Text

Monthly Operating Repts for Feb 1997 for Quad-Cities Nuclear Power Station Units 1 & 2
	ML20137C708
Person / Time
Site:	Quad Cities
Issue date:	02/28/1997
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-97-022, LWP-97-22, NUDOCS 9703250095
	Download: ML20137C708 (21)
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Osmnuinwcalth libwp Compan)

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Quad CiGes (knerating Mation

, 22710 2%th Asenue North Girdova,11. 61242-9740 a Tcl ,409M 4 22 41 LWP-97-022 1

l March 10, 1997 l l

U.S. Nuclear Regulatory Commission ,

ATTN: Document Control Desk !

Washington, D.C. 20555 l

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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 4

the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of February 1997.

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Respectfully, Comed Quad- ities Nu ear Power Station 00A w LIW.Pearce Station Manager LWP/dak . .p Enclosure I

cc: A. Beach, Regional Administrator i C. Miller, Senior Resident Inspector

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co004g STMORW2297.LWP 9703250095 970228 PDR ADOCK 05000254-R PDR lglggggggggg A l'nicum Compan)

NRC REPORT ROUTING CONCURRENCE FORM REPORT: February NRC Month Report f

N < 0Y Y ORIGIVATOR / DATE

/do<$ stoub W///97

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DEPARTMEN{ SUPERINTENDENT OR DESIGNEE DATE

- 3l/C/w REGULATORY AS RANCE DATE 4 Asu 3/i fl47 SITE VICE PRESIDENT / STATION MANAGER DATE RETURN FORM TO REGULATORY ASSURANCE, RON BAUMER FOR FILING

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QUAD-CITIES NUCLEAR POWER STATION ,

I UNITS 1 AND 2 1 .

MONTHLY PERFORMANCE REPORT a

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FEBRUARY 1997 1 1 2

1 I COMMONWEALTH EDISON COMPANY j

AND MID-AMERICAN ENERGY COMPANY i j

NRC DOCKET NOS. 50-254 AND 50-265 i l

l LICENSE NOS. DPR-29 AND DPR-30 i

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4 TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Chenges, Tests, Experiments, and Safety Related

Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval 4 C. Tests and Experiments Requiring NRC Approval l

i j IV. Licensee Event Reports V. Data Tabulations I

A. Operating Data Report

B. Average Daily Unit Power Level ;

l C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements 1

A. Main Steam Relief Valve Operations

, B. Control Rod Drive Scram Timing Data VII. Refueling Information i

VIII. Glossary TT! CHOP 3\NRC\ MONTHLY.RPT

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I. INTRODUCTION i l

Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity j of 763 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Mid-American Energy Company. The Nuclear j 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 & Constructcrs. 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, respectively.

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i II.

SUMMARY

OF OPERATING EXPERIENCE i

4 A. Unit One l

, Quad Cities Unit One was on-line the entire month of February 1997.

On February 14,1997 at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months a load drop was performed to 650 i MWe to troubleshoot Feedwater Regulating Valve problems. On February J 15,1997 at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months a scheduled load drop to 200 MWe was performed to isolate the east side of the Main Condenser to commence Tube Leak j Testing and Plugging. On February 17,1997 at 2051 hours0.0237 days 0.57 hours 0.00339 weeks 7.804055e-4 months load increase was initiated after 36 tubes had been plugged. On February 18, 1997 at 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months holding load at 650 MWe due to Feedwater i Regulating Valve problems. On February 19, 1997 at 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months increased load from 650 MWe to full power. At 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months on February j 20, 1997 holding load at 815 MWe.

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! B. Unit Two i

) Quad Cities Unit Two began the month of February 1997 at full power.

On February 28, 1997 at 1540 hours0.0178 days 0.428 hours 0.00255 weeks 5.8597e-4 months the Main Generator was tripped to commence Refuel Outage Q2R14. At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months the Reactor was manually j scrammed. A few load drops were performed due to Weekly Turbine

Testing, however the average daily power level remained at 80% or

greater.

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i III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE 1

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

C. Tests and Experiments Reauirina NRC Anoroval There were no Tests or Experiments requiring NRC approval for the ;

reporting period.

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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 of 10CFR50.73.

UNIT 1 ;

Licensee Event !

Report Number [ Lits Title of occurrence j 97-003 2/21/97 Control Room HVAC Flow Low l 1

UNIT 2 j Licensee Event :

Report Number [Lita Title of occurrence 97-001 2/27/97 HPCI Autostart During IM Surveillance.97-002 2/28/97 PORV testing times slow.

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V. DATA TABULATIONS j 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 i

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j APPENDCC C OPERATING DATA REPORT

. DOCKET NO. 50-254 k UNrr One i

j DATE March 10,1997 COMPLETED BY Kristal Moors 1

TELEPHONE (309) 654-2241 i

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OPERATING STA1VS '

0000 020197 f 1 1. REPORTING PERIOD 2400 022897 OROSS HOURS IN REPORTING PERIOD: 672 l J

2. CURRENTLY AUTHORIZED POWER LEVEL (MWL): 2511 MAX > DEPEND > CAPACfrY: 769 :

DESKIN ELECTRICAL RATING (MWe-NED: 789

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

}~ 4. REASONS POR RESTRICrlON (IF ANY,': l I I THIS MOPEH YR TO DATE CUMULATIVE i 5. NUMBER OF HOURS REACTOR WAS CRrrICAL 672.00 1416.00 165925.20 l

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6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 3421.90 {

7. HOURS GENERATOR ON LINE 672.00 1416.00 - 160944.90

8. UNrr RESERVE SHITFDOWN HOURS 0.00 0.00 909.20 ?

9. GROSS THERMAL ENERGY GENERATED (MWH) 1517642.00 3375842.40 ' 350548724.90 !

10. GROSS ELECIRICAL ENERGY GENERATED (MWH) 491722.00 1098611.00 113520041.00 !

11. NET ELECTRICAL ENERGY GENERATED (MWH) 469572.00 1050569.00 107205538.00 ;

12. REACTOR SERVICE FACTOR 100.00 100.00 76.07 .

13. REACTOR AVAILABILrrY FACTOR 100.00 100.00 77.63

14. UNrr JERVICE FAcrOR 100.00 100.00 73.78 l

15. UNTT AVAILABILTrY FAcrOR 100.00 100.00 74.20 ,

16. UNrr CAPACITY FACTOR (Using MDC) 90.87 96 48 63.91 f

17. UNtr CAPACfrY FACTOR (Using Design MWe) 88.56 94.03 62.29 -

18. UNrr PORCED OUTAGE RATE 0.00 0.00 'i.42 l l

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

20. IF SHITrDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A l

21. UNrr8 IN TEST STATUS (RUOR TO COMMERCLAL OPERATION): N/A FORECAST ACHIEVED ;

INITIAL CRrrlCALITY

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INrrIAL ELECTRICrrY ,

COMMERCIAL OPERATION ;

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, ,^ 'o . ., e 's APPENDIX C OPERATING DATA REPORT

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DOCKErNO. 50-265 i UNrr Two DATE March 10,1997 COMPLETED BY Kristal Moore 'j TELEPHONE (309) 654-224I i OPERATING STATUS 0000 020197

1. REPORTING PERIOD 2400 022897 OROSS HOURS IN REPORTING PERIOD: 672 t i

2. CURRE>rrLY AlfrHORIZED POWER LEVEL (MWO: 2511 MAX > DEPEND > CAPACfrY: 769 ,

DESIGN BIJCmlCAL RATING (MWe-NET): 789

3. POWER LEVEL TO WHICH RESTRICTED OF ANY)(MWe-Neo: N/A f

4. REASONS FOR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE ,

5. NUMBER OF HOURS REACTOR WAS CRTrlCAL 664.30 1408.30 161994.85 l

6. REACTOR RESERVE SHttrDOWN HOURS 0.00 0.00 2985.80 l

7. HOURS GENERATOR ON LINE 663.70 1407.70 157657.05

8. UNIT RESERVE SHtTrDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1647655.20 3477281.20 343149370.02

10. OROS8 BLECTRICAL ENERGY GENERATED (MWH) 530507.00 1118808.00 110135945.00

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11. NET EIJCTRICAL ENERGY GENERATED (MWH) 510548.00 1076518.00 104396239.00 1 J

12. REACIVR SERVICE FACTOR 98.85 99.46 74.80

13. REACTOR AVAILABILITY FACTOR 98.85 99.46 76.18

14. UNrr SERVICE FACTOR 98.76 99.41 72.80

15. UNfr AVAILABILrrY FACTOR 98.76 99.41 73.12

16. UNIT CAPACfrY FACTOR (Using MDC) 98.80 C'i86 62.68

17. UNrr CAPACfrY FACTOR (Using Design MWe) %.29 %.36 61.09

18. UNrr PORCED OlfrAGE RATE 0.00 0.00 11.08

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MObrrHS (TYPE, DATE, AND DURATION OF EACH): 3/1/97

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A PORECA5T ACHIEVED IN' IALCRrrlCALrrY INfr1AL ELECIltlCrrY I COMMERCIAL OPERATION 1.11-9 i

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

-UNIT One DATE March 10. 1997 COMPLETED BY Kristal Moore TEIETHONE (309) 654-2241 MONTH February 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 774 17. 213

2. 784 18, 584

3. 783 19. 619

4. 783 20. 779

5. 783 21. 782

6. 783 22. 772

7. 782 23. 784

8. 767 24. 782

9. 783 25. 783

10. 782 26, 784 11, 782 27. 739

12. 781 28._, s 780

13. 782 29.

14. 621 30.

15. 190 31.

16. 192 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day i 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 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE March 10. 1997 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH February 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 777 17. 779

2. 759 18, 777

3. 778 19, 776

4. 777 20. 776

5. 777 21. 776

6. 777 22. 772

7. 777 23. 766

8. 776 24. 772

9. 756 25. 764

10. 775 26. 770

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11. 776 27. 757

12. 776 28. 391 13, 776 29.

14. 777 30.

15. 777 31.

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16. 771 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. The_e 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 l the restricted power level line). In such cases, the average ( Hly unit power output sheet should be footnoted to explain the apparent anomaly.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE March 10, 1997 REPORT MONTH February 1997 TELEPHONE 309-654-2241 m 2 $ X e, s = n: m:

s j $- E LICENSEE

$8 28 DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS l

9741 2/14/97 F 0 A 5 ------- -- --- Troubiceooting Feedwater Regulating Valve Problems l 1

97-02 2/15/97 $ 0 A 5 --------- --- ----

Reduced load for Main CondenserTube leak l

Testing and Plugging. ;

97-03 2/18/97 F 0 A 5 ----- --- --- ---- Feedwater Regulating Valve Problems.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS

'! DOCKET NO. 50-265 UNIT NAME Two ,, COMPLETED BY Kristal Moore DATE March 10. 1997 REPORT MONTH February 1997 TELEPHONE 309-654-2241 i

M M 2: OE n j

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nob < ou9 sH 9 og eg ,

$ m m E !

$W LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 97-02 2/28/97 5 8.3 C 1 --- -- - --- - Commenced Q2R14 Refuel Outage.

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RESULTS OF SCRAM TIMING MEASUREMENTS -

PERFORMED ON UNIT 1 E 2 CONTROL

ROD DRIVES, FROM 01/01/97 TO O2/28/97

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l AVERAGE TIME IN SECONDS AT % MAX. TIME ,

j INSERTED FROM FULLY WITHDRAWN FOR 90%

1 INSERTIOIf DESCRIPTIOtt NUMBER 5 1 20 ! 50 ! 90 ! l Technical Specification 3.3.C.1 E -

DATE OF RODS 0.375 ! O.900 1 2.00 ! 3.5 7 sec. ! 3.3.c.2 iAveraae Scram Insertion Ti-1

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l 2/17/97 ? 14 i O.314 l 0.712 1 1.528 l 2.671 l 3.010 l STT for Viton Issue U-1 (Core Wid Ave. Times) l l l l (J-14) ll 1

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NitCISCRMTIME.F1tM

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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 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; Two Date: 2/28/97 Valve Actuated: No. & Tvoe of Actuation:

2-0203-3A 1 Manual

. 2-0203-3B 1 Manual 2-0203-3B* 1 Manual 2-0203-3C 1 Manual 2-0203-3D 1 Manual i 2-0203-3E 1 Manual Plant Conditions: Reactor Pressure - 1002 psig Description of Events: Surveillance testing

2-0203-3B was tested twice due to a light bulb burnt out during test.

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 i performed with reactor pressure greater than 800 PSIG. '

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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 300-532 Revision 2 QUAD CITIES REFUELING October 1989 l

INFORMATION REQUEST 4

i 1. Unit: m Reload: M Cycle: is l

2. Scheduled date for next refueling shutdown: 2/on/on l

3. Scheduled date for restart following refueling: 5/29/98

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

No ,

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

e, 5/9/98

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:

Approx. 216 SPC 9X91X Fuel Bundles Q1R15 will be loaded.

7. The number of fuel assemblies.

. a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1991

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

a. Licensed storage capacity for spent fuel: 365

b. Planned increase in licensed storage: 's

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present Ilcensed capacity: 2002 APPROVED ,

(final) OCT 3 01989 14/0395t Q.C.O.S.R.

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. QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: 02 Reload: 13 ,__

Cycle: 14

2. Scheduled date for next refueling shutdown: 3/1/97

3. Scheduled date for restart following refueling: 4/30/97

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

Yes

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

August 1996

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:

216 Siemens 9X9IX Power Corporation Fuel Bundles will be loaded during Q2R14.

7. The number of fuel assemblies.

o a. Number of assemblies in core: 724 4

b. Number of assemblies in spent fuel pool: 97?7

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 3 planned in number of fuel assemblies:

i a. Licensed storage capacity for spent fuel: 3897 Planned increase in licensed storage: 0 b.

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2002 2

! APPROVED ,

(final)

OCT 3 01997 14/0395t O.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 Trantient 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 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 TirHOP3\NRC\ MONTHLY.RIT

ML20137C708

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