Text

Monthly Operating Rept for Apr 1996 for Quad-Cities Nuclear Power Station Unit 1 & 2
	ML20112B058
Person / Time
Site:	Quad Cities
Issue date:	04/30/1996
From:	Moore K; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20112B043	List: ML20112B041; ML20112B058; ML20112B083;
References
	NUDOCS 9605220144
	Download: ML20112B058 (19)
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT April 1996 COMMONWEALTH EDISON COMPANY l

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

l-LICENSE NOS. DPR-29 AND DPR-30 l

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i 9605220144 960503 PDR ADOCK 05000254 R

PDR i

TECHOI5WRC\\MONTMLY.RIT v

TABLE OF CONTENTS 1.

Introduction II.

Summary of Operating Experience 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 VII.

Refueling Information VIII.

Glossary 1TCHOP3WRC\\ MONTHLY,RPT u

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I.

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 nwned 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; pursurnt to l

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 l

niaber 209-654-2241, extensions 3070 and 2240, respectively.

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II.

SUMARY OF OPERATING EXPERIENCE l

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A.

Unit One Quad Cities Unit One spent the month of April,1996 shutdown in Refuel l

Outage Q1R14.

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Unit Two l

Quad Cities Unit Two spent the entire month of April 1996 on line. A few load drops were performed, however the average daily power level' i

remained at 80% or greater.

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III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENAE L l

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A.

Amendments to Facility License or Technical Specifications Technical Specification Amendment No.149 was issued on April 2,1996 to Facility Operating License DPR-29 and Amendment No. 143 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments contained issuance of amendments related to TSUP Section 6.0.

l B.

Facility or Procedure Chanaes Reauirina NRC Aooroval i

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

1 C.

Tests and Experiments Reauirina NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

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TFLHOP3WRC\\ MONTHLY.RFT

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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 the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report Number Daig Title of occurrence There were no licensee event reports for Unit I for this reporting period.

l UNIT 2 Licensee Event i

Report Number Q11g Title of occurrence l

There were no licensee event reports for Unit 2 for this reporting period.

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V.

DATA TABULATIONS j

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

TECHOP3WitCGdONTMLY.RPT

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APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-254 UNTT One DATE May 3,1996 COMPLETED BY Kriste' Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 0401 %

1. REPORTING PERIOD: 2400 043096 GROSS HOURS IN REPORTING PERIOD: 719

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

3. POWER LEVLLTO WHICH RESRICTED (IF ANY)(MWe-Net): N/A

4. REASONS FOR RESRIC110N (IF ANY):

THIS MOPUH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 0.00

%4.10 161427.60

6. REACTOR RESERVE SHUIDOWN HOURS 0.00 0.00 3421.90 1

7. HOURS GENERATOR ON LINE 0.00 963.20 156722.40

8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 2288399.50 340694197.10

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 7343 %.00 110348477.00

11. NLT ELECTRICAL ENERGY GENERATED (MWH) 0.00 699244.00 104173620.00 j

12. REACTOR SERVICE FACTOR 0.00 33.21 76.57

13. REACTOR AVAILABILTTY FACTOR 0.00 33.21 75.19

14. UNTT SERVICE FACTOR 0.00 33.18 74.33

15. UNTT AVAILABILTTY FACTGa 0.00 33.18 74.76

16. UNTT CAPACTTY FACTOR (Uning MDC) 0.00 31.32 64.25

17. UNTT CAPACITY FACTOR (Using Design MWe) 0.00 30.53 62.62

18. UNTT FORCED OITTAGE RATE 0.00 0.00 7.54

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DA1T OF STARTUP: N/A

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTTICALTTY INTTIAL ELECTRICTTY COMMERCIAL OPERATION 1.1 +9 TECHOP3WRC\\ MONTHLY.RPT

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APPENDIX C OPERATING DATA REPORT 4

DOCKET NO.

50-265 i

UNrr Two 3'

l DATE - May 3,1996 i

COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STA1VS 3

0000 040196 l

1. REPORTING PERIOD 2400 043096 GROSS HOURS IN REPORTING PERIOD 719

2. CURRENTLY AlfrHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 l

DESIGN BIECmICAL RATING (MWe-NET): 789

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

4. REASONS FOR RESTRICTION (IF ANY):

THis MOPrrH YR TO DATE CUMULATIVE i

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5. NUMBER OF HOURS REACIDR WAS CRT11 CAL 719.00 2903.00 156973.45 i

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6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80 i

-,. URS GENRATOR ON LINE 719.00 2894.50 152794.05

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8. UNrr RESERVE SK7FDOWN HOURS 0.00 0.00 702.90 4

9. GROSS THERMAL ENERGY GENERATED (MWH) 1780551.50 7125516.10 331466737.02 i

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10. GROSS ELECMICAL ENERGY GENERATED (MWH) 570915.00 2285212.00 106430747.00

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I1. NET ELEC1RICAL ENERGY GENERATED (MWH) 550722.00 2200124.00 100853010.00

12. REACTOR SERVICE FACIDR 100.00 100.00 75.01 I

13. REACTOR AVAILABILrrY FACIOR 100.00 100.00 76.43 i

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14. UNrr SERVICE FACTOR 100.00 99.71 73.01 a

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15. UNrr AVAILABILrrY FACTOR 100.00 99.71 73.35

16. UNrr CAPACTTY FACTOR (Usias MDC) 99.60 98.55 62.67

17. UNrr CAPACfrY FACTOR (Using Design MWe) 97.08 96.06 61.08 IS. UNrr PORCED OUTAGE RATE 0.00 0.29 10.13

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTB4ATED DATE OF STARTUP: N/A

21. UNrrS IN TEST STATUS (PIUOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrrIAL CRrrtCALrrY INrrIAL ELECTRICfrY COMMERCIAL OPERATION 1.1 +9 TECHOPl\\NRCudON'THLY.RFr 1

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 l

UNIT One DATE May 3. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH April 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-7 17.

-8 2.

-7 18.

-8 3.

-7 19.

-8 4.

-7 20.

-8 5.

-8 21.

-8 6.

-8 22.

-8 7.

-7 23.

-8 l

8.

-8 24.

-8 9.

-8 25.

-8 10.

-8 26.

-8 11.

-7 27.

-8 12.

-8 28.

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-8 29.

-8 14.

-8 30.

-8 15.

-8 31.

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-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.

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l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two L

DATE May 3. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH Aoril 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

'1.

780 17, 762 2.

779 18.

764 3.

778 19.

769 4.

776 20.

771 5.

780 21.

719 6.

778 22.

764 7.

778 23.

771 8.

776 24.

767 i

9.

'778 25.

768 10.

776 26.

755 11.

777 27.

745 12.

774 28.

767 13.

775 29.

772 i

14.

670 30, 772 15.

765 31.

16.

758 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 figure:;

will be used to plot a graph for each reporting month. Note that when maximum l

dependable capacity is used for the net electrical rating of the unit, there i

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 i

output sheet should be footnoted to explain the apparent anomaly, i

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS 4

1 DOCKET NO.

50-254 a

i UNIT NAMEi'J one COMPLETED BY Kristal Moore 1

5 DATE May 3.

1996 REPORT MONTH Anril 1996 TELEPHONE 309-654-2241 5

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n LICENSEE i

DURATION EVENT NO.

DATE (HOURS)

REPORT CORRECTIVE ACTIONS / COMMENTS I

96-02 04/01/96 5

719.0 C

4 C*astaa of Q1R14 Refuel Outage.

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l APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT NAME Two COMPLETED BY Eristal Moore DATE May 3, 1996 REPORT MONTH Aoril 1996 TELEPHONE 309-654-2241 a:

N O@

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MM M

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M LICENSEE O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS)

REPORT j

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l, VI. UN10VE 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 l

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 & 2 CONTROL ROD DRIVES, FROM 01/01/96 TO 04/30/96 l AVERAGE TIME IN SECONDS AT %

l MAX. TIME j INSERTED FROM FULLY WITHDRAWN l MR 90%

! IngrMTION DESCRIPTION NUMBER 5

20 50 1

90 Technical Specification 3.3.C.1 &

DATE l

OF RODS 0.375 ! 0.900 2.00 3.5 7 sec.

3.3.C.2 fAveraoe Scram Insertion Time) l I

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1/13/96 l

29 0.339 0.708 1.459 2.538 2.91 l

Scram Time Test for Viton Issue (K10) j 1

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30 l 0.325 1 0.691 1 1.436 l 2.495 l

2.71 l

Scram Time Test for Viton issue l

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2/25/96 18

! 0.349 1 0.722 1.496 l; 2.577 3.07 l

Scram Time Test for Viton Issue U-2 (M-8) j i

4/22/96 1

0.32 0.69 1.46 2.54 2.54 l

PMTV for Scram Valve Leak on U-2 ll l

(K-5)

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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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TFfHOP3\\NRC\\ MONTHLY.RPT

QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST g

1.

Unit:

01 Reload:

14 Cycle:

n 2.

Scheduled date for next refueling shutdown:

2/10/96 3.

Scheduled date for restart following refueling:

5/10/96 4.

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

l NO 5.

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

supporting information:

6-1-96 i

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

or different fuel design or supplier, unreviewed design or performance l

analysis 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:

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 l

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:

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

QTP 300-532

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Revisicn 2 QUAD CITIES REFUELING Oct:bar 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

13 l'

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 proposed licensing action and supporting information:

November, 1996 6.

Important Ilconsing cons'derations associated with refueling, e.g., new i

or different fuel design or supplier, unreviewed design or performance analysis methods, significant enanges in fuel design, new operating procedures:

Approx. 224 Siemens 9X9II 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 licensed spent fuel pool storage capactty 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 Itcensed capacity:

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APPROVED (final)

E30N 14/0395t O.C.O.S.R.

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VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI