Text

Monthly Operating Repts for March 1993 for Quad Cities Nuclear Power Station Units 1 & 2
	ML20035D431
Person / Time
Site:	Quad Cities
Issue date:	03/31/1993
From:	Michael Benson, Walsh R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RJW-93-13, NUDOCS 9304130205
	Download: ML20035D431 (21)
	v • d • e

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4 O Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North j

Corcova, Illinois 61242 Telephone 309/654 2/41 RJW-93-13 i

April 1, 1993 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 I

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 March 1993.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION Robert J. Walsh Tech Staff Supervisor RJW/MB/dak Enclosure cc:

A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector l

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J QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 I

MONTHLY PERFORMANCE REPORT d

MARCH 1993 1

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IOWA-ILLINOIS GAS & ELECTRIC COMPANY f

NRC DOCKET NOS. 50-254 AND 50-265 i

LICENSE NOS. DPR-29 AND DPR-30 I

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1 TABLE OF CONTENTS I.

Introduction l

II.

Summary of Operating Experience r

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 B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions I

VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary l

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INTRODUCTION I

Quad-Cities Nuclear Power Station is composed of tv.) 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 Company and Iowa-Illinois Gas & Electric 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 l

50-254 and 50-265.

The date of initial Reactor criticalities for Units One and i

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.

l This report was compiled by Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

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I II.

SUMMARY

OF OPERATING EXPERIENCE

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A.

Unit One l

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Quad Cities Unit one was critical with the generator off line following a maintenance outage at the end of February. The generator was brought.

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on line at 09:10 on March 1, 1993 and full load was attained at 18:30.

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The unit was dropped from full load to 645 MWe, on March 2, on orders i

from the Chicago Load Dispatch (CLD).

A load drop for gland steam condenser level control valve work was taken on March 6 to 400 MWe between 23:15 and 09:00.

A load drop was initiated at 19:43 on March 11 due to an Electro-l Hydraulic Control (EHC) fluid leak in the #1 main turbine stop valve.

l A manual SCRAM was inserted at 03:15 on March 12 to effect repairs and l

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the unit was made critical again at 17:32 the same day.

The generator l

was synchronized to the grid at 01:04 on March 13 and attained full load j

at 12:35.

Unit One's was reduced to 200 MWe from 21:05 on March 20 till 10:50 on March 21 for turbino bypass valve maintenance and a containment entry to i

replace an equipment drain sump pump.

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Load drops were ordered by CLD to 650 MWe on March 26 and 29.

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B.

Unit Two j

l Quad Cities Unit Two began the month at full power. During Surveillance l

QCOS 203-3, Main Steam Relief Valve Operation", the 3E Relief valve stuck j

open. At 20:21 on March 6,1993 manual SCRAM was inserted per procedure.

i One hour later the 3E valve. cas closed.

The unit continued to cold shutdown starting refuel outags Q2R12. (See License Event Report 265 006.)

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I III.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.

Amendmen C-to Facility License or Technical Soecifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Chances Reauirina NRC Acoroval I

There trere no Facility or Procedure changes requiring NRC approval for

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the teforting period.

C.

Tests and Ernsriments Recruirina NRC Apprqv,a,1_

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

D.

Corrective Maintenance of Safety Related Eculement The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period.

This summary includes the following:

Work Request Numbers, Licensee i

Event Report Numbers, Components, Cause of Malfunctions, Results and I

Effects on Safe Operation, and Action Taken to Prevent Repetition, t

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UNIT 1 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED 004297 9900 HPCI flow computer point A loop calibration was performed indicates flow when no flow at transmitter 1-2358.

FIC and is present.

Investigate and computer point agree within 100 repair.

gpm.

Q04323 263

. Repair or replace reactor Switch was replaced with a new vessel hi pressure switch 1-one.

The new switch was j

0263-55C.

Found to have calibrated.

repeatability problems Q04815 5400 Repair 1-5402B valve.

Limit switch was adjusted.

I Q05014 756 Repair LPRM 08-25C.

Spikes Ran I/V curve to eliminate are occurring causing APRM spiking.

high alarms.

Q05260 900 Repair broken terminal Replaced with a new block.

holder in 901-32 panel.

Q05801 1600 Repair gauge and fittings at Replaced bad fitting, test cap, electrical penetration X-and gauge.

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Q06001 2300 Repair HPCI steam line drain Found valve stuck in the closed steam trap bypass valve 1-position.

Disassembled valve 2301-31.

Failed post The actuator mounting plate to maintenance verification on valve yoke holes were elongated WR Q05073.

for bolt up.

The valve was reassembled and verified operational.

Q06024 2400 Repair oxygen-hydrogen CAM Cleaned slidewires and recorder 1-2406B.

Pen calibrated both pens.

sticks at several locations.

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Q06045 750 Investigate and repair IRM Replaced pre-regulator with pre-15 loss of power.

regulator from IRM 17 Unit 2.

I Q06053 755 Investigate and repair IRM Cleaned input connector at 12 spiking high - caused 1/2 chassis.

Ran I/V curve to fix SCRM4.

spiking.

Q06072 30 Investigate HPCI interlock Found limit switches out of doors open simultaneously adjustment on both doors.

Limit i

twice in a 5 day period.

switches were adjusted and the interlock latches worked properly.

006270 1000 Repair drywell pressure Found isolation valve leaking switch 1-1001-89D.

around the stem.

Tightened packing to stop leak.

l 095303 1600 Rebuild or replace solenoid Found valve would not stroke.

i on nitrogen purge to Valve was removed, rebuilt, and l

containment stop valve 1-reinstalled.

1601-55.

Q96672 1000 Repair mechanical seal leak Replaced mechanical seal.

l on 1A RHR service water pump 1-1001-65A.

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UNIT 2 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED 005599 1400 Repair 2B core spray Found valve leaking from testable check valve 2-1402-stuffing box.

Sealed valve with 9B.

furmanite and reinstalled insulation.

005892 900 Repair alarm light socket in Found existing light socket 902-8 panel.

plastic lip broken off.

Replaced light socket with a new one.

Q06100 7800 Repair breaker in MCC 28-1B Removed the old transformer and compartment D3.

installed a new one.

Aux contacts were cleaned and lubricated.

Q06146 1100 Investigate and repair Found bad light bulb.

Bulb was circuit failure alarm for replaced and alarm cleared.

standby liquid control squib valve 2-1106A.

Q06467 7900 Resplice leads for Respliced and taped 3 distribution transformer in transformer lead connections MCC 28-1A-1 compartment A3.

with lugged and bolted connections.

Q99578 2500 Tnvestigate alarm for ACAD Found indicating lamp bad.

actuation indication 2-2540-Installed new light on dual trip 17B.

Light indication unit, replaced missing screw failed'to appear although holding top of dual trip unit actuation occurred.

in, calibrated, and functionally tested the unit.

l-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.

UNIT 1 Licensee Event Report Number Date Title of Occurrence 93-002 03-02-93 Failure of Secondary Containment Test.93-003 03-05-93 Postulated Loss of LPCI Swing Bus due j

to an original design weakness.93-004 03-31-93 RCIC/lA Core Spray and A & B RER pumps INOP due to check valve being removed.93-005 03-31-93 Control Room vent Toxic Gas Analyzer INOP Ammonia An??/zer.

l WIT 2 Licensee Event Report Number Date Title of Occurence 93-006 03-06-93 Unit 2 Manual Reactor Scram due to 3E ERV stacking open.

i 93-007 03-07-93 MSIVs failed Local Leak Rate Test l

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i 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 l

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APPENDIX C OPERATING DATA REPORT DOCKET ND 50-254 I

UNIT Dne i

DATE April 1.1993 COMPLETED BY Matt Benson l

TELEPHONE (309) 654-2241 4

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1 OPERATING STATUS 0000 030193 j

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1. REPORTING PERIOD: 2400 033193 GROSS HOURS IN REPORTING PERIOD: 744 r

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

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

4. REASONS FOR RESTRICTION (If ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR wa$ CRITICAL...........

729.7 2105.3 144866.2

6. REACTOR RESERVE SHUTDOWN HOURS..................

0.0 0.0 3421.9 4

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7. HOURS GENERATOR ON LINE.......................

713 0 2084.1 140475.7 1

i 0.0 0.0 909.2

8. UNIT RESERVE SHUTDOWN HOURS.........

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

1713103.2 5033071.2 203614895.0

10. GROSS ELECTRICAL ENERGY GENERATED (MWH).

552506.0 1636786.0 98055876.0

11. NET ELECT RICAL ENERGY GENERATED ( MWH )............

531486.0 1570095.Q_

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12. REACTOR SERVICE FACTOR............

98.08 97.47 78.81

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13. REACTOR AVAILABILITY FACTOR............

98.Q3 97.47 80.67

14. UNIT SERVICE FACTOR 95.83 96.4.2 76.42

15. UNIT AVAILABILITY FACTOR.......

95.83 96.49 76_192

16. UNIT CAPACITY FACTOR (Using MDC) 92.90 94.52 65,49 L

17. UNIT CAPACITY FACTOR (Using Design HWe).........

90.54 92.13 63.74

18. UNIT FORCED OUTAGE RATE........................

4.17 3.51 5.78 l

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

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

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

i INITIAL CRITICALITY INITIAL ELECTRICITY a

COMMERCIAL OPERATION Ts u 1.16-9 l

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APPENDIX C OPERATING DATA REPORT DOCKET NO 50-265 UNIT Two DATE Acril 1. 1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 OPERATING STATUS 0000 030193

1. REPORTING PERIOD:

2400 033193 GROSS HOURS IN REPORTING PERIOD:

744 l

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX. DEPEND. CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-Net): 7S9

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

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL............

140.30 1391.62

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6. REACTOR RESERVE SHUTDOWN HOURS.................

0.0 0.0 2985.B.R

7. HOURS GENERATOR ON LINE.....................

140.30 1356.80 136998.25 s

8. UNIT RESERVE SHUTDOWN HOURS......

0.0 0.0 702.90 i

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

346308.00 3310351,20 295973760.40 l

10. GROSS ELECTRICAL ENERGY GENERATED (MWH)..........

113498.00 1084961.00 95110222.00

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

103833.00 1033782.00

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12. REACTOR SERVICE FACTOR............

18.86 64.43 77.13 1

13. REACTOR AVAILABILITY FACTOR................

18.86 64.43 78.77

14. UNIT SERVICE FACTOR............................

18.86 62.81 75.17

15. UNIT AVAILABILITY FACTOR........................

18.86 62.81 75.55

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

____13.15 62.24 64.26

17. UNIT CAPACITY FACTOR (Using Design MWe).

17.69 60.66 62.63 i

18. UNIT FORCED OUTAGE RATE..........

2.84 12.82 7.33

19. SHUTDOWNS SC.4EDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

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

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) l FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO 50-254 UNIT One DATE April 1, 1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 l

MONTH March 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

350 17.

785 l

l 2.

734 18.

783 1

3.

783 19.

782 i

4.

785 20.

766 5.

783 21.

498 6.

629 22.

760 7.

767 23.

784 i

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728 24.

786 l

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770 25.

783 10.

770 26.

755 i

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730 27.

781 12.

18 28.

700 j

r' 13, 592 29.

748 14.

771 30.

780 15.

782 31.

785 i

16.

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INSTRUCTIONS l

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 f

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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1.16-8 NRCMORPT 1

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i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE April 1.

1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH March 1993 I

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) f 1.

783 17.

-8 2.

763 18.

-8 i

3.

784 19.

-8 4.

736 20.

-8 5.

775 21.

-8 i

6.

635 22.

-8 7.

-9 23.

-8 8.

-8

24. __

I 9.

-8 25.

-8 10.

-8 26.

-8 11.

-8 27.

-8 12.

-8 28.

-8 13.

-8 29.

-8 14.

-8 30.

-8 15.

-B 31.

-8 16.

-8 INSTRUCTIONS On this f ann, list the average daily unit power level in MWe-Net for each day in the reperting 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 NRCMORPT

APPENDIX D UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 UNIT NAME One COMPLETED BY Matthew Benson DATE April 1, 1993 REPORT HONTH March, 1993 TELEP110NE 309-654-2241 5

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DATE (HOURS)

REPORT NO.

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93-03 03-02-93 S

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5 Load Drop per CLD 93-04 03-06-93 F

9.8 B

5 Load Drop for Gland Steam Condenser Level Control Valve Work 4

93-05 03-12-93 F

21.8 A

2

1 Stop Valve EllC Leak 93-06 03=21-93 F

13.8 B

5 Drwell Entry to Change Out Sump Pump 93-07 03-26-93 S

5.2 F

5 Load Drop per CLD 93-08 03-29-93 S

5.6 F

5 Load Drop per CLD l

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4 APPF.NDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT MAME Two COMPLETED BY Matthew Bennon DATE April 1, 1993 REPORT HONTH March, 1993 TELEPHONE 309-654-2?A*

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DATE (HOURS)

REPORT NO.

CORRECTIVE ACTIONS /C0tetENTS 93-01 03-06-93 F

4.1 A

2 265-93-006 Relief Valve Stuck Open During Surveillance.

Manual SCRAM Inserted.

93-02 03-06-93 S

599.6 C

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UNIOUE REPORTING REOUIREMENTS The following items are included in this report based on prior commitments to the i

commission:

A.

Main Steam Relief Valve Operations Relitf 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: Two Date: March 6, 1993 Valve Actuated:

No. & Tyne of Actuation:

2-203 3B Manual 2-203-3C Manual 2-203-3E Manual Plant Conditions: ~920 psig Reactor Pressure - Unit shutting down for Q2R12.

Description of Events:

2-203-3B, 2-203-3C tested satisfactory.

2-203-3E would not close - Manual Reactor scram.

2-203-3E re-seated at ~193 psig Reactor Pressure.

B.

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

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VII.

REFUELING INFOFFJsTION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) f rom L. 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 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q1 Reload:

_12 Cycle:

I 13 2.

Scheduled date for next refueling shutdown:

3-14-94 3.

Scheduled date for restart following refueling:

6-13-94 4.

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

NOT AS YET DETERMINED 5.

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

NOT AS YET DETERMINED I

6.

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

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

l NONE AT PRESENT TIME.

7.

The number of fuel assemblies.

l a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1557 l

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:

Licensed storage capacity for spent fuel:

3657 a.

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:

2009 APPROVED e

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

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

Unit:

02 Reload:

12 12 Cycle:

2.

Scheduled date for next refueling shutdown:

03/06/93 3.

Scheduled date for restart following refueling:

05/29/93 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:

NO SUBMITTALS REQUIRED.

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:

NONE AT PRESENT TIME.

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

0 b.

Number of assemblies in spent fuel pool:

3307 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 licensed capacity:

2009 APPROVED (fi"*i) 14/0395t DCT 3 0 M49 Q.C.O.S.R.

VIII.

GLOSSARY l

l 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

- American National Standards Institute i