Text

Monthly Operating Repts for Jan 1996 for Quad Cities Nuclear Station
	ML20149K749
Person / Time
Site:	Quad Cities
Issue date:	01/31/1996
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-96-011, LWP-96-11, NUDOCS 9602220123
	Download: ML20149K749 (20)
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Qimnmnwealth Ilhen Gunpany

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,Qtrul Glies Generating Station 22710 206th Avenue Nonh j

Oirdjwa, IL 61212 9740

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' Tel.4094 51-22 41 1

i LWP-96-011 February 9, 1996 U.S. Nuclear Regulatory Commission i

ATTN: Document Control Desk 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 1996.

Respectfully, Comed Quad-Cities Nuclear Power Station

/

MJ LA.,

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L. W. Pearce Station Manager LWP/dak Enclosure ec:

H. Miller, Regional Administrator C. Miller, Senior Resident Inspector STMORWin96.LWP a n n 6 4 PW 9602220123 960131 PDR ADOCK 05000254 R

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i QUAD-CITIES NUCLEAR POWER STATION c

UNITS 1 AND 2 I

MONTHLY PERFORMANCE REPORT l

January 1996 COMMONWEALTH EDISON COMPANY i

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

LICENSE NOS. DPR-29 AND DPR-30 0

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TABLE OF CONTENTS j

I.

Introduction 1

II.

Summary of Operating Experience A.

Unit One B.

Unit Two t

III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance i

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 r

A.

Operating Data Report l

B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions l

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VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations i

B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary f

s TliCHOPS\\MitC\\ MONTHLY RPT

I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each w th 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 1

Sargent & Lundy, Incorporated, and the primary construction contractor was i

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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l II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One remained on-line for the entire month of January 1996. A few load drops were performed, however the average daily power level remained at 80% or greater.

B.

Unit Two Quad Cities Unit Two spent the month of January 1996 at full power except for on January 4,1996, a load drop was performed to repair a flex line break which occurred on the 2A Moisture Separator Drain Tank Level Column.

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE d

A.

Amendments to Facility License or Technical Specifications Technical Specification Amendment No.169 was issued on January 11, 1996 to Facility Operating License DPR-29 and Amendment No. 165 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments revised the Technical Specifications to incorporate 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-cooled Power Reactors," Option B.

B.

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

C.

Tests and Experiments Reauirina NRC Acoroval 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.

j UNIT 1 Licensee Event i

Reoort Nn=her Qalg Title of occurrence 96-004 1/30/96 HPCI IN0P - Auxiliary oil pump overload.

UNIT 2 Licensee Event Report Number Data Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

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t V.

DATA TABULATIONS I

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 4

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APPENDDC C OPERATING DATA REPORT DOCKET NO.

50-254 UNTT One DATE February 9.1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 010196

1. REPORTING PERIOD: 2400 0131% GROSS HOURS IN REPORTING PERIOD: 744

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

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

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4. REASONS FOR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 744.00 744.00 161207.50

6. REACTOR RESERVE SHtTTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 744.00 744.00 156503.20

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1825428.50 1825428.50 340231226.10

10. GROSS ELEC11LICAL ENEROY GENERATED (MWH) 588127.00 588127.00 110202208.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 563558.00 563558.00 104037934.00

12. REACTOR SERVICE FACTOR 100.00 100.00 77.25

13. REACTOR AVAILABILTTY FACTOR 100.00 100.00 78.89

14. UNTT SERVICE FACTOR 100.00 100.00 75.00

15. UNrr AVAILABILTTY FACTOR 100.00 100.00 75.43

16. UNIT CAPACITY FACTOR (Using MDC) 98.50 98.50 64.83

17. UNIT CAPACTrY FACTOR (Using Design MWe) 96.00

%.00 63.19 i

18. tJNTT FORCED OtfrAGE RATE 0.00 0.00 7.55

19. SHtTFDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): Refuel,2/10/96 thru 4/28/96

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

21. UNrrS IN TEST STATUS (PRIOlt TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTriCALITY INITIAL ELECTRICTTY COMMERCIAL OPERATION

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-265 UNrr Two DATE February 9,1996 COMPLETED DY Kristal Moore TELEPHONE (309) 654 2241 OPERATING STATUS 0000 010196

1. REPORTING PERIOD: 2400 013196 ORoss HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION GF ANY):

THIS MONTH YR TO DATF CUMULATIVE

5. NUMBER OF HOURS REAC'IDR WAS CRITICAL 744.00 744.00 154631.75

6. REACTOR RESERVE SHIfrDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 744.00 744.00 150643.55

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1807028.30 1807028.30 326148249.22

10. OROSS ELECTRICAL ENERGY GENERATED (MWH) 5804l3.00 580413.00 104725948.00 4

55 0 67.00 556367.00 99209253.00

11. NET ELECTRICAL ENERGY GENERATED (MWH)

12. REACTOR SERVICE FACTOR 100.00 100.00 74.66

13. REACTOR AVAILABILrrY FACTOR 100.00 100.00 76.10 l

14. UNTT SERVICE FACTOR 100.00 100.00 72.73

15. UNrr AVAILABILTTY FACTOR 100.00 100.00 73.07

16. UNIT CAPActrY FACTOR (Usin8 MDC) 97.24 97.24 62.29

17. UNTT CAPActrY FACTOR (Using Design MWe) 94.78 94.78 60.71

18. UNTT FORCED OUTAGE RATE 0.00 0.00 10.26

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

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

21. UNirs IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTilCALTrY INirlAL ELICTRICfrY COMMERCIAL OPERATION 1.1 r9 TIrHOP3\\NRC\\MONDILY.RI'r

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE February 9. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH January 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

757 17.

770 2.

775 Il'.

768 3.

775 19.

763 4.

775 20.

744 5.

774 21.

758 6.

766 22.

753 7.

774 23.

700 8.

774 24.

755 9.

774 25.

742 10.

746 26.

740 11.

774 27.

737 12.

773 28.

732 13.

774 29.

728 14.

775 30.

725 15.

773 31.

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772 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 i

the restricted power level line).

In such cases, the average daily unit power c,utput sneet should be footnoted to explain the apparent anomaly.

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APPENDIX B l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE February 9. 1996 COMPLETED BY Kristal Moore MONTH January 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

775 17, 774 2.

774 18.

774 3.

773 19.

773 4.

323 20.

774 5,

702 21.

767 6.

769 22.

772 7.

728 23.

706 8.

772 24.

772 9.

762 25.

774 f

10, 750 26.

774 11.

773 27.

773 12, 773 28.

744 f

13.

684 29.

770 14.

772 30.

773 15.

773 31.

773 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.

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i APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE February 9, 1996 REPORT MONTH January 1996 TELEPHONE 309-654-2241 N

E to M M m

MM De to LICENSEE O

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS None for the month of January.

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i APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DCCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE February 9.

1996 REPORT MONTH January 1996 TELEPHONE 309-654-2241 a

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n.a a LICENSEE i

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS 4

NO.

DATE (HOURS)

REPORT Repair Moisture Separator Drain Tank Steam 9641 1/4/96 F

0 A

5 leak.

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

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the commission:

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

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B.

Control Rod Drive Scram Timina Data for Units One and Two j

The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 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 E 2 CONTROL ROD DRIVES, FROM 01/01/96 TO 01/31/96 l

l AVERAGE TIME IN SECONDS AT %

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j INSERTED FROM FULLY WITHDRAWN l FOR 90%

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DESCRIPTION l NUMBER 5

20 50 90 l

Technical Specification 3.3.C.1 &

DATE

! OF RODS

! 0.375 ! 0.900 2.00 3.5 7 sec.

I 3.3.C.2 (Avermoe Scram Insertion Time)

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1/13/96 l

29 l 0.339 1 0.708 l 1.459 l 2.538 2.91 l Scram Time Test for Viton' Issue l

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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.

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QTP 300-532 Revision 2

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QUAD CITIES REFUELING October 1989 INFORMATION REQlJEST 1.

Unit:

01 Reload:

14 15 Cycle:

2.

Scheduled date for next refueling shutdown:

2/10/96 3.

Scheduled date for restart following refueling:

4/28/96 4.

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

NO 5.

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

3-15-96 6.

Important Ilcensing 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:

232 GE10 Fuel Bundles will be loaded during Q1R14.

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 any increase in licensed storage capacity that has been requested or is planned in numLar 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 licensed capacity:

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

OTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

13 I4 Cycle:

2.

Scheduled date for next refueling shutdown:

1-6-97 3.

Scheduled date for restart fo11owing 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 Itcensing 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 l

analysis methods, significant changes in fuel design, new operating procedures:

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

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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 Ilcensed capacity:

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

VIII. GLOSSARY 1

The following abbreviations which may have been used in the Monthly Report, i

are defined below:

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ACAD/ CAM - Atmospheric Containment Atmospheric