ML20081F076
| ML20081F076 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/28/1995 |
| From: | Aitken P, Moore K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PCA-95-021, PCA-95-21, NUDOCS 9503210523 | |
| Download: ML20081F076 (19) | |
Text
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Commonwealth litison Company Quad Citics Generating $tation l
22710 206th Asenue North
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Cordosa, IL 612 f 2 9740 Tel y P>4M22 n l PCA-95-021 March 9, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
SUBJECT:
Quad Cities Nuclear Station Units I 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 February 1995.
4 Respectfully, Comed Quad-Cities Nuclear Power Station fA Paul C. Aitken System Engineering Supervisor PCA/dak Enclosure cc:
J. Martin, Regional Administrator C. Miller, Senior Resident Inspector 210198 9503210523 950228 PDR ADOCK 05000254 l -l A L nkum compan)
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c QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT February 1995 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 i
LICENSE NOS. DPR-29 AND DPR-30 1
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TABLE OF CONTENTS' I.
Introduction.
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'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 Reparting Requirements A.
Main Steam Relief Valve Operations i
B.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary i
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INTRODUCTION l
Quad-Cities Nuclear Power Station is composed of two' Boiling Water Reactors, each with a' Maximus Dependable Capacity of 769 MWe Net, located in e
Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois' Gas & Electric Company. The Nuclear Steam Supply.
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Systems are General' Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary
- construction con;ractor 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.
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One Quad Cities Unit One started the month of February 1995 at full power and remained on line for the entire month. There have been a few-load drops, however the average daily power _ level was 80% or greater.
B.
Mnjt_Iwo Quad Cities Unit Two remained on lir.e the entire month of February 1995. A Load drop was taken February I due to conductivity. The west side of the Condenser was isolated for on-line tube leak repair. Unit Two started coast down February 11, for Refuel Outage (Q2R13) scheduled to start on March 5, 1995.
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l III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.
AND SAFETY RELATED MAINTENANCE l
A.
Amendments to Facility License or Technical Specifications There were-no Amendments to the Facility License or Technical Specifications for the reporting period.
B.
Facility or Procedure Chances Reauirina NRC Anoroval
' 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.
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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 Qalg Title of occurrence There were no Licensee Event Reports for Unit I for this reporting period.
UNIT 2 Licensee Event Report Number Q11g Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period.
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V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.. Operating Data Report B.
Average Daily Unit Power Level 4
C.
Unit Shutdowns and Power Reductions 4
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APPENDIX C -
OPERATING DATA REPORT DOCKET NO.
50 254 UNrr. Oes
' DATE ~ Masch 9,1995 COMPWTED BY Krisent Moose TELEPHONE - 0 09) 654 2241 OPERATING STATUS 0000 020195
- l. REPORTING PERIOD 2400 022895 OROSS HOURS IN REPORTING PERIOD 672
- 2. CURREKrLY AITTHmtran POWER LEVEL (WWQ: 2511 MAX > DEFEND > CAPAC.TY: 769 DESIGN ELECTRICAL RATING MWe-NET): 789
- 3. POWER LEVELTO WHICH RESTRICTED GF ANY)(MWe-Ne0: N/A
- 4. REASONS FOR RESTRICTION (IF ANY):
I THIS MONTH YR TO DATE CUMULATIVE
- 5. NUMBER OF HOURS REACTOR WAS CRTriCAL 672.00 1184.80 153617.30 f
- 6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90 i
- 7. HOURS GENERATOR ON LINE 672.00 1129.00 148952.90
- 8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20 i -
- 9. OROSS THERMAL ENEROY GENERATED (MWH) 1663388.80 2546340.70 321702464.10
- 10. OROSS ELECIllCAL ENEROY GENERATED (MWH) 539000.00 820028.00 104283882.00
- 11. NET ELECTRICAL ENiiROY GENERATED (MWH) 516483.00 782468.00 98370634.00
- 12. REACTOR SERVICE FAcrOR 100.00 83.67 76.58
- 13. REACTOR AVAILABILTrY FACIDR 100.00 83.67 78.29
- 14. UNrr SERVICE FACTOR 100.00 79.73 74.26
- 15. UNIT AVAILABILFTY FACTOR 100.00 79.73 74.71 L
16, UNIT CAPActrY FACTOR (Using MDC) 99.94 71.86 63.77
- 17. UNIT CAPACffY FACTOR (Uning Design MWe) 97.4I 70.04 62.16
- 18. UNIT PORCED OUTAGE RATE 0.00 20.27 7.60
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
- 20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
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- 21. UNTr3 IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):
PORECAST ACHIEVED INrrtAL CkTTICALTTY l
INTTIAL ELECTRICfrY COMMERCIAL OPERATION
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1.149 I
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- j APPENDIX C i
OPERATING DATA REPORT DOCKETNO. 50-265 UNrr Two -
DATE ' Maseh 9,1995 4
COMPLlfrED BY ' Kdstal Moose TELEPHONE (309) 654-2241 ~
OPERATING STATUS 0000 020195
- 1. REPORTING PERIOD 2400 022895 OROSS HOURS IN REPORTING PERIOD 672 I
- 2. CURRENTLY AUTHmtm POWER LEVEL (MWO: 2511 MAX > DEFEND > CAPACfrY: 769
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. DESIGN ELECIRACAL RATING WWe-NET): 789 5
- 3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Neo: N/A
- 4. REASONS POR RESTRICTION (IP ANY):
THIS MONTH Yk TO DATE CUMULATIVE
- 5. NUMEER OF HOURS REACTOR WAS CRrrICAL 672.00 1416.00 151191.85
- 6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80
- 7. HOURS GENERATOR ON LINE 672.00 1416.00 147347.65
- 8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
- 9. OROSS THERMAL ENEROY OENERATED (MWH) 1496015.80 3151269.10 319091973.20
- 10. OROSS ELECTRICAL ENEROY OENERATED (MWH) 473661.00 998053.00 102511954.00 J
l1. NET ELECTRICAL ENEROY OENERATED (MWH) 453211.00 954327.00 97110236.00
- 12. REACIVR SERVICE FACTOR 100.00 100.00 75.97 13.REACTOk AVAILABILrrY FACTOR 100.00 100.00
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- 14. UNrr SERVICE FACTOR 100.00 100.00 74.03
- 15. UNIT AVAILABILTTY FACTOR 100.00 100.00 74.39
- 16. UNrr CAPActrY FACTOR (Using MDC) 87.70 87.64 63.45
- 17. UNrr CAPACfrY FACTOR (Using Desige MWe) 85.48 85.42 61.84
- 18. UNrr PORCED OUTAGE RATE 0.00 0.00 9.84 j
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):
- 20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
- 21. UNITS IN TEST STATUS (PluOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED l
INTTIAL CRrrtCALTTY INrrtAL ELECTRICfrY COMMERCIAL OPERATION
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APPENDIX B AVERAGE DAILY. UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE March 9. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH February 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
769 17.
773 2.
693 18.
779 3.
764 19.
779 4.
766 20.
779 5.
752 21.
777 6.
768 22, 779 7.
769 23.
778 8.
768 24, 779 9.
768 25.
779 10.
769 26.
770 1
11.
760 27.
778 12.
769 28.
779 13.
767 29.
14.
767 30.
15.
769 31.
16.
756 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.
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- APPENDIX B i
AVERAGE dally. UNIT POWER LEVEL DOCKET NO 50-265
.i UNIT Two DATE March !L 1995 COMPLETED BY Krista; Moore TELEPHONE (309) 654-2241 MONTH February 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.
(MWe-Net)
(MWe-Net) 1.
295 17.
729 2.
190 18.
728 1
3.
201 19.
724 4.
659 20.
724 5.
746 21.
718 6..
752 22.
718 7.
756 23.-
713 8.
753 24.
712 9.
750 25.
705 10.
754 26.
706 j
11.
748 27.
701 12.
747 28.
697 13.
738 29.
14.
741 30.
15.
734 31.
16.
732 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.
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9 APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE March 9, 1995 REPORT MONTH February 1995 TELEPHONE 309-654-2241 A
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DURATION EVENT NO.
DATE (HOURS)
REPORT CORRECTIVE ACTIONS / COMMENTS NONE i
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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE March 9, 1995 REPORT MONTH February 1995 TELEPHONE 309-654-2241
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.x LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.
DATE (HOURS)
REPORT 95-04 02-01 95 F A 5
tend Drop due to Conductivity. Condenser Tube Leak Repaired.
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VI. UNIOUE 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 There was no Control Rod Drive scram timing data for Units One and Two for the reporting period.
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4 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 Aulsion 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST l'
1.
Unit:
01 Reload:
13
, Cycle:
1-'~9' 2.
Scheduled date for next refueling shutdown:
3.
Scheduled date for restart follouing refueling:
5-9-96 4.
Will refueling or resumption of operation thereafter require a Technical Speelfication change or other license amendment:
No 5.
Scheduled date(s) for submitting. proposed licensing action and supporting information:
7-4-95 i
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:
f 7.
The number of fuel assemblies.
i a.
Number of assemblies in core:
724 b.
Number of assemblies la spent fuel pool:
1717 j
S.
The present Ilconsed 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 l
spent fuel pool assuming the present Ilconsed capacity:
2006 i
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APPROVED (final)
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4 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 American National Standards Institute ANSI Average Power Range Monitor APRM Anticipated Transient Without Scram ATWS Boiling Water Reactor BWR Control Rod Drive CR0 Electro-Hydraulic Control System EHC Emergency Operations Facility EOF Generating Stations Emergency Plan GSEP HEPA
- High-Efficiency Particulate Filter HPCI
- High Pressure Coolant Injection System HRSS
- High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test Intermediate Range Monitor IRM Inservice Inspection ISI Licensee Event Report LER Local Leak Rate Test LLRT Low Pressure Coolant Injection Mode of RHRs LPCI Local Power Range Monitor LPRM Maximum Average Planar Linear Heat Generation Rate MAPLHGR Minimum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratio MFLCPR Maximum Permissible Concentration MPC 3
MSIV Main Steam Isolation Valve National Institute for Occupational Safety and Health
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NIOSH Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIOMR RBCCW
- Reactor Building Closed Cooling Water System Rod Block Monitor RBM RCIC
- i:cactor Core Isolation Cooling System Residual Heat Removal System RHRS Reactor Protection System RPS Rod Worth Minimizer RWM SBGTS Standby Gas Treatment System Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SDV SRM.
Source Range Monitor Turbine Building Closed Cooling Water System TBCCW Traversing Incore Probe TIP Technical Support Center TSC T1rHOPnNRC\\ MONTHLY.RM 1
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QTP 300-532 7
Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.
Unit:
02 Ae1 cad:
12 Cycle:
13 2.
Scheduled date for next refueling shutdown:
3-5-95 3.
Scheduled date for restart folloutng refueling:
7-9-95 4.
Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:
YES - Safety limit MCFR to be chanaed from 1.06 to 1.07 due to GE10 Fuel.
Change TS at and of Cycle 13 operation.
5.
Scheduled date(s) for submitting proposed licensing action and i
supporting information:
Approved June 10, 1994 6.
Important Ilcansing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysts methods, significant changes in fuel design, new operating procedures:
144 GE10 fuel bundles will be loaded during Q2R13.
l 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 Ilconsed spent fuel pool' storage, capacity and the size of any increase la 1.lconsed storage capacity that has been requested or is i
planned la number of fuel assemblies:
I 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 Ilconsed capacity: 2006 1
APPROVED NE 14/0395t G.C.O.SJt.
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