Text

Monthly Operating Repts for May 1995 for Quad Cities Nuclear Station Units 1 & 2
	ML20085C057
Person / Time
Site:	Quad Cities
Issue date:	05/31/1995
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-95-054, LWP-95-54, NUDOCS 9506150259
	Download: ML20085C057 (20)
	v • d • e

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Onnmonwealth lihin Onnpany I

Quad Cnin Generating St.ation 22'10 2(thth Atenue North j

Ginlova, 11. 61212 -97 no j

Tcl Sm>51221i LWP-95-054

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June 9, 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 May 1995.

Respectfully, Comed Quad-Cities Nuclear Power Station l

0. Y l^

L. W. Pearce Station Manager

)

LWP/dak Enclosure cc:

J. Martin, Regibnal Administrator C. Miller, Senior Resident Inspector STMGR\\05495 L%7 9506150259 950531 PDR ADOCK 05000254 PDR R

I A l'nkom compan3

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 s

's MONTHLY PERFORMANCE REPORT A

s May 1995

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COMMONWEALTH EDISON COMPANY s,

AND

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IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 N

TintOF1\\NRC\\ MON 1HLY.RPT

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TABLE OF CONTENTS 1.

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 i

A.

Operating Data Report l

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 i

VII.

Refueling Information VIII.

Glossary TECHOPhNRC\\MONU{LY.RTT

i I.

INTRODUCTION 1

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 j

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.

TR'HOfi\\NRC\\ MON 1HLY.RPT

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One began the month of May 1995 at full power and remained on line for the entire month. One load drop was performed per Bulk Power Operations.

B.

Unit Two Quad Cities Unit Two spent the entire month of May 1995 shutdown in Refuel Outage Q2R13. The scheduled startup is June 24, 1995.

TirHOPMNRC\\ MONTHLY.RIT

L III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications l

There were no Amendments to the Facility License or Technical i

Specifications for the reporting period.

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

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T1IHol%NRC\\MONDILY,RPT l

I 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 l

Report Number QAlg Title of occurrence i

There were no licensee event reports for Unit 1 for this reporting period.

UNIT 2 Licensee Event Report Number Q11g Title of occurrence 95-002 5/5/95 Wrong Fuses pulled on Bus 24.

1 TIIMOMWRGMOKnILY.RFI

V.

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

A.

Operating Data Report B.

Average Daily Unit Power Level i

C.

Unit Shutdowns and Power Reductions l

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNrr One DATE 3rw 9,1995 COMPLETED BY Krisaal Moore TELEPHONE (309) 654-2241 OPERATING stall!S 0000 050195

1. REPORTING PERIOD: 2400 053195 GROSS HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTDCAL 744.00 3391.80 155824.30

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 744.00 3336.00 151159.90

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1838656.80 7976329.80 327132453.20

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 591171.00 2573033.00 106036887.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 570166.00 2472677.00 100060643.00

12. REACTOR SERVICE FACTOR 100.00 93.62 76.84

13. REACTOR AVAILABILITY FACTOR 100.00 93.62 78.52

14. UNIr SERVICE FACTOR 100.00 92.08 74.54

15. UNTT AVAILABILITY FACTOR 100.00 92.08 74.99

16. UNIT CAPAcrTY FACTOR (Using MDC) 99.66 88.75 64.16

17. UNIT CAPACirY FACTOR (Using Design MWe) 97.13 86.50 62.54

18. UNrr FORCED OUTAGE RATE 0.00 7.59 7.50 l

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP:

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

TORTIAST ACHIEVED INTrtAL CRrrlCALrrY INITIAL ELEC11tICTTY COMMERCIAL OPERATION 1.1 +9 TTCHOFMNRC\\ MON 1HLY.RPr

1 APPENDIX C OPERATING DATA REPORT DOCKETNO. 50-265 UNIT Two DATE June 9,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 050195

1. REFORTING PERIOD: 2400 053195 GROSS HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MObrTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 0.00 1516.90 151292.75

6. REACTOR REtERVE SHLTTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 0.00 1514.90 147446.55

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS Tl3'1LM AL ENERGi' GENERATED (MWH) 0.00 3363599.00 319304303.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWlO 0.00 1064371.00 102578272.00 l1. NET ELECTRICAL ENERGY GENERATED (MWlO 0.00 1012484.00 97168393.00

12. REACTOR SEJtVICE FACTOR 0.00 41.87 75.18

13. REACTOR AVAILABILfrY FACTOR 0.00 41.87 76.67

14. UNTT SERVICE FACTOR 0.00 41.81 73.27

15. UNTT AVAILABILITY FACTOR 0.00 41.81 73.62 i

16. UNTT CAPACTiY FACTOR (Using MDC) 0.00 36.34 62.79 1

17. UNTT CAPACrrY FACTOR (Using Design MWe) 0.00 35.*2 61.20 1

18. UNTT FORCED OUTAGE RATE 0.00 0.00 9.84

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

20. IF SiltrrDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: 6-24-95

21. UNTFS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION).

FORECAST ACHIEVED INTTIAL CRTTICALTTY 1

INrrIAL ELECTRICrTY COMMERCIAL OPERATION

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1.19-9 11rHOPhNMMON1ElX.RIT

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

DATE June 9. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH May 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net,'.

1.

781 17.

779 2.

782 18.

780 3.

781 19.

781 4.

780 20.

726 5.

779 21.

624 6.

779 22.

721 7.

755 23, 775 8.

777 24.

772 f

9.

778 25.

778 10.

778 26.

776 11.

780 27.

776 12.

779 28.

716 l

13.

778 29.

779 14.

754 30.

763 15.

781 31, 774 16.

779 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 TirHOP3\\NRC\\MONINLY.RPT i

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE June 9. 1993 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH May 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

_(MWe-Net) 1.

-8 17.

-8 l

2.

-8 18.

-8 3.

-8 19.

-8 4.

-8 20.

-8 5.

-8 21.

-8 6.

-8 22.

-8 i

7.

-8 23.

-8 8.

-8 24.

-8 9.

-8 25.

-8 10.

-8 26.

-8 11.

-8 27.

-8 12.

-8 28.

-8 13.

-8 29.

-8 14.

-8 30.

-8 15.

-8 31.

16.

-8 i

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.

Tnese 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 TirHor3\\NRC\\ MONTHLY.RPT

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

}0-254 UNIT NAME One COMPLETED BY Kristal Moore DATE June 9, 1995 REPORT MONTH May 1995 TELEPHONE 309-654-2241 a:

O m

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E8 0

855 EE lE h

c m

E4 LICENSEE O

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS e5m4 5-21-95 5

0-F 5

Reduced load due to Bulk Power Operations.

UTHOP3tNROMONTHLY.RIT

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE June 9, 1995 REPORT MONTH June 1995 TELEPHONE 309-654-2241 a:

E26 E

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ap<

08 E

8E 28 28 9

A H

$m m

M LICENSEE o

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS o

NO.

DATE (HOURS)

REPORT Continued Refuel Outage Q2R13.

95-05 05-01-95 5

744 0 C

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

A.

Main Steam Relief Valve Operations i

There were no Main Steam Relief Valve Operations for the reporting period.

l 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, t

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T1040MWRCWONTHLY.RIT j

i VII.

REFUELING INFORMATION The following information about future,

. ads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.

0'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 INFORMATION REQUEST 14 1.

Unit:

Q1 Reload:

13 Cycle:

2.

Scheduled date for next refueling shutdown:

2/5/96 3.

Scheduled date for restart following refueling:

5/15/96 l

4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other Ilconse amenda nt:

i No l

S.

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

7-4-95 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:

200 GE10 Fuel Bundles will be loaded during Q1R14.

]

1 7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1717 8.

The present 11 censed 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 assembiles:

a.

Licensed storage capacity for spent fuel:

3657 I

b.

Planned increase in licensed storage:

0 9.

Theprojecteddateofthelastrefuelingthatcanbedischargedtothe spent fuel pool assuming the present 11 censed capacity: 200 APPROVED l

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

QTP 300-532 c'

Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unlt:

Q2 Reload:

13 I'

Cycle:

3-5-95 2.

Scheduled date for next refueling shutdown:

3.

Scheduled date for restart following refueling:

6-24-95 4.

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

NO 5.

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

Approved June 10, 1994 6.

Important Ilconsing 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 be loaded during Q2R13.

7.

The number of fuel asseabiles, a.

Number of assfeblies in core:

0 b.

Number of assemblies in spent fuel pool:

3451 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 11 censed capacity: 2006 APPROVED e

(f1nal)

W30W 14/0395t C).C.O.S.R.

I 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

- Averr.ge Power Range Monitor ATWS