ML20082H968

Monthly Operating Repts for Mar 1995 for Quad Cities Nuclear Power Plant

ML20082H968
Person / Time
Site:	Quad Cities
Issue date:	03/31/1995
From:	Aitken P, Moore K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PCA-95-026, PCA-95-26, NUDOCS 9504180005
Download: ML20082H968 (19)

Text

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Commonwealth Edison Company Quad Cities Generating Station 22710 206th Avenue North

, Cordm a, 11.61242-9740 F l

. .rci 3m(is 6 22 u PCA-95-026 April 6, 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 March 1995. .

Respectfully, Comed Quad-Cities Nuclear Power Station O 't Cmo Paul C. Aitken System Engineering Supervisor PCA/dak Enclosure cc: J. Martin, Regional Administrator C. Miller, Senior Resident Inspector 1

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9504180005 95o331 ITg PDR ADOCK 05000254 P /,/

jj; 4 R PDR TEQIOP3WROMONTHLY.RPT f A Unicom Company-

QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 MONTHLY PERFORMANCE REPORT March 1995-COMMONWEALTH EDIS0N COMPANY l AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 l LICENSE NOS. DPR-29 AND DPR-30 i

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TABLE OF CONTENTS l I. Introduction ,

II. Summary of Operating Experience A. Unit One B. Unit Two l III. Plant or Procedure Changes, Tests, Experiments, and Safety Related i Maintenance A. Amendments to Facility License or Technical Specifications l B. Facility or Procedure Changes Requiring NRC Approval  ;

C. Tests and Experiments Requiring NRC Approval IV. Licensee Event Reports V. Data Tabulations

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A. Operating Data Report j B. Average Daily Unit Power Level 1' C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements l A. Main Steam Relief Valve Operations B. Control Rod Drive' Scram Timing Data 4 VII. Refueling Information VIII. Glossary TEQlOP3WRC\MONDILY.RPT

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[ I. INTRODUCTION i

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Quad-Cities Nuclear Power Station is composed of two Boiling Water. .

' Reactors, each with a Maximum Dependable ~ Capacity of 769 MWe Net, located in 4

Cordova, Illinois. The Station is' jointly owned by Commonw'ealth Edison

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

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

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

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l construction contractor was United Engineers & Constructors. The Mississippi j ,

! River is the condenser cooling water source. . The plant is. subject.to license:-

l: numbers DPR-29 and'DPR-30, issued October 1, 1971, and March 21,.1972,-

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- respectively; pursuant to Docket Numbers 50-254 and 50-265. Te h date of I 4

i; initial Reactor criticalities for Units One and Two, respectively were October

[ 18, 1971, and April 26, 1972. Commercial generation of power began on i February 18, 1973 for Unft One and March 10, 1973 for unit Two.  !

i 4 This report was compiled by Kristal Moore'and Debra Kelley, telephone

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number 309-654-2241, extensions 3070 and 2240.

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SUMMARY

OF OPERATING EXPERIENCE i I; A. Unit One i Quad Cities Unit'One began'the month of March 1995 at full power and I remained on line for.the entire mor th. A load drop was' performed to ,

a repair 182 Heater Emergency Drain \'alve. There have been.a few other 4 load drops, however the average dai?y-power level remained at 80% or greater.

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j. B. Unit Two Quad Cities Unit Two commenced Refuel Outage Q2R13 on March 5, 1995.  ;

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l l III. PLANT OR PROCEDURE CHANGES. TESTS, EXPERIMENTS, I AND SAFETY RELATED MAINTENANCE i

A. Amendments to Facility License or Technical Specifications I

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

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B. Facility or Procedure Changes Reauirina NRC Approval {

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There were no Facility or Procedure changes requiring NRC approval for

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C. Tests and Experiments Reauirina NRC Approval j There were no Tests or Experiments requiring NRC approval for the i reporting period. ,

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J l 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.

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! UNIT 1 j Licensee Event Report Number Date Title of occurrence i ,95-004 03/29/95 HPCI-IN0P s

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Report Number Date Title of occurrence

95-001 03/07/95 28 & 2C MSIV LLRT Failure. '

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i 5 i j V. DATA TABULATIONS l 4

I i l The following data tabulations are presented in this report:  ;

i A. Operating Data Report B. Average Daily Unit Power Level l i

j a C. Unit Shutdowns and Power Reductions

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A APPENDIX C OPERATING DATA REPORT DOCKET NO.30-254' UNrr One l DATE April 6,1995 COMPLIrrED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 l 030195

1. REPORTINO PERIOD: 2400. 033195 OROSS HOURS IN REPORTING PERIOD: 744 ,

1 2 CURRENTLY ALTTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 l DESIGN ELECTRICAL RATING (MWe-NirT): 789 l

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

4. REASONS FOR RES1RICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 744.00 1928.80 154361.30 l

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l 6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90 l

l 7. HOURS GENERAMR ON LINE 744.00 1873.00 149696.90 t

l 8. UNrr RESERVE SHUTDOWN Hot' AS 0.00 0.00 909.20 f 9. GROSS THERMAL ENEROY OP!ERATED (MWH) 1812200.80 435841.50 . 323514664.90

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10. OROSS ELECIRICAL ENL1tGY GENERATED (MWH) - 585866.00 1405894.00 104869748.00

11. NET ELECTRICAL ENEROY OEMRATED (MWH) 563772.00 1346240.00 '98934406.00

12. REACTOR SERVICE FACTOR 100.00 89.30 76.67

13. REACTOR AVAILABILTTY FACTOR 100.00 89.30 78.37

14. UNTT SGtVICE FACTOR 100.00 86.71 74.35

15. UNTT AVAILABILTTY FACTOR 100.00 86.71 74.80

16. UNrr CAPActrY FACTOR (Using MDC) ' 98.54 81.05 63.90

17. UNrr CAPACTTY FACTOR (Using Design MWe) 96.04 78.99 62.28

18. UNIT FORCED OtfrAGE RATE 0.00 13.29 7.56 l 19. SHITTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE, AND DURATION OF EACH):  !

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

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

FORECAST '- ACHIEVED INITIAL CRTTICALTTY j INrrIAL ELECTRICTTY COMMERCIAL OPERATION 1.1 +9 l

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APPENDIX C OPERATING DATA REPORT -

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. DOCKET NO. 50-265 '

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UNIT Two l DATE April 6,1995 '.

1 COMPLE1ED BY Krissel Moore .

1 l TELEPHONE ~ (309) 654-2241 I OPERATING STATUS l j' 0000 030195

1. REPORTING PERIOD

2400 033195 OROSS HOURS IN REPORTING PERIOD: 744 l 2.' CURRENTLY ALTTHORIZED POWER L.EVEL(MWt): 2511 MAX > DEPEND > CAPACrrY:~ 769 '

9 DESIGN ELECTRICAL RATING (MWe-NLT): 789 i

! 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): N/A 1

j 4. REASONS FOR RES11tlCTION (IF ANY): ,

t' l THIS MONTH YR TO DATE CUMULATIVE 1

l 5. NUMBER OF HOURS REACTOR WAS CRTTICAL . 100.90 1516.90 151292.75 i

0.00

! 6. REACTOR RESERVE SHITTDOWN HOURS - O.00 2985.80 6

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7. HOURS GENERATOR ON LINE 98.90 1514.90 147446.55 i I i l 8. UNTT RESERVE SHirrDOWN HOURS 0.00 .0.00 .702.90 '

9. GROSS THERMAL ENERGY OENERATED (MWH) 212329.90 33635599.00 319304303.10 i

10. OROSS ELECTRICAL ENEROY GENERATED (MWH) ~ 66318.00 1064371.00 102578272.00 j 11. NET ELECTRICAL ENEROY GENERATED (MWH) 58157.00 1012484.00 97168393.00

12. REACTOR SERVICE FACTOR 13.56 ' 70.23 75.73 '

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13. REACTOR AVAILABILTTY FACTOR 13.56 70.23 77.23 l 14. UNTT SERVICE FACTOR 13.29 ~10.13 73.81 4

15. UNIT AVAILABILrrY FACTOR 13.29 . 70.13 74.16 i 16. UNrr CAPActrY FACTOR (Using MDC) 10.16 60.95 63.25 j 17. UNrr CAPACTTY FACTOR (Using Design MWe) 9.91 59.41 (~ 61.65 l 18. UNrr FORCED OUTAGE RATE 0.00 0'.00 l 9.84 j 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH):

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l 20. IF SHirrDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 6-5-95

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

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APPENDIX B' AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT one DATE April 6, 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 l

MONTH March 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 777 17. 780 l

l 2. 778 18, 737 1

3. 778 19, 479

4. 779 20. 510

5. 775 __

21. 762

6. 777 22. 783

7. 779 23. 781

8. 779 24. 785 i

9. 779 25. 784

10. 782 26. 784

11. 783 27. 785

12. 717 28. 784

13. 777 29. 755

14. 781 30, 782 __,

15, 781 31. 782

16. 781 L INSTRUCTIONS-On this form, list the average daily unit power level in MWe-Net for each day l

in the reporting month. Co:npute 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 l

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 DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two

DATE April 6. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH March 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net).

1. 694 17. -8 1

2. 683 18. -8 4

3. 685 19. -8

4. 562 20.- -8

5. 5 21. -8

6. -8 22. .

7. -8 23. -8 l'

8. -8 24. -8 i

9. -8 25. -8

10. _ -8 26. -8 d

11. ___ -8 27. -8

12. -8 28. -8

13. -8 29. -8 l 14. -8 30. -8 i

15. -8 31. -8

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 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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4 I i 1 APPENDIX D-UNIT SHUTDOWNS AND POWER REDUCTIONS  !

j DOCKET NO. 50-254 7

l UN2T NAME One COMPLETED BY' Kristal Moore DATE Acril 6, 1995 REPORT MOlfrH March 1995 TELEPHONE 309-654-2241

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8 l E LICENSEE l 1 DURATION g. EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS

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95-003 03-19-95 F 0 A' 5 --------- --- ---- ' Repair iB2 Hester Emergency Drain Velve.

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UNIT SHUTDOWNS AND POWER REDUCTIONS 6

DOCKET NO. 50-265 l UNIT NAME Two COMPLETED BY Kristal Moore DATE Acril 6; 1995 REPORT MONTH March 1995- TELEPHONE 309-654-2241' 4 I

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS' l

NO. DATE (HOURS) REPORT l 95-05 03-05-95. S 645.1 C 2 Commenced Refuel Outage Q2R13. .

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' i i VI. UNIOVE REPORTING REQUIREMENTS l

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l The following items are included in this report based on prior commitments to  !

the commission: )

A. Main Steam Relief Valve Operations l Relief valve operations during the reporting period are summarized in the 1 following table. The table includes information as to which relief valve l was actuated, how it was actuated, and the circumstances resulting in its  ;

actuation.  ;

Unit: One l Date: March 12, 1995 l

l Valve Actuated: No. & Type of Actuation:

1-203-3A 1 Manual I 1-203-3B 1 Manual  !

1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E 1 Manual Plant Conditions: Reactor Pressure 1000 psig Description of Events: Normal surveillance testing.

B. ContrQ .. Rod Drive Scram Timino Data for Units One and Two l There was no Control Rod Drive scram timing data for Units One and Two for l the reporting period.

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VII. REFUELING INFORMATION

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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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. OTP 300-532

. Revision 2 QUAD CITIES REFUELING October 198g

,, . INFORMATION REQUEST 13 l' l 1. Unit: 01 . Reload: Cycle:

! 2. Scheduled date for next refueling shutdown: I~'-

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

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

a No . .

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

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7-4-95 .

6. Important licensing considerations associated with refueling, e.g., new i or different fuel design or supplier, unrevleued destga or performance analysis methods, significant changes la fuel design, new operatlag procedures: - '

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7. The number of fuel assemblies. l

a. Number of assemblies la core: 724 i

b. Number of assemblies la spent fuel pool: 1717

8. Tic oresent Ilconsed spent fuel pool' storage. capacity and the size of a;g )icrease le licensed storage capacity that has been requested or is pinned la number of fuel assembiles:

a. Licensed storage capacity for spent fuel: 3657-

b. Planned lacrease la 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 x .. .

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1 Revision 2 QUAD CIT.tES REFUELING' October 1989 i INFORMATION REQUEST i

j 'l. Unit: Q2 Reload: 13 Cycle: 1' l 2. Scheduled'date for next refueling' shutdown: 3-5-95

3. . Scheduled date for restart following refueling: 6-5-95 ,

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

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

Approved June 10, 1994 I. ,

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- 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 j procedures:

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j 144 GE10 Fuel Bundles will be loaded during Q2R13.

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l a. Number of assemblies in core: 0 f

j b. Number of assemblies in spent fuel pool: 3451

}. 8. The present licensed spent fuel pool storage capacity and the size of i any increase in licensed storage capacity that has been requested or is .

j planned in number of fuel assemblies:

j a. l.icensed storage capacity for spent fuel: 3897

} b. Planned increase in licensed storage: 0 a

, 9. The projected date of the last refueling that can be discharged to the i spent fuel pool assuming the present licensed capacity: 2006 APPROVED ,

(final) g yg g 14/0395t 4 O.C.O.S.R.

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i VIII. GLOSSARY

" The following abbreviations which may have been used in the Monthly Report, are defined below:

I ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring j

- ANSI - American National Standards Institute' l t

APRM - Average Power Range Monitor ATWS - Anticipated Transient Without Scram 1

BWR - Boiling Water Reactor

. CRD - Control Rod Drive J

EHC - Electro-Hydraulic Control System

E0F - Emergency Operations Facility ,

GSEP - Generating Stations Emergency Plan l HEPA - High-Efficiency Particulate Filter l 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 l LPRM - Local Power Range Monitor 1 MAPLHGR - Maximum Average Planar Linear Heat Generation Rate I MCPR - Minimum Critical Power Ratio MFLCPR - Maximum Fraction Limiting Critical Power Ratio 1

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 RBM - Rod Block Monitor

- Reactor Core Isolation Cooling System RCIC 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 s

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