS 9405170177
Download: ML20065S182 (23)

Text

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Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 AMS-94-12 May 2, 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 S';dJECT: 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 April 1994.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLZAR POWER STATION

>A , , ev Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc J. Martin, Regional Administrator T. Taylor, Senior Resident Inspector

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J 9405170177 940430 PDR ADOCK 05000254 R PDR

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 1 MONTHLY PERFORMANCE REPORT  ;

I April 1994 I l

COMMONWEALTH EDISON COMPANY l

AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY

'l NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 nnforswacwobrD{LY.RFT

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e 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 A. Amendnents to Facility License or Technical Specifications B. Facility or Procedure Changes kequiring 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 ramonwnouornn.v.arr l l

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. . s I. INTRODUCTION 1

Quad-cities Nuclear Power Station is composed of two Boiling Water 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 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 begar. on February 18, 1973 for Unit One and March 10, 1973 for unit Two.

I This report was compiled by Matt Denson and Debra Kelley, telephone teamber 309-654-2241, extensions 2995 and 2240.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad cities Unit One spent the entire month of April 1994 shutdown in Refuel Outage Q1R13. The scheduled startup for Unit One is July 4, 1994.

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

On April 22, Unit 2 dropped load to 700 MWe for turbine stop valve testing. Main transformer trouble was indicated on April 23 when the oil temperature rose due to cooling fans tripping off. Load was reduced to 200 MWe while operating searched for the cause. A shorted relay was repaired and full capable load was restored.

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

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III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Soecifications Technical Specification Amendment No. 144 was issued on March 08, 1994 to Facility Operating License DPR-29 and Amendment No. 140 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments dele?.e the requireuents for demonstrating the operability of redundant equipment when emergency core cooling system equipment is found to be inoperable, or made inoperable for maintenance. The changes are consistent with the guidance provided by the NRC staff in Generic Letter 93-05, dated September 27, 1993.

B. Facility or Procedure Chances Recuirino N3C Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Experiments Recuirino NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Eculoment 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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4 UNIT 1 & 1/2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 002759 901-3 1-0901-3 Repair / replace broken Replaced terminal block.

fuse holder in 901-3 panel.

Q02800 901-8 1-0901-8 Repair / replace Replaced 3 terminal blocks.

terminal blocks in 901-8 panel.

Q04582 901-32 1-0901-32 Replace various Replaced 11 cracked covers.

-33 cracked HFA relay

-39 covers.

-47 1-6705-2 Q10065 0263 1-0263 Troubleshoot / repair Cleaned dust buildup on the west ATWS topaz inverter inverter filter.

malfunction.

Q11570 1300 1-1360-9A, Repair test taps on Replaced test taps on all four B,C,D RCIC main steam switches.

pressure switches.

Q12669 1000 1-1001-70B Repair / replace 1B RHR Installed new pressure indicator.

pump suction pressure gauge due to failed ca]ibration test.

Q13755 6600 1-6600-1 Repair / replace diesel Installed new temperature generator cylinder indicator.

temperature indicator.

Q14250 6700 1-6706-2 Repair sticking door Lubricated door handle latching which caused a relay mechanism.

to pick up and lock out the 1B core spray pump.

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q14523 0010 1/2-0010 Repair / certify Found one instrument out of miscellaneous calibration. Calibrated instruments. instrument.

Q15554 1300 1-1301-17 Replace severely Replaced cable.

cracked cable on main steam to RCIC downstream stop valve limitorque.

Q15585 6700 1-6705-3 Install missing jumper Installed jumper.

on 1A core spray pump breaker.

Q15947 7200 1-7200-6C Repair / replace feed to Replaced breaker programmer.

MCC 19-4 breaker.

Breaker did not trip correctly.

Q94060 2400 1-2406A Repair H202 continuous Adjusted potentiometers, cleaned air monitor recorder. slidewire and slidebar, lubricated bearings and recalibrated the blue pen.

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UNIT 2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 009063 0300 2-0305-126 Adjust limit switches Realigned adjusting rods.

for various scram inlet valves.

Q10214 8350 2-8350 Replace sheared bolts Installed new bolts. "

on 250VDC ground recorder.

Q12655 2500 2-2501 Investigate / repair ACAD Recalibrated PS 2-2540-20 and PS air compressor failing 2-2540-21 to new setpoint per to shut off at 50 psig, setpoint change 940061.

Q14193 0300 2-0305-126- Investigate / repair Adjusted scram outlet valve 2639 scram inlet valve. Rod limit switch. Changed length of stuck past 00. stem by 1/32':.

Q15316 1000 2-1053-H Replace test tap on 2C Replaced test tap.

RHR pump discharge pressure switch.

Q15474 0756 2-0756-6 Troubleshoot / repair Cleaned edge connectors on all APRM #6 Hi-Hi 1/2 cards and modules. Ran I/V scram. curves on LPRM's for APRM #6.

Performed QIS 3.2.

Q15559 0020 2-u020B-RHR Repair Droken latch on Installed door latch and 2B RHR room watertight lubricated door.

door.

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q15993 0020 2-0020-176 Repair broken window on Installed new window and sealed 3rd floor reactor with silicone.

building interlock door.

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i 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 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

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

UNIT 2 Licensee Event Report Numbeg Date Title of occurrence 94-07 4-8-94 2B RER Room Cooler INOP with 1/2 DG INOP.

94-08 4-17-94 Recirc Sample Valves 220-44 & 45 failed to close, i

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V. DATA TABULATIONS i

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i The following data tabulations are presented in this report: )

A. Operating Data Report i

l B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions

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TFfHOP3WRC\ MONTHLY.BFr

1 APPENDIX C OPERATING DATA REPORT DOCKirr NO. 50-254 UNTT Orm DATE May 2,1994 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 OPERATING STATUS 0000 040194

1. REPORTING PERIOD: 2400 043094 GRO8S HOURS IN REPORTING PERIOD: 719

2. CURRENTLY AITTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NE'I): 789

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

4. REASONS FOR RESTRICrlON (IP ANY): _

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL 0.00 1706.00 151487.30

6. REACTOR RESERVE $1!UTDOWN llOURS 0.00 0.00 3421.90

7. IiOURS GENERATOR ON UNE 0.00 1682.90 146979.20

8. UNrr RESERVE SHITrDOWN llOURS 0.00 0.00 909.20

9. GROSS TIIERMAL ENEROY GENERATED (MWII) 0.00 3865794.10 317558981.30

10. GROSS ELECIRICAL ENEROY GENERATED (MWH) 0.00 1265145.00 102963264.00

11. NLT ELECTRICAL ENEROY GENERATED (MWH) 0.00 1206708.00 97124706.00 12, REACTOR SERVICE FACTOR 0.00 59.26 78.37

13. REACTOR AVAILABILrrY FAcrOR 0.00 59.26 80.14

14. UNrr SERVICE FACTOR 0.00 58.45 76.04

15. UNIT AVAILABILrrY FACTOR 0.00 58.45 76.51

16. UNTT CAPACirY FACTOR (Using MDC) 0.00 54.50 65.34

17. UNir CAPACfrY FACTOR (Using Design MWe) 0.00 53.12 63.68

18. UNrr FORCED OUTAGE RATE 0.00 1.33 6.25 ,

19. SlitTFDOWNS SCliEDULED OVER NErr 6 MONills (TYPE, DATE AND DURATION OF EAClf):

20. IF SillTfDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 7494

21. UNTFS IN TEST STATUS (PRIOR TO COMME 3.CIAL OPERATION):

FORECAST ACifILNED INTriAL CRTTICALrrY INTTIAL ELECTRICITY COMMERCIAL OPERATION 1.16-9 TIDIOP3\NRC\MOK!MLY.RFr

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APPENDIX C

(. PERATING DATA REIORT DOCKET NO. 50-265 UNIT Two DATE .May 2,1994 COMPIETED BY Matt Benscm TELEPHONE (309) 654-2241 OPERATING STATUS 0000 040194

1. REPORTING PERIOD: 2400 043094 GROSS HOURS IN REPORTING PERIOD: 719

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

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

4. REASONS FOR RES"Ilt1CTION (IF ANY):

I THIS MOVrH YR TO DATE CUMULATIVE 1

5. NUMBER OF llOURS REACTOR WAS CRITICAL 719.00 2294.40 146195.45

6. REACTOR RESERVE SliUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 719.00 2266.20 142449.35 1

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1718756.00 5302544.90 308083506.80 1

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 558207.00 1723136.00 99032906.00 l

11. NET ELECTRICAL ENERGY GENERATED (MWH) 538676.00 1650215.00 93792775.00

12. REACTOR SERVICE FACTOR 100.00 79.69 76.25 l l

13. REACTOR AVAILABILTTY FACTOR 100.00 79.69 77.81

14. UNTT SERVICE FACTOR 100.00 78.71 74.30

15. UNIT AVAILABILTTY FACTOR 100.00 78.71 74.66

16. UNTT CAPACTrY FACTOR (Using MDC) 97.43 74.54 63.61

17. UNTT CAPACTTY FACTOR (Using Design MWs) 94.96 72.65 62.00

18. UNTT FORCED OUTAGE RATE 0.00 21.29 8.77

19. SH1JrDOWNS SCllEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACil):

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

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

FORECAST ACHIEVED t INTrlAL CRTTICALTrY INTTIAL ELECTRICTTY C(fMMERCIAL OPERATION 1.149 11rHOPENRCaf0N11{LY.! PT

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE May 2. 1994 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH April 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. - 7

2. -8 18. -

7

3. -8 19. - 7

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. - 8

11. -8 27. - 7

12. -8 28. - 7 l

13. -7 29. -

8

14. -7 30. --7 I

15. -8 31.

16. -7 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 occacions when the daily average power level exceeds the 100% line (or the restricted power level line). In such casen, the average daily unit power I

output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TIOlOPMNRC\MONT111.Y.RIT

s APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE May 2. 1994 COMPLETED BY Matt Benson TELEPHONE f309) 654-2241 MONTH April 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 761 17. 765

2. 759 18. 763

3. 760 19. 763 4, 759 20. 762

5. 761 21. 764

6. 761 22. 759

7. 761 23. 654

8. 759 24. 605

9. 760 25, 760

10. 762 26. 754

11. 761 27. 672

12. 762 28. 750

13. 762 29. 763

14. 762 30. 765

15. 762 31.

16. 751 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. j l

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No.10-254 UNIT NAME One COMPLETED BY Matt Benson DATE tiav 6, 1994 REPORT MONTH April. 1994 TELEPHONE 309-654-2241 A 9 m = E x

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1. l $E LICENSEE 08 $8 8

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 9 4 /34 441-94 S 719.0 C 4 -------- - --- ---- Continued Refuel Outage QlR13 71rHOP3\NRC\MONTMLY,RPT

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-265 UNIT NAME Two COMPLETED BY Matt Benson DATE May 6, 1994 REPORT MONTH April 1994 TELEPHONE 309-654-2241 cr; m 2 00 g b I

e m a opd == m:

s, j $n 28 $8 DURATION

$$ LICENSEE EVENT 8

CORRECTIVE ACTIONS / COMMENTS l

NO. DATE (HOURS) REPORT  !

9403 4-22 94 S 6.0 B 5 --------- --- ---- Sicp Valve Testing.

94-.04 4-23-94 F 7.5 A 5 ------ -- --- ----

lead Dny fi>r less of Main Transformer Cooling, i

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e VI. UNIOUE REPORTING REOUIREMENTS The following items are includ in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Operations There were ao Main St9am Relief Valve Operations for the reporting period.

B. Eg.atrol 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 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, 110110P3\NRC\ MON 1ELY,RPT

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

1. Unit: Q1 Reload 12 Cycle: 13

2. Scheduled date for next refueling shutdown: 3-13-94

3. Scheduled date for restart following refueling: 7-2-94 1

4. Will refueling or resumption of operation thereafter require a Technica'1' i Specification change or other license 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 ifcensing action and supporting information: ,

11-19-93

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:

144 GE10 Fuel Bundles will be loaded during Q1R13.

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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  !

ary 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 ilcensed storage. 0 2 1

9. The projected date of the last refueling that can be discharged to thh t spent fuel pool assuming the present licensed capacity: 2006 APPROVED (final) 14/0395t 00T 3 01989 Q.C.O.S.R.

OTP 300-S32 Revisten 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 Specification change or other license 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:

7-28-94

6. Important Ilcensing 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. )

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7. The number of fuel assemblies.

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 11 censed 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 APPROVED i

(finaD 14/0395t OCI3 0 M CLC.O.S.R.

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 - Inservice Inspection LER - Licensee Event Report LLRT - Local Leak Rate Test l 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 4 NIOSH - National Institute for Occupational Safety and Health I PCI - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations ,

RBCCW - Reactor Building Closed Cooling Water System RBM - Rod Block Monitor j RCIC - Reactor Core Isolation Cooling System j I

RHRS - Residual Heat Removal System RPS - Reactor Protection System l RWM - Rod Worth Minimizer j SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RMRS j SDV - Scram Discharge Volume l SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center TirHOP3\NRC\ mon 111LY.RPT

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