Text

Monthly Operating Repts for Oct 1995 for Quad-Cities Nuclear Power Station
	ML20094L179
Person / Time
Site:	Quad Cities
Issue date:	10/31/1995
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-95-102, NUDOCS 9511200082
	Download: ML20094L179 (19)
	v • d • e

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Commonwealth Ikliwn Company Qu.td Cities Generating Station 22710 JWeth Avenue North Corsova, n.6i2new ret.w > m 224i i

i LWP-95-102 November 8, 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 October 1995.

Respectfully, Comed Quad-Cities Nuclear Power Station

/. h.

r L. W. Pearce Station Manager LWP/dak Enclosure cc:

H. Miller, Regional Administrator C. Miller, Senior Resident Inspector STMGR\\l0295.L%?

9 l'.! l. C t' 9511200082 951031 PDR ADDCK 05000254 y 8 R

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 l

i MONTHLY PERFORMANCE REPORT

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l September 1995 i

COMMONWEALTH EDISON COMPANY j

i AND MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

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TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

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

Maintenance 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 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 11CHOM\\NRC040N1MLY.RPT

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1.

INTRODUCTION j

Quad-Cities Nuclear Power Station is composed of two Boiling Water 4

Reactors, each with a Maximus 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 l

cooling water source. The plant is subject to license numbers DPR-29 and l

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.

l Commercial generation of power began on February 18, 1973 for Unit One and i

i 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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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One started the month of October 1995 at full power.

A manual scram was performed on October 22, 1995 at 0026 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months . The unit had been on line for 283 days. The scram was inserted during a controlled shutdown, due to a design issue with the Scram Discharge Volume Level Switch not meeting single failure criteria. A temporary alteration is being installed and will remain in-place until the permanent modification can be. installed during Q1R14 (February,1996).

Start-up is projected for November 8, 1995.

B.

Unit Two l

Quad Cities Unit Two started the month of October 1995 on-line at 700 MWe. On October 4,1995 a load drop was commenced for the Recirc Flow Drop Test. After completion of test, the load drop was reduced further to troubleshoot a problem with the #2 Turbine Control Valve.

On October 21, 1995 at 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months the Turbine was tripped due to a leak on #1 Turbine Control Valve. At 2158 hours0.025 days 0.599 hours 0.00357 weeks 8.21119e-4 months the reactor was manually scrammed during a controlled shutdown, due to the same design issue that necessitated the shutdown of Unit 1.

The permanent modification for Unit 2 is being planned.

Start-up is projected for November 17, 1995.

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I III.

PLANT OR PROCEDURE CHAlGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE l

A.

Amendments to Facility License or Technical Soecifications Technical Specification Amendment No.163 was issued on October 20, i

1995 to Facility Operating License DPR-29 and Amendment No. 159 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station.

The amendments would relocate the requirements for the

" Review, Investigative and Audit Functions" and frequencies of the Quality Assurance (QA) program from the administrative controls section of the TS to the appropriate sections of the licensee's Quality Assurance Topical Report (QATR), CE-1-A,' Revision 65.

In addition, the proposed TS changes include title changes to reflect the reorganization of the licensee's Nuclear Operations Division and miscellaneous administrative and editorial changes.

B.

Facility or Procedure Chanaes Reauirina NRC Anoroval There were no Facility or Procedure changes requiring NRC approval for 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-Cities Units One and Two occu-ring during the reporting period, pursuant to the reportable occurrence repwting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report N aher Daig Title of occurrence 95-007 10/20/95 SDV Logic Circuitry UNIT 2 Licensee Event Egoort Number D. gig Title of occurrence 95-006 10/04/95 29-2 Breaker Trip 95-007 10/04/95 HPCI Turning Gear INOP 95-008 10/18/95 U2 HPCI Flow Oscillations TECHOP3\\NRC\\MONTMLY.WT l

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 M

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l APPENDIX C OPERATING DATA REPORT DOCKET NO.

50 254 UNrr One DATE November 8, 1995 COMPLETED BY Krissa! Moors j

TELEPHONE (309) 654-2241 OPERATING STATUS 0000 100195

1. REPORTING PERIOD: 2400 103195 OROSS HOURS IN REPORTINO PERIOD: 745

2. CURRENTLY AITrHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPActrY: 769 DESIGN ELECTRICAL RATINO (MWe-NET): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TG DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 504.50 6824.30 159256.80

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 504.50 6768.50 154592.40

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENEROY GENERATED (MWH) 1253328.80 16432164.90 335588288.30

10. GROSS ELECTRICAL ENEROY GENERATED (MWH) 403221.00 5243915.00 108707769.00

11. NET ELECTRICAL ENEROY GENERATED (MWH) 383182.00 5021058.00 102609224.00

12. REACTOR SERVICE FACTOR 67.72 93.53 77.13

13. REACIDR AVAILABillTY FACTOR 67.72 93.53 78.79

14. UNrr SERVICE FACTOR 67.72 92.77 74.87

15. UNTT AVAILABILrrY FACTOR 67.72 92.77 75.31

16. UNrr CAPActrY FACTOR (Using MDC) 66.88 89.49 64.63

17. UNrr CAPActrY FACTOR (Using Design MWe) 65.19 87.22 62.99

18. UNrr FORCED OtrTAGE RATE 32.28 7.23 7.48

19. SHtTTDOWNS SCHEDULED OVER NEXT 6 MortrHS (TYPE. DATE. AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD < F5 TIM AIED DATE OF STARTUP:

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

FORECAST ACHIEVED INrrlAL CRfilCALrrY INrrlAL ELECTRICrTY COMMERCIAL OPERA 710N i.1 +9 1TCHOP3\\NRCG40NTMLY.RI'T m

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APPENDIX C OPERATING DATA REPORT DOCKETNO. 50-265 i

UNTT Two DATE October 8,1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-224I OPERATING STATUS 0000 100195

1. REPORTING PERIOD: 2400 103195 GROSS HOURS IN REPORTING PERIOD: 745

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

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

4. REASONS FOR RESTRICriON (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 502.00 3161.80 152937.65

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 498.10 3064.80 148996.45

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1059064.20 6256168.12 322196872.22

10. OROSS ELECTRICAL ENER0Y GENERATED (MWh) 336538.00 1948558.00 103462459.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 318808.00 1847243.00 98003152.00

12. REACTOR SERVICE FACTOR 67.38 43.34 74.64

13. REACTOR AVAILABILTTY FACTOR 67.38 43.34 76.09

14. UNTT SERVICE FACTOR 66.86 42.01 72.71

15. UNTT AVAILABILTTY FACTOR 66.86 42.01 73.06 i

16. UNIT CAPACITY FACTOR (Using MDC) 55.65 32.92 62.19

17. UNTT CAPACTTY FACTOR (Using Design MWe) 54.24 32.09 60.62

18. UNIT FORCED OUTAGE RATE 33.14 15.70 10.06

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMA'!T.D DATE OF STARTUP:

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

FORECAST ACHIEVED INTTIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.19-9

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i APPENDIX B

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i AVERAGE DAILY UNIT POWER LEVEL i

l DOCKET NO 50-254 j

UNIT One DATE November 8. 1995 COMPLETED BY Kristal Moore i

TELEPHONE (3091 654-2241 MONTH October 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) s i

1.

770 17.

770 l

2.

770 18.

769 3.

768 19.

771 1

4.

768 20.

772 5.

768 21.

733 6.

768 22.

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7.

704 23.

-10 8.

770 24.

-10 9.

770 25.

-9 10.

768 26.

-9 11.

770 27.

-9 4

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771 28.

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13.

768 29.

-9 14.

773 30.

-8 15.

761 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 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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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE November 8. 1995 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH October 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

669 17.

660 2.

665 18.

660 3.

667 19. _,

661 4.

586 20.

663 5.

411 21.

455 6.

658 22.

-10 7.

662 23.

-10 8.

660 24.

-9 9.

663 25.

-8 10, 661 26.

-9 11.

656 27.

-8 12.

662 28.

-8 13, 661 29.

-8 14.

662 30.

-8 15.

662 31.

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661 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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APPENDIX D I

UNIT SHUTDOWNS AND POWER REDUCTIONS i

DOCRET NO.

50-254 l

l UNIT NAME one COMPLETED BY Kristal Moore 3

DATE Nover S.

1995 REPORT MONTH October 1995 TELEPHONE 309-654-2241 l

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l LICENSEE DURATION 8

EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS /CONMENTS Manuel seresa due to design issue on the scosse 95 10 10/22/95 F

240.5 D

2 Discharge Volume Level Switch I

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE Novamhar 8, 1995 REPORT MONTH October 1995 TELEPHONE 309-654d241 m:

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DURATION g

EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS Manuel Scram due to design issue on the Screen 95 10 10/22/95 F

240.5 D

2 Discharge Volume L.evel Switch i

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9 APPEND 1X D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.- 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE Nov="r 8.

1995 REPORT MONTN october 1995 TELEPHONE 309-654-2241 h,.

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LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT Commenced Recirc Flow Drop Test AAer C54 10/04/95 3

0 B

5 completion of test continued load drop to troubleshoot problem with #2 Turbine Control Velve.

Tripped turbine due to leak on #1 Turbins 95-10 10/21/95

'F 246.9 A

9 Conneci Velve.

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VI. UNIOUE REPORTING REOUIREMENTS The following items are included in this report based on prior commitments to the commission:

A.

Main Steam Relief Valve Operations Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Unit: One Date: October 13, 1995 Valve Actuated:

No. & Tvoe of Actuation:

l-203-3B 1 Manual

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Plant Conditions: Reactor Pressure 1005 psig Description of Events: Trouble Shooting / Maintenance B.

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

There was no Control Rod Drive scram timing data for Units One and Two for the reporting period.

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d 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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t QTP 300-532 Revision 2 i

QUAD CITIES RERIELING October 1989 l

INTORMATION REQUEST I'

l 1.

Unit:

01 Reload:

13 Cycle:

2/5/96

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2.

Scheduled date for next refueling shutdown:

5/15/96 3.

Scheduled date for restart following refveling:

4.

Will refueling or resumption of operation tMreafter require a Technical Speelfication changd or other license amendment:

n 5.

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

supporting information:

7-4-95 i

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Important Ilconsing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance j

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

procedures:

232 GE10 Fuel Bundles will be loaded during Q1R.14.

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7.

The number of fuel assemblies.

i a.

Number of assemblies in core:

724 b.

Number of assemb11es in spent fuel pool:

1717 4.

The present Ilcensed spent fuel pool storage capacity and the size o'/

)

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:

3657 4

b.

Planned increase in licensed storage:

0 9.

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

spent fuel pool assuming the present Ilconsed capacity: 2006 l

APPROVED 8

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OCT 3 059 14/0395t -

O.C.O.S.R.

OTP 300-538

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Revision 2 OUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

I3 l4 Cycle

2.

Scheduled date for next refueling shutdown:

1-6-97 3-30-97 3.

Scheduled date for restart following refueling:

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

YES 5.

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

November, 1996 6.

Important Ilconsing 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

l Approx. 200 Siemens 9X9IX Power Corporation Fuel Bundles will be loaded during Q2R14.

1 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 Ilconsed 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:

3897 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 Ilconsed capacity:

APPROVED 30W 14/0395t Q.C.O.S.R.

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