ML20058K243

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

ML20058K243
Person / Time
Site:	Quad Cities
Issue date:	11/30/1993
From:	Michael Benson, Scott A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-93-18, NUDOCS 9312150010
Download: ML20058K243 (21)

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Commonwealth Edison Quad Cities Nuclear Power Station  :

22710 206 Avenue North Cordova, Illinois 61242 w Telephone 309/654-2241 e AMS-93-18 l

i December 8, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk  ;

Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 ,

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Monthly Performance Report NRC Docket Nos. 50-254 and 50-265

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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 November 1993. i Respectfully, [

COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION F

Anthony M. Scott

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System Engineering Supervisor l i

AMS/dak Enclosure cc J. Martin, Regional Administrator  ;

T. Taylor, Senior Resident Inspector '

150n3; SA TECHOP3*WRC\ MONTHLY.RPT 9312150010 DR 931130 ADDCM 05000254 n PDR j

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I QUAD-CITIES NUCLEAR POWER STATION l i

UNITS 1 AND 2 l 1

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MONTHLY PERFORMANCE REPORT November 1993  !

I COMMONWEALTH EDISON COMPANY  ;

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l IOWA-ILLINOIS GAS & ELECTRIC COMPANY 4

NRC DOCKET NOS. 50-254 AND 50-265 .

i LICENSE NOS DPR-29 AND DPR-30 l I

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TFrilOP3 RRCMONTHLY.RFT l a

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t TABLE OF CONTENTS 1

I. Introduction l I l

[ II. Summary of Operating Experience ,

A. Unit One B. Unit Two L

III. Plant or Procedure Changes, Tests, Experiments, and Safety Related l Maintenance (

A. Amendments to Facility License or Technical Specifications [

B. F:cility or Procedure Changes Requiring NRC Approval i l C. Tests and Experiments Requiring NRC Approval  ;

D. Corrective Maintenance of Safety Related Equipment l i

IV. Licensee Event Reports ,

.. j V. Data Tabulations

-f A. Operating Data Report '

B. Average Daily Unit Power Level '

C. Unit Shutdowns and Power Reductions 1

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VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations  !

B. Control Rod Drive Scram Timing Data VII. Refueling Information l I

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VIII. . Glossary

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.i I. INTRODUCTION i

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

Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply f

Systems are General Electric Company Boiling Water Reactors. The l l

Architect / Engineer was Sargent & Lundy, Incorporated, and the primary l

construction contractor was United Engineers & Constructors. The Mississippi l

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, ,

respectivelys pursuant to Docket Numbers 50-254 and 50-265. The date of I

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.

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SUMMARY

OF OPERATING EXPERIENCE A. Unit One i.

Quad Cities Unit One began the month of November 1993 at full power, f On November 5, Unit One was reducing load in preparation for a drywell entry, due to high temperature readings on the "A" motor generator set. Prior to entry, it was determined that the temperature recoider f was faulty and the load drop was reversed at 556 MWe.

On November 6, Unit One entered a planned maintenance outage. The generator was taken off line at 01:05 hours and the unit was manually  !

scrammed at 02:24 hours. l I

Unit One exited the planned maintenance outage on November 29 when the reactor was made critical at 20:40 hours. At 01:17 hours on November )

30 a manual SCRAM was inserted when a valve leak was detected on the Reactor Vessel Level Instrument System.

B. Unit Two Quad Cities Unit Two began the month of November 1993 at full power and remained on line for the entire month. Six load drops were performed for the System Power Supply Office 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 Specifications ,

There were no Amendments to the Facility License or Technical Specifications for the reporting period. ,

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

C. Tests'and Experiments Recuirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the ,

reporting period.

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D. Corrective Maintenance of Safety Related Eculement The following represents a tabular summary of t5e major safety related maintenance performed on Units One and Two during the reporting ,

period. This summary includes the following: Work Request Numbers, i Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation,.and Action Taken to Prevent I Repetition.

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, b UNIT 1 & 1/2 MAINTENANCE

SUMMARY

lNWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 208753 1600 1-1630-Al Investigate / repair Replaced thermocouple.

torus water temperature indication.

009048 1000 1-1001-209C Repair / replace broken Installed new handwheel.

handwheel on 1C RHR pump suction shutoff valve.

Q09919 263 1-263-111C Repair / replace reactor Installed new pre-pressurization low pressure switch. valve.

Q10360 1000 1-1010 Repair 1A RHRSW room Found line plugged with scale, cooler 3/8" drain line. dirt, and mud from the river.

Unplugged line.

Q10550 2500 1-2599-2A Repair / replace 1A ACAD Replaced solenoid with a new drywell discharge valve one, solenoid.

Q10956 6700 1-6704-3 Repair aux switch Replaced stop bolts with cap linkage at bus 14, screws; flat washers with like cubicle 3. parts to remove play in the linkage; and one screw with longer screw.

Q11022 300 1-305-126- Repair CRD. Rod Adjusted seating pressure and

1415 drifted from position spring tension on scram inlet

00. valve.

Q11151 300 -305-127- Repair CRD scram inlet Replaced. diaphragm.

3447 valve. Lots of air is blowing from the diaphragm.

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4 Q11425 1600 1-1640-200B Investigate / repair Removed an analog / digital torus temperature circuit board from the Unit 2 division B recorder. torus temperature recorder and i

installed it on the Unit'1 recorder. Calibrated point #9.

i Q11477 5700 1/2-5741- Repair control room B Found resistance temperature

=

317 HVAC. Failed mod test. detector wired' incorrectly.

Rewired detector.

Q11504 5700 1/2-5741- Replace broken handle- Replaced switch handle.

316B on control room B HVAC switch.

087227 8300 1-8300-1 Change location of wire Found wire insulation brittle on #1 125VDC battery and conductor visible. Replaced charger. terminal ring.

Q99496 8350 1-8350 Replace 250VDC battery Replaced switch like for like.

selector switch. Reused original face plate. ,

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UNIT 2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q08082 756 2-756- Investigate / repair LPRM Cleaned LPRM card connections08-17C downscale alarm not and reinstalled card. Verified working. alarm was operable.

Q09783 30 2-0030 Repair concrete wall Found concrete around east side near a support for the of horizontal beam at ceiling new U2 RHRSW line. that supports U2 RHRSW line had pulled loose. Repaired wall section with new concrete and grout.

Q10093 1600 2-1640-200B Repair fan on torus Replaced fan with a new fan water temperature assembly.

recorder.

Q10441 6600 2-6600-1 Repair temperature Replaced meter assembly with a indicator for diesel new one.

generator cylinder.

Q10541 1100 2-1100 Troubleshoot / repair Adjusted circuits to maintain SBLC heaters, temperature at 130 degrees.

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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 j 6.6.B.1 and 6.6.B.2 of the Technical Specifications. j l

UNIT 1 l Licensee Event Egoort Number Date Title of occurrence ,93-020 11-11-93 Loss of Shutdown Cooling 4 l

i 93-022 11-30-93 Rx Vessel Level Instruments '

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Licensee Event Report Number Date Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

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P V. pA_TA TABULATIONS The following data tabulations are presented in this reports i A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions r i

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l APPENDIX C 6

OPERATING DATA REPORT DOChET NO. 50-254 UNIT One f DATE December 7,  ;

1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 i

OPERATING STATUS i

0000 110193

1. REPORTING PERIOD: 2400 113093 GROSS HOURS IN REPORTING PERIOD: 720 ,,

2. CURRENTLY AUTilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 ,

DESIGN ELECTRICAL RATING (MWe-NET): 789 1

3. POWER LEVELTO WlilCH RESTRICTED (IF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

• THIS MONTH YR TO DATE CUMULATIVE  ;

5. NUMBER OF llOURS REACTOR WAS CRITICAL 127.00 6621.20 149382.10

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 121.10 6549.90 144941.50

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 283837.60 15341130.90 312922954.70

10. GROSS ELECTRICAL ENERGY GENERATED (MWlf) 92605.00 5025051.00 101444141.00

11. NCr ELECTRICAL ENERGY GENERATED (MWH) 83957.00 4802579.00 95678091.00

12. REACTOR SERVICE FACTOR 17.64 82.60 78.76

13. REACTOR AVAILABILrrY FACTOR '

17.64 82.60 80.56

14. UNIT SERVICE FACTOR 16.82 81.71 76.42

15. UNTT AVAILABILrrY FACTOR 16.82 bl .71 76.90

16. UNIT CAPACITY FACTOR (Using MDC) 15.16 77.91 65.60

17. UNTr CAPArrrY FACTOR (Using Design MWe) 14.78 75.93 63.93  ;

I8. UNrr FORCED OUTAGE RATE 0.00 11.69 6.10 ,

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

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

21. UNrFS IN TEST STATUS (PRIOR TO COMMERCIAL OPER ATION): ,

FORECAST ACHIEVED INITIAL CRTTICALITY

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INrrlAL ELECTRICrTY .j COMMERCIAL OPERATION 1.1&9 TPfHOP3WRCMONDiLY.RPT j

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OPERATING DATA REIORT DOCKET No. 50 265

UNIT Two DATE December 7, 1993 COMPLETED BY Man Benson .l TELEPilONE (309) 654-2241 ,

OPERATING STATUS 0000 110193

1. REPORTING PERIOD: 2400 !!3093 GROSS HOURS IN REIORTING PERIOD: 720  !

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

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

4. REASONS FOR RESTRICTION (IF ANY):

Tills MONTil YR TO DATE CUMULATIVE  !

5. NUMBER OF 110URS REACTOR WAS CRrrICAL 720.00 4t45.50 143860.75

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

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7. fiOURS GENERATOR ON LINE 720.00 4501.40 140142.85

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERM AL ENERGY GENERATED (MWH) 1752000.80 10021142.80 302684552.00

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 564679.00 3252724.00 97277985.00

11. NET ELECTRICAL ENEROY GENERATED (MWH) 541898.00 3087247.00 92117990.00

12. REACTOR SERVICE FACTOR 100.00 58.45 76.48  ;

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13. REACTOR AVAILABILITY FACTOR 100.00 58.45 78 06

14. UNrf SERVICE FACTOR 100.00 56.16 74.50

15. UNIT AVAILABILITY FACTOR 100.00 56.16 74.87

16. US CAPACITY FACTOR (Using MDC) 97.87 50.08 63.68  ;

17. UNTT CAPACITY FACTOR (Using Design MWe) 95.39 48.81 62.07  !

18. UNIT FORCED OUTAGE RATE - 0.00 25.66 8,49 l

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

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

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

FORECAST ACHIEVED

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l APPENDIX B l AVERAGE DAILY UNIT POWER LEVEL i DOCKET NO 50-254- l UNIT' One  ;

DATE ppcember 7 1993 .[

i COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH November 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) j

1. 764 17. - 8 j

2. 762- 18. - 8 l

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3. 759 19. - 8

4. 761 20. - 8

5. 646 21. - 8 'j

6. - 3 22. - 8 i

7 - 8 23. - 8 l t

8. - 7 24. - 8  ;

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10. - 8 26. - 8 i

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16. --8 -j INSTRUCTIONS j On this. form, list the average daily unit power level in MWe-Net for each day l in the reporting month. Compute to the nearest whole megawatt. These figures l 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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N APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 l UNIT Two-  !

DATE December 7. 1993 {

COMPLETED BY Matt Benson  !

TELEPHONE (309) 654-2241 i MONTH November 1993 _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  ;

(MWe-Net) (MWe-Net)

1. 766 17 . __. 731 l

2. 766 18. 758

3. 765 19. 761 1

4. 723 20. 759 .

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5. 757 21. 718 -i

6. 757 22. 755 t

7. 760 23. 754

8. 761 24. '755 q

9. 760 25. 751

10. 761 26. 732 l

11. 761 27. -756 i

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12. 762 28. 730 '!

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13. 762 29. 755 ,

14, 714 30. 755  !

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On this form, list the average daily unit power level in MWe-Net for each day j 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 D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NJEE One COMPLETED BY Matt Benson DATE November 7. 1993 REPORT MONTH Noverr.ber 1993 TELEPHONE 309-654-2241 _  ;

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$W$ LICENSEE O DURATION EVENT CORRECTIVE ACTIONS /COFMENTS NO. DATE (HOURS) REPORT 03 55 11 05-93 F 6.5 B 5 ------ - --- - --

t/md Drop for MG Set liigh Temperature 93-56 11C691 S 595.9 B 2 -- -- - ---

Maintenance Outare 2

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APPENDIX D  ;

UNIT SHUTDOWNS AND POWER REDUCTIONS i i

DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Matt Berr9n DATE Decebmer 7. 199L REPORT MONTH November. 1993 TELEPHONE 309-654-224L h

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MO H f4 3 $ MO MO kO eU N m DURATION

$x$ m LICENSEE u l

@ EVENT CORRECTIVE ACTIONS / COMMENTS  !

NO. DATE { HOURS) REPORT  !

I None  !

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1 VI. UNIOUE REPORTING REOUIREMENTS TEOlOP3,NRCalONDiLY.RPT i

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'The-following items are included in this report based on prior commitments to I the commission: .,r t

A. Main Steam Relief Valve Ooerations l

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I Relief 7alve 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 circumrtances resulting in its  ;

actuation.  !

i Unit. One l Date. November 6, 1993 .

a V lve Actuated: No. & Tyne of Actuation:

h 1-203-3A 1 Manual .}

1-203-3B 1 Manual i 1-203-3C 1 Manual l 1-203-3D 1 Manual i i

1-203-3E 1 Manual Plant Conditions: Reactor Pressure - 920 psig I

DescriDtion of Events: Routine Surveillance testing on Shutdown for i Q1M09.  :

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D. Control Rod Drive Scram Timina Data for Ur.its One and Two l There was no Control Rod Drive scram timing data for Units One and Two for  !

the reporting period. l l

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l VII. REFUELING INFORMATION  :,

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i The following infonnation about future reloads at Quad-Cities Station was j requested in a January 26, 1978, licensing memorandum (78-24) from D. E. j O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC j Request for Refueling Information", dated January 10, 1978.  !

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QTP 300-532 l

, Revision 2  !

QUAD CITIES REFUELfMG October 1989  ;

INFORMATION REQUEST i

1. Unit: Q1 Reload: 12 r

._ Cycle: 13

2. Scheduled date for next refueling shutdown: 3-12-94  !

3.

Scheduled date for restart following refueling: 6-13-94 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.

5.

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

11-19-93 i

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:

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

8. 1 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 ,l 9.

The projected date of the last refueling that can be discharged to the' '

spent fuel pool assuming the present Ilcensed capacity: 2009 APPROVED , -

(final) 14/0395t OCT 3 01989 O.C.O.S.R.

, QTP 300-532

- Revision 2 WAD CITIES REFUELING October 1989 INFORMATION REWEST

1. Unit: Q2 Reload: 12 Cycle: 13

2. Scheduled date for next refueling shutdown: 09-24-94 3.

Scheduled date for restart following refueling: 12-04-94 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 Ilcensing action and supporting information:

5-13-94 l 6.

l Important Itcensing 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 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 licensed storage: 0 9.

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

14/0395t .

Q.C.O.S.R.

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

• 9 ACAD/ CAM - Atmospheric Containment Atmospheric [

Dilution / Containment Atmospheric Monitoring .;

ANSI - American National Standards Institute l APRM

- Average Power Range Monitor ATWS - Anticipated Transient Without Scram j BWR - Boiling Water Reactor  !

CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations Facility l GSEP - Generating Stations Emergency Plan  !

HEPA - High-Efficiency Particulate Filter j 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 j LPRM - Local Power Range Monitor ,

MAPLHGR - Maximum Average Planar Linear Heat Generation Rate -;

MCPR - Minimum Critical Power Ratio _

MFLCPR - Maximum Praction Limiting Critical Power Ratio

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MPC - Maximum Permissible Concentration ,

MSIV -

Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health _

i PCI - Primary Containment Isolation l

PCIOMR - Preconditioning Interim Operating Management Recommendations ~

RBCCW - Reactor Building Closed Cooling Water System  ;

RBM - 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 . 1

-SDC - Shutdown Cooling Mode of RHRS i SDV - Scram Discharge Volume i SRM - Source Range Monitor l TBCCW - Turbine Building Closed Cooling Water System '

TIP - Traversing Incore Probe TSC -

Technical Support Center TICIOPl.NRcAK)NTHLY R.PT

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