Text

Monthly Operating Repts for Jan 1995 for Quad Cities Nuclear Station Units 1 & 2
	ML20078P392
Person / Time
Site:	Quad Cities
Issue date:	01/31/1995
From:	Aitken P, Moore K; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	PAC-95-013, PAC-95-13, NUDOCS 9502170046
	Download: ML20078P392 (21)
	v • d • e

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Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 PCA-95-013 February 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 January 1995.

Also, please find attached the revised Appendix C on Unit 2 for the month of December.

Respectfully, Comed Quad-Cities Nuclear Power Station 6-C Paul C. Aitken System Engineering Supervisor PCA/dak Enclosure cc:

J. Martin, Regional Administrator C. Miller, Senior Resident Inspector fff 160002 nrnornsacatorm13.RPT 9502170046 950131 PDR ADOCK 05000254 R

PDR

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT January 1995 COMONWEALTH EDIS0N COMPANY i

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

1 nons-ma.m

l TABLE OF CONTENTS I.

Introduction i

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 i

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 Velve Operations B.

Control Rod Drive Scram Timing Data

-VII.

Refueling Information VIII.

Glossary TintOP3WROMONDILY.RPT

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I.

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 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.

11Ih0PhNRC\\ MON 1RLY.RIT

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One started the month of January 1995 shutdown in a forced outage. The reactor was made critical on January 10, at 1513 hours0.0175 days 0.42 hours 0.0025 weeks 5.756965e-4 months and the generator was synchronized to the grid on January 12, at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . A load reduction was performed to do repairs on the 1A2 Flash Tank.

B.

Unit Two Quad Cities Unit Two began the month of January 1995 at full capable load and remained on line through out the month.

On January 12 at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months , Unit 2 dropped load for Condensate Demineralizer backwash and precoat. Also on January 22 and January 26 load drops were performed due to problems with the Condensate Demineralizers such as high silica, plugged post strainer and high conductivity.

A few other load drops were performed but none caused the average daily unit power level to drop by 20% or greater.

l nrHOISWROMOKmLY.RN

III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE 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 Chanaes Reouirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

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

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t 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 Q1Lg Title of occurrence 95-001 01/02/95 RCIC IN0P 1

95-002 01/20/95 CR HVAC INOP 95-003 01/25/95 Tip System response to a PCIS Signal UNIT 2 Licensee Event Reoort Number Q11g Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period.

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l V.

DATA TABULATIONS

]

i The following data tabulations are presented in this report:

l A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 11IHOP3WRC\\ MONTHLY.RIT

1 t

APPENDDC C A

f OPERATING DATA REPORT

[

DOCKET NO.

50-254 UNIT One DATE February 9,1995 i

COMPLETED BY Kristal Moore i

TELEPHONE (309) 654-2241 OPERATING STATUS 0000 010194

1. REPORTING PERIOD 2400 013194 GROSS HOURS IN REPORTING PEluOD: 744

2. CURRENTLY ALT'.HORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPActrY: 769 DESIGN ELECIkiCAL 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 10 DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 512.80 512.80 152945.30

6. REACTOR RESERVE SHLTTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 457.00 457.00 148280.90

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. OROS$ THERMAL ENERGY GENERATED (MWH) 882951.90 882951.90 320039075.30

10. OROSS ELECTRICAL ENERGY OENERATED (MWH) 281020.00 281020.00 103744874.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 265985.00 265985.00 97854151.00

12. REACTOR SERVICE FACTOR 68.92 68.92 76.50

13. REACTOR AVAILABILrrY FACTOR 68.92 68.92 78.22

14. UNIT SERVICE FACTOR 61.42 61.42 74.17

15. UNrr AVAILABILITY FACTOR 61.42 61.42 74.63

16. UNIT CAPACfrY FACTOR (Using MDC) 46.49 46.49 63.65

17. UNIT CAPACfrY FACTOR (Using Design MWe) 45.31 45.31 62.04

18. UNIT FORCED OLTTAGE RATE 38.58 38.58 7.63

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

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

21. UNrrs IN TEST STATUS (PIUOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALrrY iNrnAi. EtECrRiCrrY COMMERCIAL OPERATION j

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I APPENDEX C OPERATING DATA REPORT DOCKET No.

50-265 l

UNIT Two

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DATE February 9,1995 COMPLETED BY Krissal Moore l

TELEPHONE (309) 654 2241 OPERATING STATUS i

0000 010194

1. REPORTING PERIOD: 2400 013194 GROSS HOURS IN REPORTING PERIOD 744

2. CURRENTLY AttrHORIZED 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 POR RESTRICTION (IF ANY):

]

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 744.00 744.00 150519 65

6. REAC1DR RESERVE SHlfrDOWN HOURS 0.00 0.00 2985.80 i

l

7. HOURS GENERATOR ON LINE 744.00 744.00 146675.65

8. UNfr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1655253.30 1655253.30 317595957.40

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 524392.00 524392.00 102038293.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 501116.00 501116.00 96657025.00

12. REACTOR SERVICE FACTOR 100.00 100.00 75.88

13. REACTOR AVAILABILITY FACTOR 100.00 100.00 77.39 l

14. UNrr SERVICE FACTOR 100.00 100.00 73.95

15. UNrr AVAILABILTTY FACIDR 100.00 100.00 74.30

16. UNfr CAPActrY FACTOR (Using MDC) 87.59 87.59 63.37

17. UNTT CAPACTTY FACTOR (Using Design MWe) 85.37 85.37 61.76

18. UNrr FORCED OUTAGE RATE 0.00 0.00 9.88

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

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

21. UNTFS IN TEST STATUS (PIUOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRrflCALITY INTR!AL ELECTRICTTY COMMERCIAL OPERATION 1.13-9 TirHOIMNitC\\ MONTHLY.RPT

., -.... _ _ _,. _. ~., _... _,, _ _,. _ -

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t APPENDIX C t

OPERATING DATA REPORT (Rev*med December 1994) i DOCKITNo. 50-265 I

UNrr Two DATE January 9,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS j

0000 120194 I. RSPORTING PERIOD: 2400 123194 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHOkIZED POWER LEVEL (MW): 2511 MAX > DEPEND > CAPACfrY: 769 DEslGN ELECTRICAL RATING (MWe-Nirr): 789 f

i

3. POWER LEVELTO WHICH RES1RICTED(IF ANY)(MWe-Net): N/A

4. REASONS POR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 402.20 5874.80 149775.85

6. REACIDE RESERVE SHITTDOWN HOURS 0.00 0.00 2985.80

[

7. HOURS GENERATOR ON IJNE 353.30 5748.50 145931.65

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 397,065.60 12779221.00 315560182.90 f

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 115449.00 4204131.00 101513901.00 1

11. NErr ELECTRICAL ENERGY GENERATED (MWH) 104905.00 4013349.00

% 155909.00 f

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12. REACTOR SERVICE FACIDR 54.06 67.07 75.79 J

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13. REACTOR AVAILABILrrY FACTOR 54.06 67.07 77.30 f

14. UNrr SERVICE FACTOR 47.49 65.63 73.85 i

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15. UNir AVAILABILrrY FACTOR 47.49 65.63 74.20

16. UNrr CAPACfrY FACTOR (Uning MDC) 18.34 59.58 63.28 i

17. UNIT CAPACfrY FACTOR (Unin8 Design MWe) 17.87 58.07 61.67

18. UNrr FORCED OUTAGE RATE 52.51 34.37 9.93

19. SHITTDOWNS SCHEDULED OVER NEXT 6 MO!RHS (rYPE, DATE. AND DURATION OF EACH):

[

i

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

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

FORECAST ACHIEVED INITIAL CRrrlCALrrY INrrlAL ELFCTRICrrY I

i COMMERCIAL OPERATION a

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE February 9. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH January 1995 DAY AVERAGE DAILY POWER LEVEL CAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-8 17.

564 i

2.

-8 18.

665 3.

-8 19, 670 4.

-8 20.

668 5.

-8 21.

666 6.

-8 22.

455 7.

-8 23.

759 8.

-9 24.

762 9.

-8 25.

771 10.

-8 26.

771 11.

-9 27.

770 12.

-7 28.

768 13.

129 29.

764 14.

143 30.

769 15.

142 31.

769 16.

171 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 TICHolWRC\\ MONTHLY.RIT a

B APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE January 9. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 l

HONTH January 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) l.

610 17, 750 2.

607 18.

754 3.

609 19.

753 4.

637 20.

753 5.

721 21.

754 6.

710 22.

662 7.

721 23.

703 8.

717 24.

751 9.

706 25.

754 10, 709 26.

520 11.

703 27.

463 12.

633 28.

470 13.

629 29.

470 14.

669 30.

732 i

15.

726 31.

750 16.

720 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 l

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 i

output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TinIOIMRC\\ MON 1HLY. PIT

APPENDIX D i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore 1

DATE February 9.

1995 REPORT MONTH January 1995 TELEPHONE 309-654-2241 P l H

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$8 LICENSEE 8

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS95-001 01-1-95 F

287.0 0

2 254 4 4-015 Continued Fon:ed Outage.

Lead Drup for 1 A2 Flash Tank Repairs.

93 002 01-22-95 0.0 A

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1TrHOP3\\NRC\\ MONTHLY.RIT l

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE February 9, 1995 REPORT MONTH January, 1995 TELEPHONE 309-654-2241 m

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS 1

NO.

DATE (HOURS)

REPORT i

Drop load for 'E' Condensate Demineralizer 9541 01-12-95 B 5

Backwash & Precoat 95-02 01-22-95 A 5

Dmp load for 'B' Condensate Demineralizer for high silica, and "D* Condensate Demin plugged post strainer.

Load drop for Condensate Demineralizer 95-03 01-26-95 A 5

problems and high conductivity.

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TirHOP3\\NRC\\ MONTHLY.RIT

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VI. UNIOUE REPORTING RE0VIREMENTS l

1 The following items are included in this report based on prior commitments to 4

the commission:

A.

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

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 1

I 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 performed with reactor pressure greater than 800 PSIG.

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RESULTS OF SCRAM TIMING MEASUREMENTS

?*-

PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/95 TO 12/31/95 l AVERAGE TIME IN SECONDS AT %

l MAX. TIME l

\\

INSERTED FROM FULLY WITHDRAWN

] FOR 90%

! INSERTION !

DESCRIPTION

) NUMBER l

5 l

20 50 1

90 l

Technical Specification 3.3.C.1 &

___DATE

! OF RODS

! 0.375 ! O.900 2.00 3.5 7 sec.

3.3.C.2 (Averaoe Scram Insertion Time)

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01/15/90 177 l 0.31

! O.70 1.47 2.57 l

3.30 l

Post Maintenance after Q1F35 Seq A, B, Done

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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.

TliCHOP3\\NRC\\ MONTHLY.RIT

QTP 300-532 Revision 2 l

QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST l'

I.

Unit:

01 Reload:

13 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 license amendment:

No 5.

Scheduled date(s) for submitting. proposed licensing action and j

supporting information:

)

7-4-95 6.

Important Ilconsing considerations associated with refuell.ig, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

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 licensed spent fuel pool storage capacity and the size of any increase in Itcensed 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 g.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present Ilconsed capacity:

2006

't APPROVED (final)

E30W 14/0395t Q.C.O.S.R.

=-...

Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

o2 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 and of Cycle 13 operation.

5.

Scheduled date(s) for submitting proposed !! censing 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 analysts methods, significant changes in fuel design, new operating procedures:

144 GE10 fuel bundles will be loaded during Q2R13.

7.

The nu der of fuel assemblies.

a.

Number of assemblies la 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 1lconsed 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: 2006 i

APPROVED i

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14/03g5t DCf 3 059 Q.C.O.S.R.

I

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VIII.