Text

Monthly Operating Repts for Nov 1995 for Quad Cities Nuclear Station Units 1 & 2
	ML20095E225
Person / Time
Site:	Quad Cities
Issue date:	11/30/1995
From:	Moore K; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20095E070	List: ML20095E066; ML20095E225; ML20095E230; ML20095E234; ML20095E239; ML20095E243;
References
	NUDOCS 9512140260
	Download: ML20095E225 (19)
	v • d • e

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QUAD-CITIES NUCLEAR POWER STATION l

UNITS 1 AND 2 1

1 MONTHLY PERFORMANCE REPORT November 1995 COMMONWEALTH EDISON COMPANY l

AND MID-AMERICAN ENERGY COMPANY

<RC DOCKET N05. 50-254 AND 50-265 l

LICENSE NOS. DPR-29 AND DPR-30 i

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9512140260 951200 PDR ADDCK 05000254 R.

PDR

t TABLE OF CONTENTS f

I.

Introduction

.i II.

Summary of Operating Experience i

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 j

V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 1

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Unique Reporting Requirements

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A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary i

11! CHOPS \\NRC\\ MON 1MLY.RPT

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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 i

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.

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TIEHOP3\\NRC\\ MONTHLY.RPT

i II.

SUMMARY

OF OPERATING EXPERIENCE

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A.

Unit One j

l Quad Cities Unit One started the month of November 1995 shutdown due to a design issue with the Scram Discharge Volume Level Switch. On November 9, 1995 at 0244 hours0.00282 days 0.0678 hours 4.034392e-4 weeks 9.2842e-5 months the reactor went critical. On November 10, 1995 at 0646 hours0.00748 days 0.179 hours 0.00107 weeks 2.45803e-4 months the reactor was manually scrammed due to the 1-220-1 steam drain valve leaking. After repairs the reactor went critical on November 12, 1995 at 2120 hours0.0245 days 0.589 hours 0.00351 weeks 8.0666e-4 months . The generator was synched to the grid on November 13, 1995 at 0914. A few load drops were performed, however the average daily level remained at 80% or greater.

B.

Unit Two Quad Cities Unit Two started the month of November 1995 shutdown in a forced outage due to the same design issue that shutdown Unit 1.

The reactor was made critical on November 22, 1995 at 0954 hours0.011 days 0.265 hours 0.00158 weeks 3.62997e-4 months . The generator was synched to the grid on November 23, 1995 at 1411 hours0.0163 days 0.392 hours 0.00233 weeks 5.368855e-4 months .

The Turbine was tripped on November 29, 1995 at 0513 hours0.00594 days 0.143 hours 8.482143e-4 weeks 1.951965e-4 months due to EHC leak at the #1 Turbine Control Valve. On November 29, 1995 at 2351 hours0.0272 days 0.653 hours 0.00389 weeks 8.945555e-4 months the generator was back on-line.

i 1TCHOP3\\NRC\\ MON 1HLY.RPr

j III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE l

A.

Amendments to Facility License or Technical Specifications Technical Specification Amendment No. 164 was issued on November 20, l,.

1995 to Facility Operating License DPR-29 and Amendment No. 160 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments contained the proposed upgrade of Section 3/4.2 (Instrumentation) of the Quad Cities Technical Specifications.

B.

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

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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I IV. LICENSEE EVENT REPORTS The following is a tabular sumary of all licensee event reports for Quad-l Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections i

6.6.B.1 and 6.6.B.2 of the Technical Specifications.

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l There were no Licensee Event Reports for Unit 1 and Unit 2 for this reporting 1

period.

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i 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 i

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNTT One DATE December F.

1995 COMPLETED BY Kristal Mmere TELEPHONE (309) 654-2241 OPERATING STATUS 0000 180195

1. REPORTING PERIOD 2400 113095 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHom 7mn POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 I

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

4. REASONS POR RESUtlCTION (IF ANY):

TH18 MONTH YR TO DATE CUMULATIVE 1

5. NUMBER OF HOURS REACTOR WAS CRTrlCAL 462.70 7287.00 159719.50

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90 l

7. HOURS GENERATOR ON LINE 422.80 7191.30 155015.20 i

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20 t

9. OROSS THERMAL ENERGY GENERATED (MWH) 968932.30 17401097.20 336557220.60

10. GROSS ELECTRICAL ENERGY OENERATED (MWH) 310678.00 5554593.00 109018447.00 l1. NET ELECTRICAL ENERGY GENERATED (MWH) 293985.00 5315043.00 102903209.00 l

12. REACTOR SERVICE FACTOR 64.26 90.91 77.09

13. REACTOR AVAILABILFTY FACIDR 64.26 90.91 78.74

14. UNIT SERVICE FACTOR 58.72 89.71 74.82 I

15. UNTT AVAILABILTTY FACTOR 58.72 89.71 75.26

16. UNTT CAPACfrY FACTOR (Using MDC) 53.10 86.22 64.59

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17. UNrr CAPACTTY FACTOR (Using Design MWe) 51.75 84.04 62.95 j

l8. UNrr FORCED OUTAGE RATE 41.28 10.29 7.62

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

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

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

FORECAST ACHIEVED INfflAL CRTrlCALITY I

INfr!AL ELECTRICTrY l

COMMERCIAL OPERATION i

1.14-9 I

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APPENDIX C 1

l OPERATING DATA REPORT DOCKET NO.

50-265 3

UNrr Two i

DATE Deceseber 8, 1995 COMPIETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS i

0000 110195

1. REPORTING PERIOD 2400 113095 GROSS HOURS IN REPORTING PEluOD: 720

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

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

4. REASONS FOR RE31RICTION (IF ANY)-

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrICAL 206.10 3550.60 153326.45

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6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 159.10 3223.90 149155.55

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 294462.60 6550630.72 322491334.82

10. ORoss at ar'IRECAL ENERGY GENERATED (WWH) 87064.00 2035622.00 103549523.00 l

11. NEr ELECTRICAL ENERGY GENERATED (MWH) 77988.00 1925231.00 98081140.00 i

12. REACTOR SERVICE FACTOR 28.63 44.29 74.56

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13. REACTOR AVAILABILITY FACTOR 28.63 44.29 76.02

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14. UNrr SERVICE FACTOR 22.10 40.22 72.54

15. UNrr AVAILARILTTY FACTOR 22.10 40.22 72.88

16. UNrr CAPACfrY FACTOR (Using MDC) 14.09 31.23 62.03

17. UNrr CAPACfrY FACTOR (Uning Design MWe) 13.73 30.44 60.45

18. UNTT PORCED OUTAGE RATE 77.90 25.98 10.35

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

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

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

FORECAST ACHIEVED INrrIAL CRrriCALTTY INTTIAL ELECIRECITY COM%IERCIAL OPERATION 1.b-9 1TCHOP3\\MitC\\ MON 1HLY.RFr

APPENDIX B

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AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO 50-254 UNIT One DATE December 8. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH November 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 1.

-9 17, 775 l

2.

-9 18.

777 6

3.

-8 19.

777 4.

-9 20.

776 i

5.

-9 21.

774 6.

-9 22.

775 7.

-9 23, 773 8.

-9 24, 779 9.

-11 25.

758 10.

-10 26, 778 11.

-10 27.

778 12.

-9 28.

776 13.

73 29.

771 14.

166 30, 776

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503 31.

16, 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 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 11rHOP3NMON1HLY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two DATE December 8. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH November 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 1.

-8 17.

-8 2.

-8 18.

-9 3.

-8 19.

-8 4.

-8 20.

-8 5.

-8 21.

-8 l

6.

-9 22.

-8 7.

-9 23.

45 8.

-9 24.

197 9.

-11 25.

293 10.

-10 26.

696 11.

-9 27.

766 12.

-9 28.

770 13.

-10 29.

126 14.

-8 30.

552 15.

-8 31.

16.

-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 daily unit power output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TirHOP3\\NRC\\ MONTHLY.RPT

APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE December 8, 1995 REPORT MONTH November 1995 TELEPHONE

)09-654-2241 a:

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MM M

EE E l5 E0 50 a

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Mx LICENSEE O

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 95-10 11/01/95 F

297.2 D

2 Continued Forced outage due to design issue on the Scram Discharge Volume Level Switch TECHOMWRC\\MONWLY.RFT

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS l

DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE December 8, 1995 REPORT MONTH Novamher 1995 TELEPHONE 309-654.2241 a:

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to MM M M u

E8 5O8 A a:

to HO ho M

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DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT 95-10 11/01/95 F

542.0 D

2 Continued Forced Outage.

95-11 11/29/95 F

18.7 A

9 Tripped turbine to plug EHC Leak on il Turbine Control Valve.

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noionwacwoNTHLY RIT

VI.

UNIOVE REPORTING RE0VIREMENTS 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 The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 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 & 3 CONTROL ROD DRIVES, FROM 01/01/95 TO 07/31/95 l

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INSERTED FROM FULLY WITHDRAWN l FOR 90%

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DESCRIPTION INSERTION NUMBER 5

20 50 90 Technical Specification 3.3.C.1 &

DATE OF RODS

! 0.375 ! 0.900 2.00 3.5 7 sec.

3.3.C.2 (Averaoe Scram Insertion Time) i I

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1 01/15/95 177 l 0.31 l 0.70 l

1.47 l

2.57 3.30 l

Post Maintenance after Q1F35 Seq A, B, l

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J-6 l Done for Unit 1

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0.29 0.65 l

1.42 l

2.48 l

2.48 Q18840 to torque Scram Inlet Valve Packing.

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l 0.30 L 0.65 1.37 2.41 l

2.41 l Diagnostic Testing of U-1 H-9 j

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07/03/95 172 0.31 1 0.71 1.55 1

2.71 l

3.15 l BOC for Q2C14 l;

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08/05/95 20 0.30 0.67 l

1.41 l

2.46 l

2.65 los for new Tech Spec Unit 1 1

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54 l

0.32 1 0.70 ll 1.48 2.58 3.02 Remainder of BOC for Q2C14 after maintenance K10 I was performed Unit 2 l

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21 0.33 0.71 1.49 l

2.59 2.71 10% for Tech Spec and 1 PMTV Unit 1 H-6 l

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[ 0.71 1.51 2.65 l

3.00 1

10% for Spec and 26 PMTV Unit 2 l

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i VII. REFUELING INFORMATI0tl i

1 The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.

3 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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OTP 300-532 i-Revision 2 h

OUAD CITIES REFUELING october 1989 i

INFORMAT?i$ IEQUEST l'

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Unit:

01 Reload:

13 Cycle:

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2/5/96 2.

Scheduled date for nort refueling shutdown:

3.

Scheduled date for restart following ref'oeling:

5/15/96 l

4.

W111 refueling or resunption of operation the.reafter require a Technical j

Spectftcation changd or other license amendment:

No t

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

supporting information:

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7-4-95 i

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Important licensing considerations associated with refueling, e.g., new i

or different fuel design or supplier, unreviewed desty or performance i

analysis methods, significant changes in fuel design, new operating j

procedures:

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232 GElo Fuel mundles will be leaded during Q1134.

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The number of fuel assemblies.

4.

Nummer of assemblies la core:

724

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b.

Number of assemb11es la spent fuel pool:

1717 l

4.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is l

planned in number of fuel assemblies:

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a.

Licensed storage capacity for spent fuel:

3657 i

b.

planned increase in licensed storage:

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

spent fuel pool assuming the present Ilconsed capacity: 2006 i

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l APPROVED (finai! -

OCT3 055 w assse.

c.c.o.s.n.

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Revision 2 QUAD CITIES REFUELING Octsber 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

I3 Cycle:

2.

Scheduled date for next refueling shutdown:

1-6-97 3.

Scheduled date for restart following 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 preposed licensing 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 analysts methods, significant changes in fuel design, new operating procedures:

Approx. 200 Siemens 91911 Power Corporation Fuel Bundles will be loaded during Q2R14.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 3377 b.

Number of assemblies in spent fuel pool:

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 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 Itcensed capacity:

APPROVED (finai)

OCT 3 01989 l

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

l VIII. GLOSSARY

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