Text

Monthly Operating Repts for Oct 1994 for Quad Cities Nuclear Station
	ML20078M430
Person / Time
Site:	Quad Cities
Issue date:	10/31/1994
From:	Aitken P, Moore K; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	PCA-94-003, PCA-94-3, NUDOCS 9412020083
	Download: ML20078M430 (20)
	v • d • e

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O 2271o 206 Avenue North Commonwealth Edison Quad Cities Nuclear Power Station Cordova, Illinois 61242 Telephone 309/654-2241 PCA-94-003 November 7, 1994 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

)

i Enclosed for your information is the Monthly Performance Report covering the i

operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of October 1994.

Respectfully, Comed Quad-Cities Nuclear Power Station YbPaulC.Ait'h, ken System Engineering Supervisor AMS/dak Enclosure cc:

J. Martin, Regional Administrator C. Miller, Senior Resident Inspector 020003 nrHOPhNMMONTHl Y.Rri 9412O20083 941031 DDR ADOCK 05000254 i

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QUAD-CITIES NUCLEAR POWER STATION L

UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT October 1994 COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE il0S. DPR-29 AND DPR-30 l

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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 D.

Corrective Maintenance of Safety Related Equipment 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 Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary i

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INTRODUCTION 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 t

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

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SUMMARY

OF OPERATING EXPERIENCE A.

Unit One i

Quad Cities Unit One was taken off-line October 2, 1994, at 1644 and' the reactor was manually scrammed at 1715.

This was due to differential temperature of the recirculation loops greater than 50 l

degrees during single loop operation which exceeded Technical Specification limits.

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l B.

Unit Two Quad Cities Unit Two was taken off-line October 3, 1994, at 1055 and deal with a combination of equipment problems and personnel

l the reactor was manually scrammed at 1128.

This action was taken to performance. issues.

Both units are expected to be on-line by the middle of November, 1994'.

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l III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE i

A.

6mendments to Facility License or Technical Soecifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Chanaes Reouirina NRC Acoroval Revision 1.1 to the Offsite Dose Calculation Manual (0DCM) was Onsite Reviewed and accepted on October 5, 1994.

The revision incorporates the following changes:

Clarification of standard Technical Specification requirements or guidance.

Update information on IRSFs and DAW Facilities.

Update recent ODCM based on recent Technical Specification changes.

Update of proposed Generic Letter.

Provide optional Uniform REMP Program.

The changes effected Chapter 1,2,3,4,5,6,7,8,9 and Appendix A, B, C, D, E and is documented in Onsite Review Report Number 94-21.

l C.

Tests and Experiments Reauirina NRC ADoroval 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 Qate Title of occurrence 94-012 10-11-94 DW Hi Pressure Switches out of T.S.94-013 10-07-94 EDG HVAC 94-014 10-14-94 CRD High Point Vent Valves95-015 10-02-94 Recirculation loop greater than 50 degrees during single loop operation which exceeded Technical Specification limits.

UNIT 2 Licensee Event Report Number Dalg Title of occurrence 94-011 10-06-94 RHRSW Pump work exceeded LCO time frame.

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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 C.

Unit Shutdowns and Power Reductions ununsacmasnux.arr j

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNrr One DATE November 7, 1994 COMPLETED BY Kristal Moore TELEPilONE (309) 654-2241 OPFRATING STATUS 0000 100194

1. REPORTING PERIOD: 2400 103194 GROSS HOURS IN REPORTING PERIOD: 744 2, CURRENTLY AUTIIORIZED POWTR LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECI'RICAL RATING (MWe-NET): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTil YR TO DATE CUMULATIVE

5. NUMf1ER OF llOURS REACTOR WAS CRTTICAL 41.20 2651.20 152432.50

6. REACTOR RESERVE SHUTDOWN llOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 40.70 2527.60 147823.90

8. UNIT RESERVE SliUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 69114.90 5462936.20 319156123.40

10. G2OSS ELECTRICAL ENERGY GENERATED (MWH) 23502.00 1765735.00 103463854.00

11. NrT ELECTRICAL ENERGY GENERATED (MWH) 15741.00 1670168.00 97588166.00

12. REACTOR SERVICE FACTOR 5.54 36.34 77.10

13. REACTOR AVAILABILTTY FACTOR 5.54 36.34 78.83

14. UNTT SERVICE FACTOR 5.47 34.65 74.77

15. UNrr AVAILABILITY FACTOR 5.47 34.65 75.23

16. UNTT CAPACfrY FACIT)R (Using MDC) 2.75 29.77 64.19

17. UNrr CAPACTTY FACTOR (Uning Design MWe) 2.68 29.02 62.56

18. UNIT FORCED OUTAGE RATE 94.50 22.31 6.63

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

20. IF SIIUTIX)WN AT END OF REM)RT PERIOD < ESTIMATED DATE OF STARTUP:

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

FORECAST AClilEVED INITIAL CRTTICALTTY INTTIAL ELECTRICITY COMMERCI AL OPERATION 1.16-9 TICHolWWC\\ MONTH 1.Y RI'r

F APPENDIX C l

OPERATING DATA REPORT j

I DOCKET NO.

50-265 UNTT Two DATE November 7, 1994 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS i

0000 100194

1. REPORTING PERIOD: 2400 103194 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 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 CRrrICAL 59.50 5472.60 149373.65

6. REACTOR RESERVE SHITFDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 58.90 5395.20 145578.35

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWII) 132979.10 12762676.60 315543638.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 42777.00 4088682.00 101398452.00

11. NL'r ELECTRICAL ENERGY GENERATED (MWII) 34796.00 3908444.00 96051004.00

12. REACTOR SERVICE FAcrOR 8.00 75.02 76.15

13. REACTOR AVAILABILrrY FACTOR 8.00 75.02 77.68

14. UNTT SERVICE FACTOR 7.92 73.96 74.22

15. UNTT AVAILABILITY FACTOR 7.92 73.96 74.58

16. UNrr CAPACfrY FACTOR (Uning MDC) 6.08 69.67 63.68

17. UNIT CAPACrrY FACTOR (Using Design MWe) 5.93 67.90 62.06

18. UNTT FORCED OUTAGE RATE 92.08 26.04 9.33

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

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

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

FORECAST ACHIEVED INITIAL CRITICALTTY INTilAL ELECTRICTTY COMMERCI Al. OPERATION 1.16-9 TirHOP3\\NRCiHONTMLY.Rli

4 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 I

UNIT One DATE November 7. 1994__

COMPLETFD BY Kristal Moore TELEPHONE (309) 654-2241 MONTH October 1994 DAY AVERAGE DAILY POWE'A LEVEL DAY AVERAGE DAILY POWER LEVEL

{

(MWe-Net)

(MWe-Net) 1.

777 17.

-8 i

2.

153 18.

-9 3.

-10 19.

-9 4.

-10 20.

-9 l

5.

-9 21.

-9 6.

-8 22.

-9 7.

-8 23.

-9 8.

-8 24.

-9 9.

-9 25.

-9 10.

-8 26.

-10 11.

-8 27.

-10 12.

-8 28.

-9 13.

-9 29.

-9 14.

-9 30.

-9 15.

-8 31.

-9 16.

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INSTRUCTIONS On this form, list the average daily unit power level in HWe-Net for each day i

in the reporting month.

Compute to the nearest whole megawatt.

These figures i

I will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is ased for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or j

the restricted power level line).

In such cases, the average daily unit power output shaet 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 November 7. 1994 COMPLETED BY Kristal Moore TELEPHONE 1309) 654-2241 MONTH October 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

760 17.

-8 2.

760 18.

-8 3.

174 19.

-9 4.

-10 20.

-9 5.

-8 21.

-9 6.

-8 22.

-9 7.

-8 23.

-9 8.

-8 24.

-9 9.

-8 25.

-9 10.

-8 26.

-9 11.

-8 27.

-9 12.

-8 28.

-9 13.

-8 29.

-9 14.

-8 30.

-9 15.

-8 31.

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-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 dtily 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 Oe COMPLETED BY Kristal Moore U24IT NAME J

DATE November 7, 1994 REPORT MONTH Jctober 1994 TELEPHONE 309-554-2241 u

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DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 94 4105 10-2-94 F

703.3 2

Differential Temperature of the Recire loops G

greater than 50' during single loop operation.

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i APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE Novert.ber 7, 1994 REPORT MONTH November 1994 TELEPHONE 309-654-2241 K

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS JO.

DATE (HOURS)

REPORT Equipment problems and personnel 94-15 1043-94 F

6581 2

performance issues.

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VI. UNIOUE REPORTING REQUIREMENTS 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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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 ~,ities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

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L, QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST q

1.

Unit:

01 Reload:

13 14 Cycle:

2.

Scheduled date for next refueling shutdown:

1-4-96 3.

Scheduled date for restart following refueling:

5-9-96 4.

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

No S.

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

7-4-95 6.

Important Ilconsl~ considerations associated with refueling, e.g., new or different fuel ossign or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating i

procedures:

7.

The number of fuel assemblies.

i a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1717 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or 1s-planned in number of fuel assemblies:

Y a.

Licensed storage capacity for spent fuel:

3657 f

b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can be discharged to the i

spent fuel pool assuming the present licensed capacity:

2006 i

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APPROVED 14/0395t O.C.O.S.R.

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e QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 i

INFORMATION REQUEST 1.

Unit:

02 Reload:

12 Cycle:

13 2.

Scheduled date for next refueling shutdown:

3-5-95 3.

Scheduled date for restart following refueling:

7-9-95 4.

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

YES - Safety limit MCPR to be changed from 1.06 to 1.07 due to GE10 Fuel.

Change TS at end of Cycle 13 operation.

5.

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

Approved June 10, 1994 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:

144 CE10 fuel bundles will be loaded during Q2R13-.

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 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 d&te of the last refueling that can-be discharged to the spent fuel pool. assuming the present licensed capacity: 2006 i

APPROVED 14/0395t

-I-OCT 3 01989 0.C.O.S.R.

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l VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, l