ML20086K021

Monthly Operating Repts for June 1995 for Quad Cities Nuclear Station Units 1 & 2

ML20086K021
Person / Time
Site:	Quad Cities
Issue date:	06/30/1995
From:	Moore K, Pearce L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-95-068, LWP-95-68, NUDOCS 9507190334
Download: ML20086K021 (21)

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g. Commonwcalth I:dhon Company

. . Quad Otics Generating Station 22710 2G6th Asenue North Cordova, 11.61262 9760 rel pr>w22 n LWP-95-068 July 10, 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 June 1995.

Respectfully, Comed Quad-Cities Nuclear Power Station i ,

IL L. W. Pearce Station Manager .

LWP/dak Enclosure cc: H. Miller, Regional Administrator 1 C. Miller, Senior Resident Inspector

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RETURN FORM TO REGULATORY ASSURANCE, RON BAUMER FOR FILING I

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT June 1995 COMMONWEALTH EDISON COMPANY AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 I

LICENSE NOS. DPR-29 AND DPR-30 l

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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. 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 l

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b 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 Company and Mid-American Energy 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 1

United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29'and DP4-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Dccket 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 99neration 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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TICHOP3\NRC\ MONTHLY.RI'T

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4 II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One began the month of June 1995 at full power and remained on line for the entire month. Several load drops were performed, however the average daily power level remained at 80% or greater.

B. Unit Two Quad Cities Unit Two spent the entire month of June 1995 shutdown in Refuel Outage Q2R13. The scheduled startup is July 17, 1995.

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• E III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Soecifications Technical Specification Amendment No.152 was issued on February 16, 1995 to Facility Operating License No. DPR-29 and Amendment No. 148 to Facility Operating Licens9 No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments would revise the Technical Specification Sect!cas 1.0 (Definitions), 3.0 (Limiting Conditions for Operating) and i.0 (Surveillance Requirements). These l changes are part of the Technical Specification Upgrade Program (TSUP). j Technical Specification Amendment No. 153 was issued on May 30, 1995 j to Facility Operating License No. DPR-29 and Amendment No. 149 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments would change the Technical Specifications by (1) revising the low pressure valve at j which the High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) systems can be tested to 150 psig, and (2) testing these systems against a system head corresponding to reactor vessel pressure when steam is supplied to the turbines at 920 psig to 1005 psig for high pressure testing and 150 psig to 325 psig for low pressure testing.

Technical Specification Amendment No. 154 was issued on June 8, 1995 to Facility Operating License DPR-29 and Amendment No. 150 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments would revise the Technical Specification Section 3/4.4 (Standby Liquid Control System). These changes are part of the Technical Specification Upgrade Program (TSUP).

Technical Specification Amendment No. 155 was issued on June 13, 1995 to Facility Operating License No. DPR-29 and Amendment No. 151 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively. The amendments would revise the Technical Specification Sections 2.0 (Safety Limits and Limiting Safety System Settings), 3/4.11 (Power Distribution Limits) and 3/4.12 (Special Test Exceptions). These changes are part of the Technical Specification Upgrade Program (TSUP).

Technical Specification Amendment No. 156 was issued on June 14, 1995 to Facility Operating License No. DPR-29 and Amendment No. 152 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2 respectively. The amendment would revise the Technical Specification Section 5.0 (Design Features). These changes are part of the Technical Specification Upgraded Program (TSUP).

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B. Facility or Procedure Chanaes Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

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

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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 6.6.8.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report Number Q111 Title of occurrence There were no licensee event reports for Unit I for this reporting period.

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

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l V. DATA TABULATIONS 1

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 t

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APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNIT One DATE July 10,1995 COMPLETED BY Krisul Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 060195

1. REPORTING PERIOD: 2400 063095 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY ALTTilORIZED POWER LEVEL (MWt): 1511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECiltlCAL RA%d (MWe-NET): 789

3. POWER LEVELQWF.CH RESTRICTED (lF ANY)(MWe-Net): N/A

4. REASONS FOR RES TRICTION (IF ANY):

TH15 MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REAC" TOR WAS CRTilCAL 720.00 di11.80 156544.30

6. REACTOR RESERVE SliUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 720.00 4056.00 151879.90

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERM AL ENERGY GENERATED (MWH) 1785745.30 9762075.10 328918198.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 564586.00 3137619.00 106601473.00

11. NET ELECTRICAL ENTRGY GENERATED (MWH) 541658.00 3014335.00 100602501.00

12. REA("rOR SERVICE FACTOR 100.00 94.68 76.92

13. REACTOR AVAILABILITY FACTOR 100.00 94.68 78.60 i i

14. UNrr SERVICE FACTOR 100.00 93.39 74.63

15. UNrr AVAILABILrrY FACTOR 100.00 93.39 75.07 I l

16. UNrr CAPACrrY FACTOR (Using MDC) 97.83 90.26 64.28

17. UNrr CAPActrY FACTOR (Using Desgn MWe) 95.35 87.97 62.65

18. UNTT FORCED OUTAGE RATE 0.00 6.61 7.46

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS UYPE, DATE, AND DURATION OF EACif):

20. IF SHtTTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP. i l

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): l FORECAST ACHIEVED INirlAL CRTTICALTTY INTTIAL ELECTRICrrY COMMERCIAL OPERATION 1.10-9 TTHOP3tN RC\MONTitLY.RPT

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APPENDIX C )

l OPERATING DATA REPORT DOCKET No. 50-265 1

UNTT Two DATE July 10,1995 COMPLL'TED BY Kristal Moore TELEPHONE (309) 654-224i OPERATING STATUS 0000 060195

1. REPORTING PERIOD: 2400 063095 GROSS HOURS IN REPORTING PERIOD: 720

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

3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A l 4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 0.00 1516.90 151292.75

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 0.00 1514.90 147446.55

8. UNTT RE5ERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 3363599.00 319304303.10 l

l 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 1064371.00 102578272.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 1012484.00 97168393.00

12. REACTOR SERVICE FACTOR 0.00 34.93 74.91

13. REACTOR AVAILABILITY FACTOR 0.00 34.93 76.39 1

14. UNTT SERVICE FACTOR 0.00 34.88 73.01

15. UNIT AVAILABILTTY FACTOR 0.00 34.88 73.36

16. UNTT CAPACTTY FACTOR (Usir.g MDC) 0.00 30.32 62.57

17. UNTT CAPACTTY FACTOR (Using Design MWe) 0.00 29.55 60.98

18. UNTT FORCED OUTAGE RATE 0.00 0.00 9.84

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 7-17-95

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

FORECAST ACHIEVED INTTIAL CkTTICALTTY INTTIAL ELECTRICTTY COMMERCIAL OPERATION 1.16-9 TIrHOP3\NRC\ MON 1HL'!.RFT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE July 10. 995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH June 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY PGVER LEVEL (MWe-Net) (MWe-Net)

1. 761 17, 749

2. 774 18. 712

3. 775 19. 754 4, 773 20. 752

5. 772 21. 749

6. 758 22. 750

7. 766 23. 749

8. 769 24. 718

9. 772 25. 746

10. 770 26. 747

11. 713 27. 750

12. 745 28. 754

13. 747 29. 755

14. 755 30. 688

15. 766 31.

16. 765 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 l 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 TirHOP3iNHOMONDILY.RYr

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE July 10. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH June 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. -8

2. -8 18. -8

3. -8 19. -8

4. -8 20. -9

5. -8 21. -9

6. -8 22. -8

7. -8 23. -9

8. -8 24. -8

9. -8 25. -8

10. -8 26. -9

11. -8 27. -8

12. -8 28. -8

13. -8 29. -8

14. -8 30. -9

15. -8 31.

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 wholr. megawatt. These figures will be used to plot a graph for each reporting montn. 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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l APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE July 10, 1995 REPORT EDNTH June 1995 TELEPHONE 309-654-2241 h 9 to 2 OO E 2 em a o- n: ==

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$ Ob<E

$8 !8

$ LICENSEE O DURATION EVENT a

NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS None 1

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE July 10. 1995 REPORT MONTH June 1995 TELEPHONE 309-654-2241 m

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2 O a 25 WW $W Am g Ho Q g $

$ LICENSEE 28 $o8 O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 95-05 064195 S 720.0 C 4 ----- -- --- ---- Continued Refuel Outage Q2R13.

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

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

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 Drive Scram timing for the reporting period. All scram timing as performed with reactor pressure greater than 800 PSIG.

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/95 TO 06/30/95 l l AVERAGE TIME IN SECONDS AT % j MAX. TIME l l l INSERTED FROM FULLY WITHDRAWN i FOR 90% l

!  !  ! INSERTION ! DESCRIPTION j NUMBER l 5  ! 20  ! 50  ! 90 l l Technical Specification 3.3.C.1 &

DATE  ! OF RODS ! O.375 ! O.900  ! 2.00 ! 3.5  ! 7 sec.  ! 3.3.C.2 (Averace Scram Insertion Time) i i  : i l 1 1 01/15/95 l 177 l 0.31 l 0.70 l 1.47 l 2.57 l 3.30 Post Maintenance after Q1F35 Seq A, B, Done l l l l l l J-6 l l l l l l l 04/28/95 l 1 l 0.29 l 0.65 l 1.42 l 2.48 l 2.48 '

Q18840 to torque Scram Inlet valve Packing.

l l l l l L14 06/24/95 l 1 l 0.30 0.65 1.37 l 2.41 l 2.41 l Diagnostic Testing of U-1 H-9 l l l l l H-9 l l l l l i l l l l l l l

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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-S32 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q1 Reload: 13 Cycle: 14

2. Scheduled date for next refueling shutdown: 2/5/96

3. Scheduled date for restart following refueling: 5/15/96

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

NO

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

{ 7-4-95

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

232 GE10 Fuel Bundles will be loaded during QlR14.

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7. The number of fuel assemblies.

a. Number of assemblies in core: 724 i l

b. Number of assemblies in spent fuel pool: 1717 l

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 i

14/0395t -1 OCT 3 01969 Q.C.O.S.R.

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

1. Unit: Q2 Reload: 13 Cycle:

2. Scheduled date for next refueling shutdown: 3-05-95

3. Scheduled date for restart following refueling: 7-17-95

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

NO S. 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 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 assemblies,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 3377

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 APPROVED ,

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14/0395t OCT 3 01989 C1.C.O.S.R.

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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 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 lest IRM - Intermediate Range Monitor ISI - Inservice Inspection LER - Licensee Event Report l 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 i

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 TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center 11CHOPhNRC\ MONTHLY.RIT

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