Text

Monthly Operating Repts for Jan 1997 for Quad Cities Nuclear Station,Units 1 & 2
	ML20138M012
Person / Time
Site:	Quad Cities
Issue date:	01/31/1997
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-97-015, LWP-97-15, NUDOCS 9702250229
	Download: ML20138M012 (19)
	v • d • e

,.

f Commonwealth Illiwn Company Quad Citics Generating Station 22710 2(Lth Avenue North

)

Cordos a. IL 61212 9710 Tel.409M 4-2211 i

LWP-97-015 February 10, 1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l

Washington, D.C. 20555

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

i Respectfully, Comed Quad-Cities Nuc ear Power Station bL1 L),.Pearce W

Station Manager LWP/dak if Enclosure cc:

A. Beach, Regional Administrator C. Miller, Senior Resident Inspector

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SutGRiol597.LWP 9702250229 970131 PDR ADOCK 05000254 R

PDR r;

A i nicom Company

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l QUAD-CITIES NUCLEAR POWER STATION

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UNITS 1 AND 2 1

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l MONTHLY PERFORMANCE REPORT JANUARY 1997 COMMONWEALTH EDISON COMPANY i

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AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 r

LICENSE NOS. DPR-29 AND DPR-30 i

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TABLE OF CONTENTS 1

I.

Introduction l

II.

Summary of Operating Experience j

l 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 i

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 C.

Unit Shutdowns and Power Reductions VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data j

VII.

Refueling Information VIII.

Glossary

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I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reacters and Steam Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Mid-American Energy 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, respectively.

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II.

SUMMARY

OF OPERATING EXPERIENCE

-i A.

Unit One Quad Cities Unit One was on-line the entire month of January 1997. A few load drops were performed, however the average daily power level remained at 80% or greater.

B.

Unit Two Quad Cities Unit Two was on-line the entire month of January 1997. On January 9,1997, a load drop was performed to troubleshoot the 2C1 Feedwater Heater operating vent leak. The leak was repaired and the unit was brought up to full power on January 12, 1997.

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A l

III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE i

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 Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for i

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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IV.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-l Cities Units One and Two occurring during the reporting period, pursuant to 1

the reportable occurrence reporting requirements of 100FR50.73.

UNIT 1 Licensee Event l

Report Number D11g Title of occurrence i

97-001 1/10/97 Technical Specification required l

instrumentation readings were not completed within the required time frequency after changing from eight hour to twelve hour shifts because the consequences associated with changing shift duration were not adequately reviewed or assessed.97-002 1/27/97 Piping may experience stresses above l

FSAR allowables.

UNIT 2 Licensee Event Reoort Number Data Title of occurrence There were no LER's for Unit 2 during the month of January.

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l V.

DATA TABULATIONS l

The following data tabulations are presented.in this report:

A.

Operating Data Report 8.

Average Daily Unit Power Level i

C.

Unit Shutdowns and Power Reductions l

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l APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 l

UNTT One l

DATE February 10 i

1997 i

l COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 010197

1. REPORTING PERIOD: 2400 013197 GROSS HOURS IN REPORTINO PERIOD: 744

2. CURRENTLY AITTHORIZED 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 MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 744.00 744.00 165253.20

6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 744.00 744.00 160272.90

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1858200.00 1858200.00 349031082.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 606889.00 606889.00

!!3028319.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 580997.00 580997.00 106735 % 6.00

12. REACTOR SERVICE FACTOR 100.00 100.00 75.99 l

13. REACTOR AVAILABILTTY FACTOR 100.00 100.00 77.57

14. UNTT SERVICE FACTOR 100.00 100.00 73.70

15. UNTT AVAILABILITY FACTOR 100.00 100.00 74.12

16. UNTT CAPACTrY FACTOR (Using MDC) 101.55 101.55 63.83

17. UNTT CAPACTrY FACTOR (Using Design MWe) 98.97 98.97 62.21

18. UNTT FORCED OtTTAGE RATE 0.00 0.00 7.45

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

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

21. UNTr5 IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTilAL CRTTICALTTY i

INTR!AL ELECTRICTTY COMMERCIAL OPERATION 1.16-9 l

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APPENDIX C i

OPERATING DATA REPORT I

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DOCKET NO.

50-265 UNrr Two

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DATE February 10, 1997 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 010197

1. REPORTING PERIOD: 2400 013197 GROSS HOURS IN REJORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION (IF ANY):

TH15 MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REAcrOR WAS CRTTICAL 744.00 744.00 161330.55

6. REACIOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80 l

7. HOURS GENERATOR ON LINE 744.00 744.00 156993.35

8. UNir RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 182 % 26.00 1829626.00 341501714.82 l

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10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 588301.00 588301.000 109605438.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 565970.00 565970.00 103885691.00

12. REACTOR SERVICE FACTOR 100.00 100.00 74.72

13. REACTOR AVAILABILrrY FACTOR 100.00 100.00 76.11

14. UNTT SERVICE FACTOR 100.00 100.00 72.72

15. UNIT AVAILABILITY FACTOR 100.00 100.00 73.04

16. UNir CAPACITY FACTOR (Using MDC) 98.92 98.92 62.57

17. UNir CAPACirY FACTOR (Using Design MWe) 96.41 96.41 60.99

18. UNIT FORCED OUTAGE RATE 0.00 0.00 11.13

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

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

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16-9 TirHOPnNRC\\ MONTHLY.RI'r

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l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 10-254 i

UNIT One DATE February 10. 1997 i

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH January 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

784

-17.

784 2.

783 18.

778 l

3.

784 19.

782 4.

734 20.

783 5.

783 21.

783 _

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6.

783 22.

782 i

i 7.

783 23.

783 8.

783 24.

784 l

9.

784 25.

779-10.

783 26, 784 11.

770 27.

772 12.

784 28.

783 l

13.

780 29.

783 I

14.

783 30.

783 15.

782 31.

784 16.

783 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 i,

output sheet should be footnoted to explain the apparent anomaly, 1.16-8 11sCHOP3\\NRC\\ MON 1HLY.RIT

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4 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two l

DATE February 10. 1997 l

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 l

MONTH January 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

778 17.

777 2.

778 18.

778 3,

778 19.

763 4.

778 20.

767 5.

769 21.

770 6.

774 22, 771 l

7.

777 23.

774 l

8, 775 24.

773 9.

638 25.

774 10, 643 26.

766 11, 643 27.

777 12.

747 28.

776 13.

776

29. -

777 14.

777 30.

776 l

15.

777 31.

764 l

l 16.

777 l

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.

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o APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UN2T NAME One COMPLETED BY Kristal Moore DATE February 10. 1997 REPORT MONTH January 1997 TELEPHONE 309-654-2241 k

to 3C r.

n-N-

$W E0 ! 8 LICENSEE O

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS l

I None i

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE February 10, 1997 REPORT MONTH January 1997 TELEPHONE 309-654-2241 ON l

m E

$g oZ<

$M

$M M

E sE 00 20 h

5 g

m e

$W LICENSEE O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS j

NO.

DATE (HOURS)

REPORT j

9741 1/9/97 F

0 A

5 Reduced lead to Troubleshoot 2C1 Feedwater Heater Operating Vent Leak.

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l VI. MHIRUE 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 Timino 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 l

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 l

Revision 2 i

QUA0 CITIES REFUELING October 1989 l

INFORMATION REQUEST e

1.

Unit:

01 Reload:

14 Cycle:

is 2.

Scheduled date for next refueling shutdown:

3/28/98 3.

Scheduled date for restart following refueling:

5/29/98 4.

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

g 5.

Scheduled date(s) for submitting proposed Itcensing action and

)

supporting information:

5/9/98 6.

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

Approx. 216 SPC 9X9IX Fuel Bundl'es Q1R15 will be loaded.

4 7.

The number of fuel assemblies.

a.

Number of assemblies In core:

724 b.

Number of assemblies in spent fuel pool:

1933 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 g

planned in number of fuel assemblies:

3657 a.

Licensed storage capacity for spent fuel:

0 b.

Planned increase in licensed storage:

9.

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

i APPROVED l

l (final)

DCT 3 0 UN

-I-l 14/0395t Q.C.O.S.R.

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QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 i

INFORMATION REQUEST 1.

Unit:

Q2 Reload:

13 Cycle:

14 i

i 2.

Scheduled date for next refueling shutdown:

3/1/97 3.

Seneduled date for restart following refueling:

4/30/97 4.

Will refueling or resumption of operation thereafter require a Technical l

Specification change or other license amendment:

(:

b 5.

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

August 1996 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 i

procedures:.

l 216 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 Ilcensed spent fuel pool storage capacity and the size of any increase in Itcensed storage capacity that has been requested or is N

planned in number of fuel assemblies:

a.