Text

Monthly Operating Repts for Sept 1996 for Quad Cities Nuclear Station Unit 1 & 2
	ML20129B844
Person / Time
Site:	Quad Cities
Issue date:	09/30/1996
From:	Moore K, Pearce L; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LWP-96-074, LWP-96-74, NUDOCS 9610230127
	Download: ML20129B844 (20)
	v • d • e

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Commonwcahh lilimo Gimpan)

Quad Citie<. Generating Station 22'10 2($th Asenur North Cordova. IL 61212 97 to Tei.umis w2 ii j

LWP-96-074 October 10, 1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washingto.., D.C. 20555 i

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 i

Monthly Performance Report I

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, l

during the month of September 1996.

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Respectfully, Comed i

Quad-Cities Nuclear Power Station Y

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

A. Beach, Regional Administrator C. Miller, Senior Resident Inspector smo m m.t.wr

/

9610230127 960930 PDR ADOCK 05000254 R

PDR A Uniton Company

.. - -. - _ =. _. -.

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1996 COMMONWEALTH EDIS0N COMPANY AND MID-AMERICAN ENERGY COMPANY 1

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 TTfHOP3\\NRC\\ MON 1HLY.RPT

TABLE OF CONTENTS J

I.

Introduction II.

Summary of Operating Experience 1

A.

Unit One j

B.

Unit Two i

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 IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Avera>Je 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 TIiCHOP3\\NRC.MONTHI Y.RPT

I.

INTRODUClION l

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

l Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by l

Commonwealth Edison Company and Mid-American Energy Company. The Nuclear Steam Supply Systeies 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, l

respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of i

initial Reactor critic.sities for Units One and Two, respectively were October 1

18, 1971, and April 26, 1972.

Commercial generation of power began on l

February 18, 1973 for Unit One and 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, respectively.

e TECHOP)\\NRC\\ MONTHLY.RI"T

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Quad Cities Unit One was critical the entire month of September 1996, t

On September 1, 1996 at 0532 hours0.00616 days 0.148 hours 8.796296e-4 weeks 2.02426e-4 months the generator was synched to the j

grid. On September 2, 1996 at 0141 hours0.00163 days 0.0392 hours 2.331349e-4 weeks 5.36505e-5 months the generator was taken off-line due to the ID Main Steam Isolation Valve failing timing i

requirements. The actuator was repaired and the generator synched to l

the grid on September 6, 1996 at 0206 hours0.00238 days 0.0572 hours 3.406085e-4 weeks 7.8383e-5 months . The Generator,was taken off-line on September 10, 1996 at 0037 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months and back on-line at 2110 hours0.0244 days 0.586 hours 0.00349 weeks 8.02855e-4 months to recalibrate the Feedwater Flow Control Valve.

8.

Unit Two Quad Cities Unit Two was on-line the entire month of September. On September 26, 1996 at 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months a load drop was performed to maintain l

vacuum. Condenser vacuum returned to normal after repairing a failed i

bellows on the 2A SJAE Relief Valve.

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l III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTrNANCE l

l A.

Amendments to Facility License or Technical Soecifications 1

There were no Amendments to the Facility License or Technical l

Specifications for the reporting period.

B.

Facility or Procedure Chanaes Reauirina NRC Aonroxql There were no Facility or Procedure changes requiring NRC approval for j

the reporting period.

1 C.

Tests and Experiments Reauirina NRC Acoroval i

There were no Tests or Experiments requiring NRC approval for the i

reporting period.

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TECHOP3\\NRCG40NTHLY.RFT

IV.

LICENSEE EVENT REPORTS i

1 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 of 10CFR50.73.

UNIT 1 Licensee Event Report Number Qate Title of occurrence l

96-018 9/3/96 Technical Specification Surveillance Requirements were misinterpreted due to a conservative misunderstanding of the requirement.96-019 9/4/96 Main steam line radiation monitor functional test not performed within frequency established for Technical Specifications when in Refueling mode due to incomplete documentation of a Technical Specification Interpretation.96-020 9/7/96 Control Room Emergency Filtration System inoperable due to operator i

knowledge weakness.

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

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nrHOP3WRCWONWLY RVT

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DATA TABULATIONS The fv110 wing data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions l

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i APPENDIX C a

i OPERATING DATA REPORT DOCKET NO.

50-254 UNIT One DATE October 10, 1996 l

COMPLETED BY Kristal Moore i

j TELEPHONE (309) 654-2241

{

OPERATING STATUS 0000 0901 %

1. REPORTING PERIOD: 2400 093096 GROSS HOURS IN REPORTING PERIOD: 720 t

2. CURREPrrLY AlfTHORIZED POWER LEVEL (MWL): 25tl MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

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

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4. REASONS FOR RESTRICTION (IF ANY):

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THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 720.00 1836.70 162300.20

6. REACTOR RESERVE SHIJTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 597.50 1560.70 157319.90 l

8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 1158168.00 3447229.90 341853027.50

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 344281.00 1078677.00 110692758.00

!1. NET ELECTRICAL ENERGY GENERATED (MWH) 326343.00 1025587.00 104499963.00

12. REACTOR SERVICE FACTOR 100.00 27.93 75.66

13. REACTOR AVAILABILrrY FACTOR 100.00 27.93 77.26

14. UNrr SERVICE FACTOR 82.99 23.74 73.34

15. UNrr AVAILABILITY FACTOR 82.99 23.74 73.76

16. UNrr CAPACfrY FACTOR (Using MDC) 58.94 20.28 63.35

17. UNrr CAPActrY FACTOR (Using Design MWe) 57.45 19.77 61.74

18. UNIT FORCED OUTAGE RATE 16.38 6.97 7.58

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

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

1

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

)

FORECAST ACHIEVED INirlAL CRTriCALrrY i

INrrlAL ELECTRICfrY COMMERCIAL OPERATION 1.1 u-9 TECHOP3\\NRC\\MONLY.RFr i

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-265 UNrr Two DATE October 10, 1996 COMPLETED BY Kristal. Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 090196

1. REPORTING PERIOD: 2400 093096 GROSS HOURS IN REPORTING PERIOD: 720

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

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

4. REASONS FOR RESTRICTION (IF ANY):

i THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTrlCAL 720.00 4307.10 158377.55

6. REACTOR RESERVE SHtrTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 720.00 4240.80 154140.35

8. UNIT RESERVE SHirrDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATFD (MWH) 1720979.00 10315946.50 334657167.42 1

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 539883.00 3245375.00 107430910.00 l

11. NET ELECralCAL ENERGY GENERATED (MWH) 514753.00 3146763.00 101799649.00

12. REACTOR SERVICE FACTOR 100.00 65.51 74.37

13. REACTOR AVAILABILTrY FACTOR 100.00 65.51 75.78

14. UNrr SERVICE FACTOR 100.00 64.50 72.38 i

15. UNTT AVAILABILrrY FAcrOR 100.00 64.50 72.71

16. UNTT CAPActrY FACTOR (Using MDC) 92.97 62.24 62.17

17. UNrr CAPACfrY FACTOR (Using Design MWe) 90.61 60.66 60.59 I8. UNrr FORCED OUTAGE RATE 0.00 35.50 11.26 i

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19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): 2/1/97 1

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

21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTrlAL CRTilCALrrY INTTIAL ELEC11tlCfrY COMMERCIAL OPERATION 1.19-9 4

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APPENDIX B l

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 i

UNIT One DATE October 10. 1996 l

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH September 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

53 17.

576 2.

-2 18.

714 3.

-9 19.

744 4.

-9 20.

770 5.

-9 21.

763 6.

109 22.

776 7.

143 23.

776 i

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223 24.

776 i

9.

175 25.

774 10.

7 26.

773 11.

391 27.

761 12.

387 28.

667 13.

380 29.

781 14.

391 30.

778 15.

420 31.

16.

507 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 TECHOP3'NRCTMONTELY.RPT

1 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE October 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH September 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

723 17.

759 2

2.

740 18, 761 3.

737 19.

762 4.

737 20.

761 5.

738 21.

761 6.

720 22.

720 7.

674 23.

761 8.

745 24.

762 9.

743 25, 762 10.

739 26.

401 11.

741 27.

275 12.

743 28.

711 13.

747 29.

721 14.

748 30.

767 15.

715 31.

16.

757 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 i

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 TECHOP3\\NRc\\ MON 1HLY.RPT

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Kristal Moore l

DATE October 10, 1996 REPORT MONTH September 1996 TELEPHONE 309-654-2241 l

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LICENSEE O

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS 9643 09/01/96 S

5.5 C

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Continuation of QlRld Refuel Outage.

l 9643 09/02/96 F

%.4 A

9 Forced Outage Q1F37 Due to ID MSIV Failing j

Timing Requirernents.

96-04' 09/10/96 F

20.6 A

9 Forced Outage Due to 3508C Flow Control Valve Repairs.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE October 10. 1996 REPORT MONTH Sootember. 1996 TELEPHONE 309-654-2241 a:

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LICENSEE DURAT70N EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOUR 13)

REPORT 96-06 9 26- %

P 0.0 A

5 Reduced load to maintain vacuum and troubleshoot air ejectors and offges problems.

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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 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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b RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/96 TO 09/30/96 t

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AVERAGE TIME IN SECONDS AT %

l MAX. TIME ll INSERTED FROM FULLY WITHDRAWN l FOR 90%

! INSERTION DESCRIPTION NUMBER l

5 20 t

50 90 t

,l Technical Specification 4.3.D, 4.3.E &

DATE

! OF RODS

! O.375 ! O.900 2.00 3.5 l

7 sec.

1 4.3.F (Averace Scram Insertion Timel l

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1/13/96 l

29 l 0.339 0.708 1.459 2.538 l

2.91 Scram Time Test for Viton Issue U-2 l

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30 l 0.325 l 0.691 l 1.436 l 2.495 l

2.71 l Scram Time Test for Viton Issue l

(M-8) at EOC U1 I

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! O.349 I O.722 l 1.496 l

2.577 l

3.07 l

Scram Time Test for Viton Issue U-2 2/25/96 l

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4/22/96 1

0.32 0.69 1.46 2.54 l

2.54 l

PMTV for Scram Valve Leak on U-2 e

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5/05/96 177 0.308 i O.713 l 1.543 2.700 3.03 Beginning of Cycle for U-1 F

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8/16/96 l

177 l 0.330 ! O.707 1.473 l: 2.569 2.85 i

PMTV for SSPV Maintenace U-2 l

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12 0.319 l 0.703 l 1.478 l 2.573 ll 2.79 l

PMTV for various Maintenance U-1

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(F-6) i 9/26/96 10 l 0.358 l 0.734 1.497 2.602 2.78 STT for Viton Issue U-2 l

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VII.

REFUELING INFORMATION i

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

t 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 QUAD CITIES REFUEL 8NG October 1989 INFORMATION REQUEST 1.

Unit:

01 Reload:

14 Cycle:

15 2.

Scheduled date for next refueling shutdown:

2/10/98 3.

Scheduled date for restart following refueling:

4/1/98 l

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 supporting information:

6.

Important licensing 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:

232 GE10 Fuel Bundles were loaded during Q1R14.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

724 o

b.

Number of assemblies in spent fuel pool:

1933

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8.

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

planned in number 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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APPROVED (final)

OCT 3 01989 14/0395t '

C).C.O.S.R.

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QTP 300-S32 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

13 Cycle:

14 2.

Scheduled date for next refueling shutdown:

3/1/97 3.

Scheduled date for restart following refueling:

5/23/97 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 licensing action and supporting information:

August 1996 6.

Important licensing 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:

Approx. 216 Siemens 9X9IX Power Corporation Fuel Bundles will be loaded during Q2R14.

i 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 requestou or is 3

planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel: