ML20077F923

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

ML20077F923
Person / Time
Site:	Quad Cities
Issue date:	11/30/1994
From:	Aitken P, Moore K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PCA-94-009, PCA-94-9, NUDOCS 9412150192
Download: ML20077F923 (19)

Text

{{#Wiki_filter:' Cor.im::nwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654 2241 PCA-94-009 December 8, 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 50-265 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 November 1994. Respectfully, Comed Quad-Cities Nuclear Power Station (* - Paul C. Aitken System Engineering Supervisor AMS/dak Enclosure cc: J. Martin, Regional Administrator C. Miller, Senior Resident Inspector l 1500q nc,,on miu m p/) 9412150192 941130 PDR ADOCK 05000254 vF 1 p PDR

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT November 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 TIri!OP3\\NRC\\ MONTHLY.RM

4 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 4 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 TIrHOP3\\NR('\\ MON 111LY.RPT

l I. INTRODUCTIOtl 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 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. TECH 0P3\\NRC\\ MONTH 1.Y.RFr _____ _ _ j

II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One spent the entire month of November 1994 shutdown in a forced outage. The schedule startup for Unit One is December 19, 1994. B. Unit Two Quad Cities Unit Two was off-line the entire month of November 1994. Unit Two is expected to be on-line December 10, 1994. TirHOl'3tNRC\\ MON 11{LY.RI'r

r-i e 9 III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE l A. Amendments to Facility License or Technical Soecifications Technical Specification Amendment No.150 was issued on November 3, 1994 to Facility Operating License DPR-29 and Amendment No. 146 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2 respectively. The amendments add a license condition that modifies the March 14, 1983, NUREG-0737, " Clarification of THI Action Plan Requirements, " Order to allow the commitments made in response to NUREG-0737 to be controlled under the requirements of 10CFR50.59. Technical Specification Amendment No.151 was issued on November 16, 1994 to Facility Operating License DPR-29 and Amendment No. 147 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station, Unit 1 and 2, respectively. The proposed amendments would revise the Technical Specification 3.4/4 to revise the sodium pentaborate solution concentrations for Standby Liquid Control System (SBLC) storage tanks based on net positive suction head test results. 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 Experiments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period. i EOK)PMNROMONDt!.Y.RPT j

4 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 Reoort Number Dalg Title of occurrence 94-014 10-14-94 CRD High Point Vent Valves (NOTE: Deleted 11/11/94) 94-014 11-07-94 Missed Fire Surveillances 94-016 11-23-94 RHRSW Pipe Support UNIT 2 Licensee Event Egoort Number Qalg Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period. TIDiotP3\\NRC\\MONDnX5WT

9 V. DATA TABULATIONS 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 11GIOP3\\NRC\\ MONTHLY.Rrf

l APPENDtX C OPERATING DATA REPORT DOCKETNO. 50-254 UNrr One DATE December 8, 1994 ) COMPLETED BY Kristal Moore TELEPilONE (309) 654-2241 OPERATING STATUS 0000 110194

1. REPORTING PERIOD: 2400 l13094 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY ALTrilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWs-NET): 789

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

4. REASONS FOR RESTRICrlON GF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF IIOURS REACTOR WAS CRrriCAL 0.00 2651.20 152432.50

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. IlOURS GENERATOR ON LINE 0.00 2527.60 147823.90

8. UNrr RESERVE SitLTTDOWN llOURS 0.00 0.00 909.20

9. GROSS TilERMAL ENERGY GENERATED (MWH) 0.00 5462936.20 319156123.40

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

11. NET ELECTRICAL ENEROY GENER ATED (MWH) 0.00 1670168.00 975R8166.00

12. REACTOR SERVICE FACTOR 0.00 33.08 76.82

13. REACTOR AVAILABILTrY FACTOR 0.00 33.08 78.54

14. UNrr SERVICE FACTOR 0.00 31.54 74.50

15. UNTT AVAILABILrrY FACTOR 0.00 31.54 74.95

16. UNrr CAPACITY FACTOR (Using MDC) 0.00 27.10 63.95

17. UNir CAPACrrY FACTOR (Using Design MWe) 0.00 26.41 62.33

18. UNIT FORCED OITTAGE RATE 100.00 36.39 7.05

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < FSTIMATED DATE OF STARTUP: 12-19-94

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

FORECAST ACHIEVED INrr!AL CRrrICALrrY INTTIAL ELECTRICrrY COMMERCIAL OPERATION 1.16-9 TECHol'3\\NRC\\ MON 1NLY RIT

amma APPENDIX C OPERATING DATA REPORT DOCKET NO. 50 265 UNrr Two DATE December 8, 1994 COMPLETED BY Kristal Moore TELEPIIONE (309) 654-224i OPERATING STATUS 0000 110194

1. REPORTING PERK.1: 2400 113094 GROSS IlOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWe-NCT): 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. NUMBER OF IIOURS REACTOR WAS CRTriCAL 0.00 5472.60 149373.65

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 0.00 5395.20 145578.35

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERM AL ENERGY GENERATED (MWH) 0.00 12762676.60 315543638.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 4088682.00 10139R452.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 3908444.30 96051004.00

12. REACTOR SERVICE FACTOR 0.00 68.28 75.88

13. REACTOR AVAILABILfrY FACTOR 0.00 68.28 77.39

14. UNrr SERVICE FACTOR 0.00 67.31 73.95

15. UNrr AVAILABILTTY FACTOR 0.00 67.31 74.30

16. UNfr CAPAcrTY FACTOR (Using MDC) 0.00 63.41 63.45

17. UNrr CAPACrrY FACTOR (Using Design MWe) 0.00 61.80 61.84

18. UNTT FORCED OUTAGE RATE 100.00 32.68 9.73

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTIIS (TYPE, DATE, AND DURATION OF EAClf):

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 12/10/94

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

FORECAST ACHIEVED INrflAL CRrflCALITY INITIAL ELECTRICfrY COMMERCIAL OPERATION j 1.16-9 TECHOP3\\NRC\\MONTHl.Y.RIT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i DOCKET N0 50-254 UNIT One DATE December 8. 1994 COMPLETED BY Kristal Moore TELEPHONE 1309) 654-2241 MONTH November 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1. -9 17. -9 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. -9 24. -8 9. -9 25, -8 10. -9 2 6. ____ -8 11. -8 27. -8 12. -9 28. 9 13. -9 29. -9 14. -9 30. -9 15. -_S 16. -9 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each riuy in the reporting month. Compute to the nearest whole megawatt. These fi9ures 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. 1.16-8 TirHOP3\\NRCutONTIILY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE December 8. 1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH November 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (MWe-Net) 1. -9 17. -9 2. -9 18. -8 3. -9 19. -8 4. -9 20. -8 5. -9 21. -8 6. -9 22. -9 7. -9 23. -8 8. -9 24. -8 9. -8 25. -8 10. -8 26. -8 11. -8 27. -8 12. -8 28. -8 13. -9 29. -8 14. -9 30. -8 15. -8 16. -9 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. 1.16-8 TTrHOP3\\NRC\\ MONTHLY.Rl*r

r APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME pne COMPLETED BY Kristal Moore DATE December 8, 1994 REPORT MONTH November 1994 TELEPHONE 309-654-2241 H A E x 5 o"t HM = = $a se k l O<E 08 = 8

r: $

h m M LICENSEE O DURATION 8 EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS Continued Foned Outage. 944X)5 11148 F 720.0 0 2 T1X'llOl% RC\\ MON 1111.Y. RFT l

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-265 UN8T NAME Two COMPLETED BY Kristal Moqip_ DATE December 8, 199.4,, REPORT HONTH December 1994 TELEPHONE 3 0 9-6 5 4 -2,)g ),,,,,_ j .. w m-sar H b Os0 = x W = $W W O WW i o 4 28 2 N 9 g E 8 2"8 l N x b LICENSEE O DURATION 8 EVENT CORRECTIVE ACTI0ft i/CCMMENTS l l NO. DATE (HOURS) REPORT Continued Forced Outage. 94-15 11 1 N P 7m.0 2 T1rHOP3\\NFDMON11tLY.RFT

VI. M.ill_00E REPORTING RE0VIREMENTS Ilowing items are included in this report based on prior commitments to nie cc. mission: A. tigi;c Steam Rg. lief Valve Operations There were no Main Steam Relief Valve Operations for the reporting period. B. Control Rod Drive Scram Timina Data for Units One at.d Two There was no Control Rod Drive scram timing data for Units One and Two for the reporting period, i e l l DfitOPhNRC\\MONDtLY.Rl'r

VII. REFVELING 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. I I i l i l I I I l l l TirHOPhNRC%f0NTHLY.RPT I

QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST i 14 1 1. Unit: 01 Reload: 13 Cycle: 2. Scheduled date for next refueling shutdown: 1-4-96 3. Scheduled date for restart following refueling: 5-9-96 1 4. Will refueling or resumption of operation thereafter require a Technical i Specification change or other license amendment: No 1 5. Scheduled date(s) for submitting proposed licensing action and ) supporting information: 1 7-4-95 6. Important licensing considerations associated with refueling, e.g., new i or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating i procedures: ) 1 I l 7. The number of fuel assemblies. a. Number of assemblies in core: 724 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 licented 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 I spent fuel pool assuming the present'llcensed capacity: 2006 l l l l l APPROVED i (final) g 3,g g 14/0395t G.C.O.S.R. .... _ _ m _

QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1. Unit: 02 Reload: 12 Cycle: 13 .i 1 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 thereaf ter require a Technical Specification change or other license amendment: YES - Safety limit MCPR to be changed from 1.06 to 1.07 due to GELO 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 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 bc 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. L kensed 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 (final) ggg 14/0395t, G.C.O.S.R.

T VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below: ACAD/ CAM - Atmospheric Containment Atmospheric heric Monitoring Dilution / Containment A' American National Stat.

nstitute ANSI Average Power Range Moni..

APRM ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System Emergency Operations Facility E0F Generating Stations Emergency Plan GSEP HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System Integrated Primary Containment Leak Rate Test IPCLRT Intermediate Range Monitor IRH Inservice Inspection ISI LER - Licensee Event Report LLRT - Local Leak Rate Test Low Pressure Coolant Injection Mt 'f RHRs LPCI LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio MCPR MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concentration MSIV - Main Steam Isolation Valve National Institute for Occupational Safety and Health NIOSH PCI - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCW - Reactor Building Closed Cooling Water System RBH - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System Residual Heat Removal System RHRS RPS - Reactor Protection System RWM - Rod Worth Minimizer Standby Gas Treatment System SBGTS SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS Scram Discharge Volume SDV SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center TECHOM\\NRC\\ MON 1HLY.RI'T}}