ML20237A625

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Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2
ML20237A625
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/31/1998
From: Hamilton L
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20237A620 List:
References
NUDOCS 9808140218
Download: ML20237A625 (18)
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QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT i

JULY 1998 l I

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COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY i

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

l 9908140218 900010 7T PDR ADOCK 05000254 R PDR c I

- TirHOP3\NRC\ AUGUST 98.IX)C

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TABLE OF CONTENTE I. Introduction

11. 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 oi 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. Average Daily Unit Power Level B. Operating Data Report C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Red Drive Scram Timing Data VII. Refueling Information Vill. Glossary TlfHOP3\NRC\AUGUS198. DOC

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I. INTRODUCTION Quad Cities Nuclear Power Station is composed of two Boiling Water Reactors and Steam Turbine / Generators, each with a Maxhnum Dependable Capacity of 769 MWe Net, 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 & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constrictors. 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 ofinitial 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, TIrHOP3*RCMUGUST98. DOC ,

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II.

SUMMARY

OF OPERATING EXPERIENCE l

l A. Unit One i

Quad Cities Unit One began the month of July 1998 operating at full power with minor interruptions for routine maintenance and surveillance testing. On July 17,1998 a load drop to 350 MWe occurred to repair a steam leak on the IB Moisture Separator Drain Tank flex hose (average daily unit power level reduction of 33 percent). Load was increased to full power on July 19,1998. On July 24,1998 a load drop to 350 MWe i again occurred to repair a steam leak on the IB Moisture Separator Drain Tank vent pipe (average daily unit power level reduction of 15 percent). On July 25,1998 load was increased to full power. Unit One operated at full power the remainder of the month.

i B. Unit Two Quad Cities Unit Two was synchronized to the grid at 1:43 a.m. on July 1,1998. The Unit began a load increase and reached full power on July 3,1998 at 5:00 p.m.

Unit Two operated throughout the remainder of the month at full power with minor interruptions for routine maintenance and surveillance testing.

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Ill. PLANT OR PP XEDURE CHANGES. TESTS. EXPERIMENT _S.

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

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

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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 reporting period.

UNIT 1 Licensee Event Submission Report Number Date Title of Occurrence 1-98-17 7/22/98 ' "B" Train CR HVAC Trip 1-98-18 7/28/98 Rx Scram During APRM Surv UNIT 2 Licensee Event Submission Repon Number Date Title c,f Occurrence 2-98-03 7/28/98 Rx Scram During Adverse Weather I

TirHOP3 sNRC\ AUGUST 98. DOC i.

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

A. Average Daily Unit Power Level B. Operating Data Report C. Unit Shutde vns and Power Reductions 11rHOP3WRGAUGU3195. DOC

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-254 UNIT: ONE DATE: August 10,1998 COMPLETED BY: Lynne Hamilton TELEPHONE: (309)654-2241 MONTH: July 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (Mwe-Net)

1. 265 17.. 745
2. 707 18. 501 1
3. 760 19. 759 l
4. 759 20. 760 5, 759 21, 760
6. 763 22. 760
7. 767 23. 762
8. 766 24. 739
9. 766 25. 630
10. 763 26, 764
11. 768 27. 764 j
12. 763 28. 765
13. 763 29. 764 I l
14. 761 30. 765
15. 761 31. 765
16. 761 l e l

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 j month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may t be occasions when the daily average power level exceeds the 1009E line (or the restricted power level line). In  ;

such cases, the average daily unit power output sheet should be footnoted to explain the apparent anonuly.

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TECHOP3WRCMUGU5193.1X)C w-____- --

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL  ;

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DOCKET NO.: 50-265 l UNIT: TWO ,

DATE: August 10,1998 COMPLETED BY: Lynne Hamilton l TELEPHONE: (309)654-2241 l i

l MONTH: July 1998 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i

1. I13 17. 765
2. 613 18. 765 ,
3. 670 19. 761 4, 766 20. 762 1
5. 768 21. 761 I l
6. 769 22, 762 l 7, 761 23. 762 j
8. 769 24. 767 .

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9. 768 25, 767 l
10. 767 26, 768
11. 771 27. 768
12. 754 28. 767
13. 768 29. 767
14. 765 30. 768
15. 765 31. 768
16. 764 INSTRUCilONS: 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 mor.th. Note that when maximum dependable capacity is used for the nn: Atr;eal sating of the umt, 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 t

TECHoP3\NkC\ AUGUST 98. Doc

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APPENDIX C OPERATING DATA REPORT DOCKET NO: 50-254 UNIT: One DATE: August 10,1998 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654-2241 OPERATING STATUS 0000 070198

1. REPORTING PERIOD: 2400 073198 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWc-NET): N/A
4. REASONS FOR RESTRICTION (IF ANY):

TIIIS MONTil YEAR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 1438.40 173813.80
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90
7. HOURS GENERATOR ON LINE 744.00 1354.50 - 168649.80

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8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20
9. GROSS THERMAL ENERGY GENERATED (MWH) 17933532.00 19254160.80 384691403.40
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 552086.00 971309.00 119224678.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 525668.00 922745.00 107077714.00
12. REACTOR SERVICE FACTOR 100.00 28.28 75.39
13. REACTOR AVAILABILITY FACTOR 100.00 28.28 76.87
14. UNIT SERVICE FACTOR 100.00 26.63 73.15
15. UNIT AVAILABILITY FACTOR 100.00 26.63 73.54
16. UNIT CAPACITY FACTOR (Using MDC) 91.83 23.59 60.39
17. UNIT CAPACITY FACTOR (Using Design Mwe) 89.55 22.99 58.86
18. UNIT FORCED OUTAGE RATE 0.00 0.03 7.18
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

Refuel, .11/07/98,30 days.

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STAR FUP: N/A
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACillEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERAITON l.16-9 i

TECHQPhNRCMUGUSTM DOC

APPENDIX C OPERAllNG DATA REPORT DOCKET NO: 50-265 UNIT: Two DATE: August 10,1998 COMPLETED BY: Lynne Hamilton TELEPHONE: (309) 654E41 OPERATING STATUS 0000 070198

1. REPORTING PERIOD: 2400 073198 GROSS IlOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 DESICN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(Mwe-NET): N/A
4. REASONS FOR RESTRICTION (IF ANY):

Tills MONTil YEAR TO DATE CUMULATIVE

5. NUMBER OF llOURS RFACTOR WAS CRITICAL 744.00 1619.25 165986.30
6. REACTOR RESERVE SHUTDOWN IIOURS 0.00 0.00 2985.80
7. HOURS GENERATOR ON LINE 742.30 1501.60 161471.45
8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 180369.60 3513878.40 351870134.72
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 552790.00 1083987.00 112846531.00
11. NET ELECTRICAL ENERGY GENERATED (MWil) 529647.00 1032044.00 106979502.00
12. REACTOR SERVICE FACTOR 100.00 31.83 72.48 j
13. REACTOR AVAILABILITY FACTOR 100.00 31.83 73.79
14. UNIT SERVICE FACTOR 99.77 29.52 70.51 l
15. UNIT AVAILABILITY FACTOR 99.77 29.52 30 82 j
16. UNIT CAPACITY FACTOR (Using MDC) 92.57 26.38 60.75
17. UNIT CAPACITY FACTOR (Using Design Mwe) 90.23 25.71 59.21
18. UNIT FORCED OUTAGE RATE 0.23 6.46  !!.15
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACH):

None

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACIIIEVED INITIAL CRIT!CALITY INITIAL ELECTRICITY COMMERCIAL OPERAITON 1.'6-9 l

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS  !

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DOCKET NO. 50-254 COMPLETED BY: Lynne Hamilton UNIT NAME: One TELEPHONE: 309-654-2241 DATE: August 10,1998 REPORT MONTH July 1998 NO DATE TYPE DURATION REASON METIIOD I,ICENSEE SYSTFAI COMPONENT CORRECTIVE )

FOR (llOURS) OF EVENT CODE CODE ACTIONS / COMMENTS j S SilUTTING REPORT DOWN NO.

REACTOR 98-07 980718 F 0 A 5 - -

IB Moisture Separator Drain Tank Repairs (20%

lead Reduction) 4 Legend:

(1) Reason A - Equipment Failure (Explain)

B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training /Licene Examination F- Administrative G - Operational Error -(Explain)

H - Other (Explain)

(2) Method 1 - Manual 2 - Manual Trip / Scram 3 - Automatic Trip / Scram j 4 - Continuation '

5 - Other (Explain) 1TrHOP3\NRC\AUGUS198 DOC

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS i

DOCKET NO. 50-265 COMPLETED BY: Lynne Hamilton UNIT NAME: Two TELEPHONE: 309 4 54-2241 DATE: August 10,1998 REPORT MONTH: July 1998 NO DATE TYPE DURATION REASON METilOD LICENSEE SYSTEM COMPONENT CORRECTIVE FOR (llOURS) OF EVENT CODE CODE ACTIONS / COMMENTS S SIIUTTING REPORT DOWN NO.

REACTOR I None l l

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I Legend:

(1) Reason A - Equipment Failure (Explain) j B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training /Licenne Examination F- Administrative G - Operational Error (Explain) 11 - Other (Explain)

(2) Method 1 - Manual 2 - Manual Trip / Scram 3 - Automatic Trip / Scram 4 - Continuation 5 - Other (Explain) i TECHOP3WRC\AIXJUS195. DOC f' _ . _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _ _ ____

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VI. UNIOUE REPORTING REQUIREMENTS I

The following items are included in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Ooerations  !

There were no Relief Valve Operations during the reporting period.

B. Control Rod Drive Scram Timing Data for Units One and Two The following table is a complete summary of Unit One Control Rod Drive Scram  ;

timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 PSIG. Fifteen rods were scram time tested during the month ofJuly 1998.

One control rod was for post-maintenance testing. Fourteen rods were tested for trending data on SSPVs.

ROD DATE 5% 20 % 50 % 90 %

A-6 7/13/98 0.32 0.68 1.43 2.49 )

E-ll 7/18/98 0.32 0.67 1.40 2.45 1 F-13 7/18/98 0.31 0.68 1.45 2.54 F-7 7/18/98- 0.44 0.83 1.59 2.66  :

B-4 7/18/98 0.30 0.65 1.38 2.45 l E-10 7/18/98 0.35 0.72 1.50 2.59' "

G-15 7/18/98 0.32 0.72 1.54 2.70 N-7 7/18/98 0.36 0.74 1.50 2.56 P-7 7/18/98 0.35 0.72 1.46 2.51 1 J-13 7/18/98 0.32 0.68 1.44 2.49 K-ll 7/18/98 0.49 0.88 1.62 2.69 K-9 7/18/98 0.36 0.71 1.44 2.46 N-5 7/18/98 0.36 0.74 1.53 2.65 L-5 7/18/98 0.30 0.66 1.39 2.42 K-7 7/18/98 0.36 0.74 1.50 2.56 The following table is a complete summary of Unit Two Control Rod Drive Scram timing for the reporting period. All scram timing was performed with reactor pressure '

greater than 800 PSIG. One control rod was scram time tested for post-maintenance testing.

ROD DATE 5% 20 */. 50 % 90 %

K-14 7/30/98 0.26 0.60 1.35 2.42 Scram time data percent is all in seconds.

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l VII. REFUELING INFORMATION i 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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l TirHOP3\NRC\ AUGUST 98 IXX'

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/ , QTP 0300-S32 R vicion 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 ., Will refueling or resumption of operation thereafter require'a Technical Specification change or other license amendments 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 pool: 1933
8. The present licensed spent. fuel pool storage capacity ani 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 (final) 1 L____________-_---__--_--__

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1 1 . QTP 0300-S32 j R vicion 3 1 April 1997 )

QUAD CITIES REFUELING i 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 amendments 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 l procedures:

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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 ir, 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

Vill. 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-Efliciency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection L:iR Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRs 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 I 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 l SRM Source Range Monitor l TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center TirHOP3\NRC\ AUGUST 97 000

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