Text

Monthly Operating Repts for Mar 1996 for Quad Cities Units 1 & 2
	ML20101R057
Person / Time
Site:	Quad Cities
Issue date:	03/31/1996
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-96-037, LWP-96-37, NUDOCS 9604160028
	Download: ML20101R057 (20)
	v • d • e

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- *,4bmmonwealth Ediwn Comp.iny

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Quad,Citics Generating Station 2G10 206th Avenue North

. Cordova, 11.61242 9740 Tel 3W6512241 I

LWP-96-037 April 10, 1996 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 1996.

Respectfully, Comed Quad-Cities Nuclear Power Station

/

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.il.[ea<rce l GC -

Station Manager LWP/dak Enclosure cc:

H. Miller, Regional Administrator C. Miller, Senior Resident Inspector smaamm j

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9604160028 960331 PDR ADOCK 05000254 p i R

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT March 1996 COMMONWEALTH EDIS0N COMPANY AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 11iCHOP3\\NRC\\ MONTHLY.RFT

1 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 IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level 4

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 1TCHOP3\\NRCudONTHLY.RPT

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1.

INTRODUCTION l

l Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in t

Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Mid-American Energy Company. The Nuclear Steam Supply Systems are l

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 l

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 a

l 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.

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

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

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4 II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One spent the month of March,1996 shutdown in Refuel Outage Q1R14. The scheduled start-up date is April 28, 1996.

B.

Unit Two Quad Citics Unit Two began the month of March, 1996 on line. On March 4,1996, a load drop was performed to troubleshoot the #2 Turbine Control Valve oscillations. The Main Turbine was tripped on March 5, 1996 at 02:57 hours to replace the #2 Turbine Control Valve servo.

The generator was sync to the grid on March 5, 1996 at 11:27 hours.

The Unit remained :n line for the rest of the month.

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I TECHOP)\\NRC\\ MON 1HLY.RPT

III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications 1

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

B.

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

C.

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

i 1TCHOP3\\NRC\\ MON 1MLY,RPT

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.

UNIT 1 Licensee Event Report Number Qalg Title of occurrence 96-008 2/25/96 Control Room "B" Train IN0P from a freon leak. (THIS WAS DOWNGRADED ON 3/21/96)96-001 3/4/96 Control Room HVAC IN0P UNIT 2 Licensee Event Report Number Dalg Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

TECHOPS\\NRC\\ MON 1MLY,RI"T

. _..._ = _ =

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V.

DATA TABULATIONS The following data tabulations are presented in this report:

1 A.

Operating Data Report B.

Average Daily Unit Power Level l

C.

Unit Shutdowns and Power Reductions l

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l TECHOP3\\NRC\\ MON 1ELY.RPT

1 APPENDIX C OPERATING DATA REPORT DOCKETNO. 50-254 UNIT One DATE April 10,1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 0301 %

1. REPORTING PERK)D: 2400 033196 OROSS HOURS IN REPORTING PEIUOD: 744

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

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe-Ne0: N/A

4. REASONS FOR REST 10CT10N (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrriCAL 0.00 964.10 161427.60

6. REACTOR RESERVE SHtTTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 0.00 963.20 156722.40

8. UNTT RESERVE SHttrDOWN HOURS 0.00 0.00 909.20

9. GRo6s THERMAL ENERGY GENERATED (MWH) 0.00 2288399.50 340694197.10 l

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 7343 %.00 110348477.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 699244.00 104173620.00

12. REACTOR SERVICE FACTOR 0.00 44.14 76.83 a

13. REACTOR AVAILABILrrY FACTOR 0.00 44.14 78.46

14. UNrr SERVICE FACTOR 0.00 44.10 74.59

15. UNrr AVAILABILrrY FACTOR 0.00 44.10 75.02

16. UNIT CAPACfrY FACTOR (Using MDC) 0.00 41.63 64.47 1

17. UNTT CAPActrY FACTOR (Using Design MWe) 0.00 40.58 62.84

18. UNTT FORCED OLTTAGE RATE 0.00 0.00 7.54

19. SHirrDOWNS SCHEDULED OVER NEXT 6 MOPrrHS (TYPE, DATE, AND DURATION OF EACH): Rebel,2/10/96 diru 4/28/96 1

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

21. UNrrS IN TEST STATUS (PIUOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrrtAL CRrriCALTTY INTR 1AL ELECTIUCffY COMMERCIAL OPERATION 1.1< >-9 TECHOP3\\NRC\\ MON 1MLY.RFr

APPENDIX C OPERATING DATA REPORT DOCKET NO.

50 265 UNTT Two DATE April 10,1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 030196

1. REPORTING PERIOD: 2400 0331% OROSS HOURS IN REPORTING PERIOD: 744

2. CURREPrrLY AITTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECMICAL RATING (MWe-NET): 789

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

4. REASONS POR RESTRICTION (IF ANY):

THIS MOPrrH YR TO DATE CUMULATIVE

3. NUMBER OF HOURS REACTOR WAS CRTrlCAL 744.00 2184.00 156254.45

6. REACIDR RESERVE SHtTTDOWN HOURS 0.00 0.00 2985.80

7. HOURS OENERAER Off LINE 735.50 2175.50 152075.05

8. UNTT RESERVE SHITTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1810337.80 5344964.60 32 % 86I85.52

10. OROSS ELECTRICAL ENERGY GENERATED (MWH) 577677.00 1714297.00 105859832.00

11. NEr ELECTRICAL ENERGY GENERATED (MWH) 558063.00 1649402.00 100302288.00

12. REACTOR SERVICE FACIDR 100.00 100.00 74.92

13. REACTOR AVAILABILTTY FACrOR 100.00 100.00 76.35

14. UNTT SERVICE FACrOR 98.86 99.61 72.92

15. UNTT AVAILABILTTY FACTOR 98.86 99.61 13.26

16. UNTT CAPACrrY FACTOR (Using MDC) 97.54 98.21 62.54

17. UNTT CAPACfrY FACrOR (Uning Design MWe) 95.07 95.72 60.96

18. UNrr FORCED OUTAGE RATE 0.00 0.00 10.17

19. SHITTDOWNS SCHEDULED OVER NEXT 6 MOPrrHS (rYPE, DATE, AND DURATION OF EACH): N/A

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

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A 1

{

FORECAST ACHIEVED i

INTTIAL CRrrlCALTTY iNrrIAL ELECTRICTTY l

COMMERCIAL OPERATION l

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE April 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH March 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-8 17.

-7 2.

-8 18.

-8 3.

-8 19.

-8 4.

-8 20.

-8 5.

-8 21.

-8 6.

-8 22.

-8 7.

-8 23.

-7 l

8.

-8 24.

-7 9.

-8 25.

-8 10.

-8 26.

-8 11.

-8 27.

-8 12.

-8 28.

-7 13.

-7 29.

-7 14.

-7 30.

-7 15.

-8 31.

-7 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.

1.16-8 1TCHOP3\\NRC\\ MONTHLY RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE April 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH March 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 1.

777 17.

740 2.

779 18.

775 3.

767 19.

776 4.

558 20.

776 5.

253 21.

779 6.

766 22.

779 7.

774 23.

770

)

8.

777 24.

779 9.

777 25.

780 10.

770 26.

781 11.

774 27.

780 12, 774 28.

780 13, 773 29.

780 14.

744 30.

774 15.

774 31.

781 16.

773 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 11 CHOPS \\NRC\\MONTMLY.RPT i

l APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME One COMPI.ETED BY Kristal Moore DATE Anril 10, 1996 REPORT MONTH March 1996 TELEPHONE 309-654-2241 5

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20 D =

LICENSEE DURATION EVENT No.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 96-02 03/01/96 s

744.0 C

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-265 UNIT NAME ho COMPLETED BY Kristal Moore DATE Aoril 10, 1996 REPORT MONTH March 1996 TELEPHONE 309-654-2241 g"it h lM En E

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28 2 8 C

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LICENSEE O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT 9643 03/04/96 F

0 A

5 Load Drop to Troubleshoot #2 Turbine Control Valve oscillating from 50% to full closed.

96-04 03/05/96 F

8.5 A

9 Tripped turbine to replace the #2 Turbine Control Val /e Servo.

TECHOP3\\NRCu(ONTHLY.RPT

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

A. Main Steam Relief Valve Ooerations 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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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.

TECHOP3\\NRC\\n40N1MLY.RFT

QTP 300-532 t

Revision 2 1

QUAD CITIES REFUELING October 1989 j'

INFORMATION REQUEST f

1.

' Unit:

01 Reload:

14 Cycle:

15 j

2.

Scheduled date for next refueling shutdown:

2/10/96 4

3.

Scheduled date for restart following refueling:

4/28/96 i

4.

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

NO i

1 5.

Scheduled date(s) for submitting proposed licensing act' ton and j

supporting information:

i 6-1-96 i

a j

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 j

procedures:

232 GE10 Fuel Bundles will be loa'ded during Q1R14.

l 1

d 2

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1701 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 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 Itcensed capacity:

4 APPROVED (final)

DCT 3 01989 14/0395t Q.C.O.S.R.

QTP 300-532 Revision 2 QUAD CITIES REFUELfNG October 1989 1

INFORMATION REQUEST

~

1.

Unit:

Q2 Reload:

13 I'

Cycle:

2.

Scheduled date for next refueling shutdown:

1-6-97 3.

Scheduled date for restart following refueling:

3-30-97 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 licensing action and supporting information:

November, 1996 6.

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

Approx. 224 Siemens 9X9IX Power Corporation Fuel Bundles will be loaded during Q2R14.

7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2727 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:

AP ROVED (final) 14/0395t OCT 3 01989 C1.C.O.S.R.

A

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