SVP-98-087, Monthly Operating Repts for Feb 1998 for Quad Cities Nuclear Station,Units 1 & 2

Monthly Operating Repts for Feb 1998 for Quad Cities Nuclear Station,Units 1 & 2

ML20216E547
Person / Time
Site:	Quad Cities
Issue date:	02/28/1998
From:	Kraft E, Stockman D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-98-087, SVP-98-87, NUDOCS 9803180082
Download: ML20216E547 (21)

Text

, . . . .

Onmnonwealth litivin Gimpany a

,, Quad Otics Generating Station I

• . 22710 206th Asenue North Girdova, II. 61212-97 40 rel .urnist22 il i

SVP-98-087 i i

March 10, 1998 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 i 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 February, 1998.

If you have any questions concerning this letter, please contact Mr. Charles Peterson, Regulatory Affairs Manager, at (309) 654-2241, extension 3609.

Respectfully, N.hs E. S. K t IJ r. l' Site Vi President Quad Cities Station i ESK/dak  !

Enclosure cc: A. Beach, Regional Administrator R. Pulsifer, Project Manager, NRR C. Miller, Senior Resident Inspector W. Leech, MidAmerican Energy Company D. Tubbs, MidAmerican Energy Company F. Spangenberg, Regulatory Affairs Manager, Dresden INPO Records Center Office of Nuclear Facility Safety, IDNS DCD License r M. Wagner, Licensing Comed Bob Ganser, IDNS y k. jI Deb Kelley, Quad Cities

, Dick Stockman, Quad Cities

'"" SVP Letter File 9803180082 980228 PDR ADOCK 05000254 R PDR f lltlhlllfflllffflllflf A Unicum Gimpany

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1998 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-263 LICENSE NOS. DPR-29 AND DPR-30 11iCHOP3\NRCWON1HLY.RPT

II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit one was off-line the entire month of February 1998 due to a unplanned extension of maintenance Outage Q1P01.

B. Unit Two Quad Cities Unit Two remained shutdown for the month of February 1998 due to a unplanned extension of maintenance outage Q2P01.

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TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One l 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 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  ;

l A. Main Steam Relief Valve Operations l B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary i

TECHOP3\NRC\ MONTHLY.RFT

49 I. INTRODUCTION 1

Quad-Cities Nuclear. Power Station is composed of two Boiling Water Reactors'and Steam' Turbine / Generators, each with a Maximum Dependable Capacity of 769 MWe'Nat, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and MidAmerican Energy Company. The Nuclear Steam Supply Systems are )

General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent 6 Lundy, Incorporated, and the primary construction contractor was United Engineers & q 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 Dick Stockman and Debra Kelley, I

telephone number 309-654-2241, extensions 3221 and 2240, I respectively.

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III. ELANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE

.A. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.  !

B. Facility or Procedure Chances Reauirina NRC Acoroval j i

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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k IV. LICENSEE EVENT REPORTS  ;

The following is a tabular summary of all licensee event reports for Quad-cities Units One and Two submitted during the raporting period.

1 UNIT 1 Licensee Event Submission Renort Numher Date Title of Occurrence 1-98-01 2/4/98 The Unit One Emergency Diesel Generator (EDG) Received an Inadvertent Start Signal When a Relay Was Bumped During Testing, the EDG Failed to Start as Would i be Expected on Receipt of this Signal, and the EDG was Inadvertently Started 15 Minutes Later Due to an Error by an Operator Who Was Responding to the Failure to Start.

1-97-26, R1 2/4/98 Technical Specification (TS)

Required Instrument Channel checks and Primary Containment Sump Flowrate Surveillances Were Not Documented Prior to Entering the Applicable Mode Due to Inadequate Procedure Development and Review.

1-98-03 2/5/98 Technical Specification (TS)

Limiting Condition for Operation (LCO) was exceeded when both Standby Gas Treatment (SBGT) subsystems were inoperable because both the Unit 1 and the Unit 2 Emergency Diesel Generators (EDG) were inoperable due to inadequate procedure development and review.

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1 UNIT 1 CONTINUED Licensee Event Submission l Report Number Date Title of Occurrence I l-98-04 2/12/98 Residual Heat Removal (RHR) )

Shutdown Cooling Common Suction Header was Made Inoperable Due to a Technical Specification  ;

Limiting Condition for Operation i (LCO) When Evaluating an I Unacceptable.Nechari.ical Shock-Arrestor (Snubber) Due to Operations and Engineering Knowledge Deficiencies and an i Inadequate Procedure.  ;

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1-98-07 2/11/98 The design basis of the Quad Cities Station Reactor Building  !

(RB) superstructure is not in literal conformance with Updated Final Safety Analysis Report '

(UFSAR) description of Class I loading combinations. This is due to the fact that the FSAR, when originally written, lacked sufficient detail in description of Class I loading combinations i for addressing infrequent loading conditions (such as the  !

crane) concurrent with a seismic event.

1-98-08 2/26/98 Residual Heat Removal (RHR)

Shutdown Cooling Common Suction Header was Inoperable Due to Inadequate Installation Instructions Resulting in ,

Mechanical Failure of a I Mechanical Shock Arrestor (Snubber). i 1-98-06 2/25/98 Reactor Building Post Loss of I Coolant Accident (LOCA)

Temperatures are Higher Than i Values Used for the Environmental Qualification of Electrical Equipment Due to Unvalidated Engineering Judgement, the Cause of Which Cannot Be Determined.

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UNIT 2 Licensee Event- Submission Report Number Date Title of Occurrence The were no U2 LER's for this reporting period.

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V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Average Daily Unit Power Level B. Operating Data Report C. Unit Shutdowns and Power Reductions j

TTCHOP3\NRC\ MON 1HLY.RIT

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j APPENDIX C OPERATING DATA REPORT DOCKETNO. 50-254 UNrr One DATE Marcli10,1998 COMPLETED BY Dick Stockman TELEPHONE (309) 654-2241 OPERATING STATUS 0000 020198

1. REPORTING PERIOD: 2400 022898 OROSS HOURS IN REPORTING PERIOD: 672

2. CURRENTLY AlfrHnas7mn POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPActrY: 769 DESION ELECTRICAL RATING (MWe-NET): 789

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

4. REASONS POR RESTRICrlON (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrICAL 0.00 0.00 172375.40 i 1

6. REACTOR RESERVE SHLTTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 0.00 0.00 167295.30

8. UNIT RESERVE SHUrDOWN HOURS 0.00 0.00 909.20 1

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 365437242.60

10. OROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 118253369.00 ;

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11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 106154969.00

12. REACTOR SERVICE FACTOR 0.00 0.00 75.97

13. REACTOR AVAILABILTTY FACTOR 0.00 0.00 77.48

14. UNTT SERVICE FACTOR 0.00 0.00 73.73

15. UNTT AVAILABILrrY FACTOR 0.00 0.00 74.13

16. UNTT CAPACTTY FACTOR (Using MDC) 0.00 0.00 60.84

17. UNTT CAPACfrY FACTOR (Using Design MWe) 0.00 0.00 59.30

18. UNTT PORCED OUTAGE RATE 0.00 0.03 7.19

19. SHtTfDOWNS SCHEDULED OVER NEXT 6 MONTHS frYPE DATE. AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: QlP01 - 4/17/98

21. UNTIS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTrlCALrrY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.1u-9

'IECHOPS\NRC\ MON'IMLY.RFr

APPENDIX C OPIRATING DATA REPORT DOCKET NO. 50-265 UNIT Two DATE March 10,1998 COMPLETED BY Dick Stockman TELEPHONE (309) 654-2241 OPERATING STATUS 0000 020198

1. REPORTING PERIOD: 2400 022898 GROSS HOURS IN REPORTING PFJtlOD: 672 2, CURRENTLY AITTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVELTO 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 CRTTICAL 0.00 0.00 164367.05

6. REACTOR RESERVE SHtTTDOWN HOURS 0.00 0.00 2985.80

7. HOURS 'IENERATOR ON LINE 0.00 0.00 159969.85

8. UNrr RESERVE SHLTrDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 0.00 348356256.32

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 111762544.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 105947458.00

12. REACTOR SERVICE FACTOR 0.00 0.00 72.94

13. REACTOR AVAILABILrrY FACTOR 0.00 0.00 74.27

14. UNrr SERVICE FACTOR 0.00 0.00 70.99

15. UNir AVAILABILTTY F ACTOR 0.00 0.00 71.30

16. UNrr C.APActrY FACTOR (Using MDC) 0.00 0.00 61.14

17. UNIT CAPACrrY FACTOR (Using Design MWe) 0.00 0.00 59.59

18. UNIT FORCED OUTAGE RATE 0.00 0.00 11.19

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP:Q2P01 - 4/12/98

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

FORECAST ACHIEVED INrrIAL CRrrlCALrrY INTrlAL ELECTRICrrY COMMERCIAL OPERATION 1.16-9 TIUiOP3\NRC\MONT1tLY.RFr

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i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL I

DOCKET NO 50-254 UNIT One DATE March 10. 1998 COMPLETED BY Dick Stock ==n TELEPHONE f309) 654-2241 NONTH February 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -7 17. -

7

2. -7 18. - 7

3. -7 19. -

7

4. -6 20. - 7

5. -7 21. - 7

6. -8 22. -

8

7. -8 23. -

8

8. -8 24. - 7

9. -8 25. - 7

10. -8 26. -

7

11. -8 27. -

7

12. -8 28. - 7

13. -8 29.

14. -7 30.

15. -7 31.

16. -7 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 March 10, 1998 COMPLETED BY Dick Stockman TELEPHONE (309) 654-2241 MONTH Februay 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -7,, 17. -7

2. -7 18. -7

3. -7 19. -7

4. -7 20. -7

5. -7 21. -6

6. -8 22. -8

7. -8 23. -7

8. -8 24. -6

9. -8 25. -7

10. -8 26. -7

11. -8 27. -7

12. -8 28. -7

13. -8 29.

14. -8 30.

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15. -7 _._ 31.

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16. -7 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 not electrical rating of the unit, there .

may be occasions when the daily average power level exceeds the 100% line (or l the restricted power level line). In such cases, the sverage daily unit power j output sheet should be footnoted to explain the apparent anomaly. 1 1.16-8 TECHOP3\NRC\ mon 1HLY.RPT

1 APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Dick Stockman DATE March 10. 1998 REPORT MONTH February 1998 TELEPHONE 309-654-2241 a:

M to E O

O@ M M z

E8A 2 N

39 N na M

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$ LICENSEE DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 98 4 980201 5 672.0 B 4 --..- -- ---

Continuation of Maintenance Outage QIP01 (Unplanned Extension).

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' APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 l

UNIT NAME Two COMPLETED BY Dick Stockman DATE March 10, 1998 REPORT MONTH February 1998 TELEPHONE 309-654-2241 a:

m = 00 X r- a n: ==

C he l $eb5 LICENSEE 08 m

28 O

DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT ,

9841 980201 S 672.0 B 4 ------ ---- ---

Continuation of Maintenance Outage Q2P01 (Unplanned Extension).

TECHOP3\NHC\MOND{LY.RPT

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 There were no Main Steam Relief Valve Operations for the reporting period.

B. Control Rod Drive Scram Timina 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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REFUELING INFORMATION l , VII.

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The following information about future reloads at Quad-cities l Station was requested in a January 26, 1978, licensing memorandum I l (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-cities and Zion Stati 1--NRC Request for Refueling Information", dated January 18, 1978.

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.. QTP 0300-S32 R visien 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST

1. Unit 01 Reload: 14 Cycle: 15

2. Scheduled date for next refueling shutdown: 11/07/98

3. Scheduled date for restart following refueling: 12/17/98 4

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

Yes

5. scheduled date(s) for submitting proposed licensing action and supporting information:

Approved

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 SPC 9X9IX Fuel Bundles will be loaded.

7. The number of fuel assemblies. ,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pools 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 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: 2002 i

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, QTP 0300-832 R vicion 3 April 1997

• QUAD CITIES REFUELING INFORMATION REQUEST

1. Unit 02 Reload: 14 Cycle: 15

2. Scheduled date for next refueling shutdown: 1/8/2000

3. Scheduled date for restart following refueling: 2/17/2000

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, 1999

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:

N/A

7. The number of fuel assemblies,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool 2943

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 j

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2002 l

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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 - American National Standards Institute APRM - Average Power Range Monitor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations Facility GSEP - Generating Stations Emergency Plan HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT - 7"tagrated Primary Containment Leak Rate Test IRM - Intermediate Range Monitor ISI - Inservice' Inspection LER. - Licensee Event Report LLRT - Local Leak Rate Test i LPCI - Low Pressure Coolant Injection Mode of RHRs j LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio ,

MFLCPR - Maximum Fraction Limiting Critical Power Ratio  !

MPC - Maximum Permissible Concentration MSIV - Main Steam Isolation Valve  ;

NIOSH - National Institute for Occupational Safety and Health PCI - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations ,

RBCCW - Reactor Building Closed Cooling Water System RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System RWM - Rod Worth Minimizer SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP- - Traversing Incore Probe TSC - Technical Support Center TBCHOPS\NRCG40N1MLY.RIPT -