ML20077S634

Monthly Operating Repts for Dec 1994 for Quad Cities Units 1 & 2

ML20077S634
Person / Time
Site:	Quad Cities
Issue date:	12/31/1994
From:	Aitken P, Moore K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PCA-95-003, PCA-95-3, NUDOCS 9501240183
Download: ML20077S634 (20)

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Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 PCA-95-003 January 9, 1995 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 December 1994.

Respectfully, Comed Quad-Cities Nuclear Power Station x 0-Paul C. Aitken System Engirieering Supervisor PCA/dak Enclosure cc: J. Martin, Regional Administrator C. Miller, Senior Resident Inspector i

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l QUAD-CITIES NUCLEAR POWER STATION l UNITS 1 AND 2 E

MONTHLY PERFORMANCE REPORT December 1994 COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TDCMOP3\NRCMtON1HLY.Rrf a

1 TABLE OF CONTENTS

1. Introduction II. Summary of Operating Experience i

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 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 E

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I 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 -

Cordova, Illinois. The Station is jointly owned by Commonwealth Edison i

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, ,

L 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, rnd April 26, 1972. Commercial generation of power began on l 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 i

s A. Unit One Quad Cities Unit One spent the entire month of December 1994 shutdown in a forced outage. The scheduled startup for Unit One is elanuary 13, '

1995.

B. Unit Two Quad Cities Unit Two began the month of December in cold shutdown.

The reactor was made critical on December 15, at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> and the generator was synchronized to the grid on December 17, at 0643 hours0.00744 days <br />0.179 hours <br />0.00106 weeks <br />2.446615e-4 months <br />.

On December 29, a load reduction was perfon J to accommodate Condensate Demineralizer backwash and precoat.

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9 III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. t 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.

Facility or Procedure Chanaes Reauirino NRC Acoroval i B.

There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Exoeriments Reauirina NRC Aporoval -

t There were no Tests or Experiments requiring NRC approval for the reporting period. t t

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

UNIT 1 ,

Licensee Event -

Report Number M Title of occurrence ,94-017 12-05-94 Control Rod Sequence Does Not Meet BRWs  ;

UNIT 2 i Licensee Event i Report Number M Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period. i i

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l V. DATA TABULATIONS i

l 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 f

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APPENDIX C OPERATING DATA REPORT l DOCKin NO. 50-254 ,

1 UNIT One DATE January P,1995 COMPLETED BY Kristal Moore i

TELEPHONE (309) 654-2241 OPERATING STATUS 0000 120aN

1. REPORTING PERIOD: 2400 123194 GROSS HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOL WAS CRTTICAL 0.00 2651.20 152432.50 .

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 0.00 2527.60 147823.90

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERM AL ENERGY GENERATED (MWH) 0.00 546293,6.20 319156123.40

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 1765735.00 103463854.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 1670168.00 97588166.00

12. REACTOR SERVICE FACTOR 0.00 30.27 76.53

13. REACTOR AVAILABILTTY FACTOR 0.00 10.27 78.25

14. UNTT SERVICE FACTOR 0.00 28.86 74.22

15. UNTT AVAILABILTTY FACTOR 0.00 28.36 74.67

16. UNTT CAPACTTY FACTOR (Using MDC) 0.00 24.80 63.71

17. UNTT CAPACTTY FACTOR (Using Design MWs) 0.00 24.17 62.10

18. UNTT FORCEI' OUTAGE RATE 100.00 46.42 7.49

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP: 1 13-95

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

FORECAST ACHIEVED INTTIAL CPJTICALITY ,

INITIAL ELECTRICTTY COMMERCIAL OPERATION 1.19-9 TTCHOP3\NRCudONTHLY.RPT

APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNrr Two DATE January 9,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 120194

1. REPORTING PERIOD: 2400 123194 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY ALTTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACirY: 769 DESIGN ELECIRICAL RATING (MWe-NET): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NLMBER OF HOURS REACTOR WAS CRTTICAL 402.20 5874.80 149775.85

6. RE(CTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENI 3tATOR ON LINE 353.30 5748.50 145931.65 8.11Nrr RESERVE SHtfrDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 16544.40 12779221.00 315560182.90

10. GROSS ELECTRICAL ENERGY GENERATED (MWH)  !!5449.00 4204131.00 101513901.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 104905.00 4013349.00 96155909.00

12. REACTOR SERVICE FACTOFs 54.06 67.07 75.79

13. REACTOR AVAILABILrrY FACTOR 54.06 67.07 77.30 ,

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14. UNIT SERVICE FACTOR 47.49 65.63 73.85

15. UNrr AVAILABILITY FACTOR 47.49 65.63 74.20 I I

16. UNrr CAPACITY FACTOR (Using MDC) 18.34 59.58 63.28 ,

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17. UNrr CAPACTTY FACTOR (Using Design MWe) 17.87 58.07 61.67 I

18. UNrr FORCED OLTTAGE RATH 52.51 34.37 9.93

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

0. IF SHtTFDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): l FORECAST ACHIEVED INTTIAL CRTTICALrrY INITIAL ELECTRTCT1'Y COMMEPCIAL OPERATION 1.10-9 TliCilOPS\NRCWONTHLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 -

UNIT One DATE January 9. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH December 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -9 17. -10

2. -9 18. -9

3. -9 19. -9

4. -9 20. -9

5. -9 21. -9

6. -9 22. -9

7. -9 23. -9

8. -7 24. -8

9. -8 25. -8

10. -9 26. -8

11. -8 27. -8

12. -9 28. -8

13. -9 29. -8

14. . -9 30. -8

15. -10 31. -8 -

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INSTRUCTIONS )

On this form, list the average daily unit power level in MWe-Net for each day 1 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 1 dependable capacity is used for ti.e net electrical rating of the unit, there I may be occasions when the daily average power leval 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 N0 50-265 UNIT Two DATE January 9. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH January 1995 DAY AVERAGE DAILY POWEP. LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,

1. -8 17. 33

2. -9 18. 121

3. -8 19. 142 1

4. -8 20. 173

5. -8 21. 166 i

6. -8 22. 167

7. -8 23. 175  !

8. -6 24. 246

9. -7 25. 272 -

10. -8 26, 272

11. -8 27. 272

12. -8 28. 596

13. -8 29. 645 ,

14. -9 30._ 614

15. -9 31. 612

16. -11 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 4 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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4 APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.10-254 UNIT NAME One COMPLETED BY Kristal Moore DATE January 9. 1995 REPORT MONTH December 1994 TELEPHONE 229-654-224)

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HE E LICENSEE O DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 94405 12-1-94 F 744.0 0 2 154/94415 ---- - -- Contirued Forced Outage.

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a APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE January 9, 1995 REPORT MONTH December 1994 TELEPHONE 309-654-2241 M

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$M LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 04-15 12-1-94 F 390.7 F 2 ---- ---- --- -- - Continued Forced Outage.

94-1G 12-29-94 F 0.0 B 5 toad drop to accommodate condensate demineralizer backwssh and precoat.

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. l VI. UNIOUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Operations Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Unit: 2 Date: 12/17/94 Valve Actuated: No. & Tvoe of Actuation:

2-203-3A 1 Manual 2-203-3B 1 Manual i 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual Plant Conditions: Reactor Pressure - 920 psig Descriotion of Events: Manual actu&tions on startup from Q2F35 l l

B. Control Rod Drive Scram Timina Data for Units One and Two 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 Control Rod i Drive Scram timing for the reporting period. All scram timing as performed  :

with reactor pressure greater than 800 PSIG. 1 l

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RESULTS OF SCRAM TIM 2NG MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/94 TO 12/31/94 j j AVERAGE TIME IN SECONDS AT % MAX. TIME j l l INSERTED FROM FULLY WITHDRAWN FOR 90% i

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INSERTION 1 DESCRIPTION l NUMBER i 5  ! 20  ! 50  ! 90 '

Technical Specification 3.3.C.1 A DATE  ! CF RODS  ! 0.375 ! 0.900  ! 2.00 3.5 7 sec. 3.3.C.2 (Averaoe Scram Insertion Tima) l l l l l' i 01-27-94 l 1 l 0.31 ] O.69 l 1.45 2.53 , H-1 l U1 for Maintenance

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t 01-29-94 ll 1 l 0.33 [ 0.73 l 1.51 l 2.58 l M-10  ! U1 for Maintenance

! , j j 2.58 l i 1 01-29-94 '

177  ! 0.32 '

O.69 l 1.46 l 2.56 l H-3 l U2 SEQ A & B for Tech Spec & Maintenance '

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02-10-94 l 1  ! 0.29 j 0.65 l 1.39 2.41 F-7 l U1 F-7 for WR Q12855

' 2 41 1 i 1 i I i i I  ! I l 02-19-94 1 1 0.31. 0.69 l 1.45 j 2.53 l H-1 j U1 U-1 for WR Q14360

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02-23-94 l 1 l 0.30 0.68 l 1.45 , 2.62 l J-3 l U2 J-3 for WR Q14662 l l l 2.62  !

l  ! :l t l t 1 06-28-94 l 7 1 0.31 0.69 l 1.45 2.54 l 2.67

• U2 H-5, H-3, E-5, D-13, H-11, D-5 l  !. l l L-3 for WR Q15111 SSPV i 1 i 07-13-94 l 4 0.33 0.71 1.48 l 2.57 2.77 i U2 K-13, B-7, D-7, E-4

!  !  ! I 08-31-94 ! 177 0.30 ! O.68 1.45 2.54 ' 2.80 l U1 BOC Q1C14 I I I 09-28-94 l 1 l 0.32 j 0.69 1.47 2.55 2.55 U1 M-10 Q18064 1

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09-30-94 2 0.28 0.61 l 1.27 ll 2.24 2.26 U2 F-1, B-5 for WR Q18123, Q18116 12-19-94 177 , 0.32 0.695 l 1.46 2.56 B-4 l U2 Hot Scram Timing - Unit Startup i l l l j l 2.82 l Post-Maintenance NRC/SCRKHME.FRM

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: 01 Reload: 13 CycIe: l'

2. Scheduled date for next refueling shutdown: 1-4-96

3. Scheduled date for restart following refueling: 5-9-96

4. Will refueling or resumption of operation thereafter require a Technical l Specification change or other license ameadment:

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

1 7-4-95 l

6. Important licensing considerations associated with refueling, e.g. new i or different fuel design or supplier, unreviewed design or performance l analysis methods, significant changes in fuel design, new operating l procedures:

7. The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1717

8. The present licensed spent fuel pool storage. capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 3657

b. Planned increase in licensed storage: 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2006 APPROVED (final) 14/0395t W30W i l

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OTP 300-532 Revision 2 QUA0 CITIES REFUELING October Igsg INFORMATION REQUEST

l. Unit: 02 Reload: 12 Cycle: 13

2. Scheduled date for next refueling shutdown: 3-5-95

3. Scheduled date for restart following refueling: 7-9-95

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. Change TS at end of Cycle 13 operation.

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

Approved June 10, 1994

6. Important licensing considerations associated with refueling, e.g., new l or differeni: fuel design or suppller, 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 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 6

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 APPROVED 14/0395t .

Q.C.O.S.R.

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i VIII. GLOSSARY I

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 APPJi - Average Power Range Monitor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System E0F - 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 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 lnterim 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 TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center UCHOf%NRC\MONDEY.RIT