SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2

Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2

ML20249A570
Person / Time
Site:	Quad Cities
Issue date:	05/31/1998
From:	Dimmette J, Hamilton L COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-98-215, NUDOCS 9806170084
Download: ML20249A570 (19)

Text

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Commonwealth liliwn Compary 7 Quad Citics Generating $tation 22710 2!(>th Avenue North Cordova, 11.61242-9740 Tei S m a 224:

SVP-98-215 June 10,1998 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk

Subject:

Quad Cities Nuclear Power Station Units 1 and 2 Monthly Performance Report NRC Docket Numbers 50-254 and 50-265 Facility Operating License Numbers DPR-29 and DPR-30 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 May 1998.

Ifyou have any questions conceining this letter, please contact Mr. Charles Peterson, Regulatory Affairr Manager, at (309) 654-2241, extension 3609.

Since ely,  !

n l A w -

cel P. Dimmette, Jr.

Site Vice President l Quad Cities Station Attachment cc: C. J. Paperiello, Acting Regional Administrator, Region Ill R. M. Pulsifer, Project Manager, NRR }

C. G. Miller, Senior Resident Inspector, Quad Cities f W. D. Leech, MidAmerican Energy Company D. C. Tubbs, MidAmerican Energy Company F. A. Spangencerg, Regulatory Affairs Manager, Dresden ,(

INPO Records Center  ;

, [L OfTice of Nuclear Facility Safety, IDNS

,s~ DCD License (both electronic and hard copies)

M. E. Wagnr, Licensing, Comed S.P. Focht, American Nuclear Insurers Bob Ganser, IDNS Lynne Hamilton, Quad Cities Da Kelley, Quad Cities SVP Letter File 990617oos4 990531 PDR ADOCK 05000254 R PH u

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MAY 1998 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 1

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I 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 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 l

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I. INTRODUCTION l

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 Net, located in Cordova, Illinois.

The Station is jr.,intly owned by Commonwealth Edison Company and MidAmerican Energy Company. The Nuclear Steam Supply Gystems are General Electric Company Boiling Water Reactors. The Architect /

Engineer was Sargent & Lundy, Incorporvced, and the primary construction contractor was United Engineers & Constructors. The Mississippi River la 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 Lynne Hamilton and Debra Kelley, telephone number 309-654-2241, extensions 3114 and 2240, respectively.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit one was off-line the entire month of May, 1998 due to an unplanned extension-of Maintenance

' Outage Q1P01. On May 31, 1999 at 3:20 a.m., Unit One commenced start-up activities with the pulling of rods and at 6:26 a.m. the reactor went critical. As of 4:30 p.m.on May 31, 1908 the unit was at 150 pounds of pressure and low pressure HPCI/RCIC runs were beginning.

B. Unit Two Quad Cities Unit Two began the month of May, 1998 shutdown due to-an unplanned extension of Maintenance Outage Q2P01.

On May 23,'1998 at 3:15 a.m., Unit Two commenced start-up activities with the pulling of rods and at 6:15 a.m. the reactor went critical.- On May 26, 1998 at 2:45 a.m., Unit Two was synchronized to the grid. The Quad Cities Station Senior Management Review Board conducted collegial _ reviews at 40%, 60% and 90% power ascension hold-points during start-up of Unit Two. Unit Two continued its ascent in power, reaching 98% power, 785 MWe at 4:30 p.m. on May 31, 1998.

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• III. PLANT 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 Recuirina NRC ADoroval On March J1, 1998 the NRC issued to Quad Cities an exemption from the requirements of 10CFR70.24. The exemption was based on Quad Cities plant design for fuel storage, handling and use which precludes an accidental criticality event.

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

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c IV. LICENSEE EVENT REPORTS i l

i The following is a tabular summary of all licensee event reports  ;

for Quad-Cities Units One and two submitted during the reporting I period.

UNIT 1 Licensee Event Submission Report Number Date Title of Occurrence 98-16 5/11/98 Technical Specification Scram Discharge Volume Instrumer.ts Exceeded Setpoint Due to Insufficient Setpoint Margin as a Result of a Cognitive Engineering Error.

98-06, R1 5/29/98 Reactor Building (RB) Post Loss of Coolant Accident (LOCA)

Temperatures are Higher Than Values Used for the Environmental Qualification of Electrical Equipment Due to Invalid Engineering Judgment, The Cause of Which Cannot Be Determined.

98-12, R1 5/29/98 The Unit One Reactor Bottom Head Drain Line Developed a Leak Due to Outside Diameter Initiated Stress Cracking When Surface-Contaminants Were Inadvertently Introduced As a Result of an Isolated Inadequate' Work Practice During Original Installation.

UNIT 2 Licensee Event Submission Eeoort Number Date TJtle of Occurrence

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None.

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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

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APPENDIX B

. . AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 l UNIT One DATE June 10, 1998 COMPLETED BY Lynne Hamilton

, TELEPHONE f309) 654-2241 j MONTH May 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net)

1. -7 17. - 8

2. -6 18. - 8

3. -7 19. - 6

4. -7 20. - 8 l

l S. -7 21. -8 I 6. -7 22. - 7

7. -7 23. - 8

8. -6 24. -11 l

l 9. -7 25. -11 l

10. -6 26. -9 11.- -6 27. -8

12. -5 28. -8 l 13. -5 29. -9

14. -5 30. - 8

15. -6 31. -9

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 j

. . AVERAGE DAILY UNIT POWER LEVEL )

DOCKET NO 50-265 UNIT Two DATE June 10, 1998 COMPLETED BY Lynne Hamilton TELEPHONE (309) 654-2241 l MONTH May 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -7 17. -8

2. -7 38. -8

3. -7 19. -8

4. -7 20. -8

5. -7 21. -8

6. -7 22. -8

7. -7 23. -8

8. - 6 24. -10

9. -

7 25. -11

10. -6 26. 101

11. -5 27. 121

12. -5 28. 313

13. -5 29. 552

14. -5 30. 603

15. -5 31. 745

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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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. APPENDDC C OPERATING DATA REPORT DOCKET NO. 50-254 UNTT One DATE June 10,1998 l COMPLETED BY Lynne Hamilton TELEPHONE (309) 654-2241 OPERATING STATUS 0000 050198

1. REPORTING PERIOD: 2400 053198 GROSS HOURS IN REPORTING PERIOD: 744

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

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

4. REASONS FOR RESTRICTION (IF ANY):

THis MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 17.40 17.40 172392.80

c. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 0.00 0.00 167295.30

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

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

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 118253369.00

!! NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 0.00 106154969.00

12. REACTYR SERVICE FACTOR 2.34 0.48 75.25

13. REACTOR AVAILABILITY FACTOR 2.34 0.48 76.74

14. UNIT SERVICE FACTOR 0.00 0.00 73.02

15. UNTT AVAILABILITY FACTOR 0.00 0.00 73.42

16. UNIT CAPACTTY FACTOR (Using MDC) 0.00 0.00 60.25

17. UNTT CAPACTTY FACTOR (Using Design MWe) 0.00 0.00 58.73

18. UNIT FORCED OUTAGE RATE 0.00 0.01 7.19

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

Refuel, t1/07/98,40 days

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

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVFD INTn'IAL CRTTICALTTY l INTTIAL ELECTRICITY COMMERCIAL OPERATION

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APPENDIX C OPERATING DATA REPORT l DOCKET NO. 50-265 UNrr Two DATE June 10,1998 COMPLETED BY Lynne Hamilton TELEPilONE (309) 654-2241 OPERATING STATUS 0000 050198

1. REPORTING PERIOD: 2400 053198 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AITTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACirY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 3 POWER LEVEL TO WHICH RES11tlCTED OF ANY)(MWe-Net): N/A

4. REASONS FOR RESTRICr10N OF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 209.75 209.75 164576.80

6. REACFOR RESERVE SHtTTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 141.30 141.30 160111.15

8. UNrr RESERVE SHITTDOWN IIOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWil) 218539.20 218539.20 348574795.52

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 62014.00 62014.00 111824558.00

11. NET ELECTRICAL ENERGY GENERATED (MWH) 54108.00 54108.00 106001566.00

12. REACTOR SERVICE FACTOR 28.19 5.79 72.33

13. REACTOR AVAILABILrrY FACTOR 28.19 5.79 73.64

14. UNrr SERVICE FACTOR 18.99 3.90 70.37

15. UNTT AVAILABILITY FACTOR 18.99 3. #' 70.68

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16. UNrr CAPACITY FACTOR (Using MDC) 9.46 1.94 5 60.58

17. UNrr CAPACrrY FACTOR (Using Design MWe) 9.22 1.89 59.04

18. UNrr FORCED OLTTAGE RATE 0.00 0.00 11.18

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): None

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

21. UNirS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrrlAL Crit"CALrrY INITIAL ELECTRICrrY COMMERCIAL OPERATION ,

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-254 UNIT NAME One COMPLETED BY Lynne Hamilton DATE June 10, 1998 REPORT MONTH May, 1998 TELEPHONE 309-654-2241 {

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DURATION EVENT No. DATE 8 (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 9842 980501 S 744.0 B 4 --- - - ---

Continuation of Maintenance Outage 01P01 (Unplanned Extension).

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I APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 1

UNIT NAME Two COMPLETED BY Lynne Hamilton DATE June 10, 1998 REPORT MONTH May, 1998 TELEPHONE 309-654-2241 l

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@ LICENSEE 8 DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE A (HOURS) REPORT 98-01 980501 5 602.7 B 4 --...-- ---- ---

Continuation of Maintenance Outage Q2P01 (Unplanned Extension).

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

A.-Main Steam Relief Valve Operations l Relief. valve operations during the reporting period are ]

l 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: .TVo Date: May 24, 1998 Valve Actuated: Lo. & Tyne of Actuation:

l 2-0203-3A 1 Manual 2-0203-3B 1 Manual 2-0203-3C 3 Manual (Note 1) 2-0203-3D. 1 Manual )

2-0203-3E 3 Manual (Note 1) l Plant Conditions: Reactor Pressure - 320'psig Description of Events: QCOS 0203-03 " Main Steam Relief Valves l Operability: Test" l

' Note 1:

The second test of 2-0203-3C was performed due to a burned out: closed light bulb on panel 902-3. This second test ,

proved the valve worked properly. The third test of 2- l 0203-3C was performed in conjunction with the investigation

[ of 2-0203-3E PORV stroke times in a comparison of valve timing.

The'first test of the 2-0703-3E shoded the closed stroke

. time of the valve was out d de the In-Service Testing timing criteria. The second test of 2-0203-3E was to confirm the closed stroked time of the FORV was outside the IST timing criteria as allowed by the code. The third test of the 2-0203-3E>was conducted in conjunction with the investigation of the stroke times by PIF (1998-02632.

B. Control Rod Drive Scram Timing Data for Units One and Two The. basis for reporting this Cata to the Nuclear Regulatory Commission.is.specified in the surveillance requirements of Technical Specifications 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 timirg for the reporting period. All scram timing.was performed with reactor pressure greater than 800 PSIG.-

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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' Brian 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 0300-S32 Rzvision 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST l 4

1. Unit: 01 Reload: 14 Cycle: 15 I l

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

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

4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendments l

Yes

5. Scheduled date(s) for1 submitting proposed licensing action and supporting information:

Approved l

6. Important licensing considerations associated with refueling, e.g., ew 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.

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'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 i

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9. The projected date of the last refueling that can -

be discharged to the spent fuel pool assuming the present licensed capacity: 2002 '

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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 9%

6. Importent licensing consideration.s 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 l procedures:

N/A I l

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7. The number of fuel assemblies. I

a. Number of assemblies in cores i;4

b. Number of assemblies in spent fuel pool: 2943 l 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 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: 2002 (final) 2 L_____________..______________.-.__________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . . _ -.________.__._________.__.__._-.________________________________.-____,__._..J

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VIII. GLOSSARY The following abbreviations which may have been used in the i 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 1 CRD - Control Rod Drive.

EHC~ - Electro-Hydraulic. Control System

. EOF' - Emergency Operations Facility j GSEPf - Generating Stations Emergency' Plan l HEPA' - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System l HRSS - High Radiation Sampling System I

.IPCLRT .- Integrated. Primary Containment Leak Rate Test )

IRM0

- Intermediate Range Monitor 1 ISI - Inservice. Inspection LER> . Licensee Event Report LLRT - Local Leak Rate Test LPCI. - Low Pressure Coolant Injection Mode of RHRs

'LPRM - Local PowerLRange Monitor .

MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio MFLCPR - Maximum Fraction' Limiting Critical Power Ratio l MPC - Maximum Permissible Concentration MSIV - Main Steam Isolation Valve .

NIOSH - National. Institute for Occupational Safety and Health .I PCI - Primary Containment Isolation PCIONR - Preconditioning Interim Operating Manacement 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 i

'TBCCW Turbine Building Closed. Cooling Water System.

TIP; - Traversing:Incore Probe-TSC' - Technical Support-Center l-I, TBCHOPS\NHCU40N'Dft.Y.RPT

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