ML20216J069

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Monthly Operating Repts for Aug 1997 for Quad Cities Nuclear Station,Units 1 & 2
ML20216J069
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 08/31/1997
From: Pearce L, Sirles K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-97-097, LWP-97-97, NUDOCS 9709170147
Download: ML20216J069 (19)
v • d • e


Text

________-_______ --_____--__-__ - - - -

( onuconwtalth lihwn umilun)

Quad Otits Generating Station

, 22710 2@th Asenue Nor.h Lordova. 11.612124/740 Tri .wn,s i 22 41 LWP-97-097

! September 9, 1997 U.S. Nuclear Regulatory Commission i

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 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 August, 1997.

Respectfully, Comed Qua -Cities Nuclear Power Station

/

i I li h'd LL I

" ll.' b ~ Pearce W. h ,.

Station Manager g LWP/dak Enclosure oc: A. Beach, Regional Administrator

} 7 (} (. 'D' C. Miller, Senior Resident Inspector stuomo9miw -

970917014'7 970831 FDR ADOCK 05000254 lfl[rhlll-llll,ll[lf[l.l((.f[ l R PDR *.

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i QUAD-C1 TIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1997 I

COMMONWEALTH EDISON COMPANY AND MIDAM'ERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265-LICENSE NOS. DPR-29 AND DPR-30 t

. TECHOPENRC440NTHLY.RPT

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 Proceduro-Changes Requiring NRC Approval l

C. Tests and Experiments Requiring NRC Approval Licensee Event Reports IV.

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 1smOMWROM0mWLY.Rrr

I. INTRODUCTION 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 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 &

Constructors. The Mississippi River is the condtnser 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 Kristal Sirles and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively.

TECHOP3\NRC\ MONTHLY.RFT

II.

SUMMARY

OF' OPERATING EXPERIENCE A '. Unit One I Quad Cities Unit One was on-line the entire month of. August 1997.- .A few-load drops were performed during the month to reverse Condenser flow, conduct Turbine Weekly---Testing,-and 4 at the request of Bulk Power Operations, however the average daily power level remained at 80% or greater.

B. Unit'Two Quad Cities Unit Two was on-line the entire month of August 1997. On August 6, 1997 at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, a load reduction.

was initiated in preparation for Drywell--entry to identify l 'the source fc.y increased input-and temperature of the Drywell Equipment Drain Sump. The stem leakoff line on RHR 2-1001-68A had significant flow. The in-line isolation valve on the stem leakoff line was closed. The Drywell Equipment Drain Sump temperature and input dropped. The RHR 2-1001-68A valve has been scheduled for maintenance during the next refuel outage. on August 113, 1997 at 0000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />s-a load drop commenced for Furmanite repairs on the 2A Moisture Separator Drain Tank Vent-Flange. Another load drop was performed-on August 30, 1997 at-2100' hours for- 1 Turbine-Weekly Testing and Control Rod Drive Testing.

i 193EOMWWNE)NWlX.Mi Mcwo a o

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. III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE A. Amendments tg Facility License or Technical Sp.ecifications There were no Amendments to the Facility License or Technical specifications for the reporting period.

I B. Facility or Procedure Chanags Reauirina NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

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

r TECHOP3\NRC\MOPrDILY.RPT

4 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 requirementa of 10CFR50.73.

UNIT 1-Licensee Event Repcrt Number Date Title of occurrence 97-016 8/7/97 Diesel Generator Cooling Water Inservice Testing Requirements were r.ot completed when an inaccurate predefined work request used for scheduling was implemented, i l 97-019 8/8/97 Technical Specification 3.0.C-was entered because there was no Limiting Condition For Operation 1 available for Secondary containment when both doors for an Interlock were opened simultaneously.

UNIT 2 Licensee Event Report Number Date Title of occurrence 97-010 8/19/97 Obtained a once every eight hour Compensatory offgas Hydrogen Sample 30 Minutes Late due to a communication error during shift turnover.between two Chemistry Technicians.

NOTE: Sequence _of LER Numbers is out of order due to reuse of numbers.

11!CHOPENRCM40NTHLY.RPT

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 1TLTOM\NRC\ MON 1HLY.RPT

APPENDIX C OPERATING DATA REM)RT DOCKET NO, 50 254 UNTT One t

DATE September 9, 1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 OPERATING STATUS 0000 080197

1. REPORTING PERIOD: 2400 083197 GROSS liOURS IN REK)RTING PERIOD: 744
2. CURRENTLY ALTTliORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTR} CAL RATING (MWe NET): 789
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 CRTTICAL 744.00 5212.10 169721.30
6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 3421.90
7. IlOURS GENERATOR ON LINE 744.00 5123.50 164652.40
8. UNTT RESERVE SHITTDOWN HOURS 0.00 0.00 909.20
9. GROSS THERM AL ENERGY GENERATED (MWlO 1844344.80 12127102.80 359299985.30

(

10. GROSS ELECTRICAL ENERGY GENERATED (MWH') 582470.00 3874446.00 116295876.00 lI. NET ELECTRICAL ENERGY GENERATED (MW10 555280.00 3699871.00 109854840.00
12. REACTOR SERVICE FACTOR 100.00 89.39 76.26
13. REACTOR AVAILABILTTY FACTOR 100.00 89.39 77.80
14. UNTT SERVICE FACTOR 100.00 87.87 73.98
15. UNTT AVAILABILTTY FACTOR 100.00 87.87 74.39
16. UNTT CAPACTTY FACTOR (Using MDC) 97.05 82.51 64.19
17. UNTT CAPACTTY FACTOR (Using Design MWe) 94.59 80.42 62.56
18. UNTT FORCED OUTAGE RATE 0.00 12.13 7.64
19. SHITTDOWNS SCHEDULED OVER NEXT 6 MONTils (TYPE, DATE, AND DURATION OF EACH): QlP01 1/3/98 1/24/98
20. IF SlitTTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTTICALTTY INTTIAL ELECTRICTTY COMMERCIAL OPERATION 1TCHOP3\NRC\ MONTHLY.RPT J

APPENDDC C OPERATING DATA REPORT DOCKET NO. 50-265 UNrr Two DATE SePteneer 9 1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 OPERATING STATUS 0000 080197

1. REPORTING PERIOD: 2400 083197 GROSS IlOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACirY: 769 DESIGN ELECTRICAL RATING (MWe. NET): 789 l
3. POWER LEVEL TO WHICH RESTRICTED (1F ANY)(MWe.Nc0: N/A
4. REASONS FOR RES11tlCTION (IF ANY):

TH15 MONTil YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTilCAL 744.00 3139.80 163726.35
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80
7. HOURS GENERATOR ON LINE 744.00 3082.60 159331.95
8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENEROY GENERATED (MWH) 1637437.20 7117183.80 346789272.62
10. GROSS ELECT 1tlCAL ENERGY GENERATED (MWH) 512416.00 2247826.00 Ii1164963.00 l1. NET ELECTRICAL ENEROY GENERATED (MWH) 489744.00 2150923.00 105470644.00
12. REACTOR SERVICE FACTOR 100.00 53.85 74.09
13. REACTOR AVAILABILITY FACTOR 100.00 53.85 75.44
14. UNrr SERVICE FACTOR 100.00 $2.87 72.10
15. UNTT AVAILABILTTY FACTOR 100.00 52.87 72.41
16. UNTT CAPACTTY FACTOR (Using MDC) 85.60 47.97 62.06
17. UNfr CAPACTTY FACTOR (Using Design MWe) 83.43 46.75 60.49
18. UNTT FORCED OLTAGE RATE 0.00 0.37 10.99
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH): Q2P0110/4/91 10d4/97
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
21. UNrrs IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRTTICALTTY INTTIAL ELECTRICfrY COMMERCIAL OPERATION

'TfHOP3WROMONTHLY.Rrr

, APPENDIX R AVERACE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE Sootember 9, 1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 MONTH Auaust 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net) (HWe-Net)

1. 749 17. 740
2. 743 18. 742
3. 740 19. 753
4. 727 20. 756
5. 733 21. 758
6. . 729 22. 759
7. 710 23, 746
8. 689 24. 761
9. 746 25. 758
10. 736 26, 757 11, 746 27.. 755
12. - 756 28. 755
13. 758 29. 754
14. 756 30. 750
15. 756 31. 757
16. 745 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 not 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 TECHOP3*RcWONTHLY.RPT

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APPENDIX B

. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE september 9, 1997 COMPLETED BY Kristal Sirles TELEPHONE f309) 654-2241 MONTH Aucust 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met) (MWe-Net)

1. 755 17. 720
2. 747 18. 717
3. 709 19. 759
4. 756 20. 761
5. 755 21. 762
6. 176 22. 759
7. 55 23. 757
8. 442 24. 713

' 9. 510 25. 762

10. 510 26, 764
11. 646 27. 762 L 12, 701 28, 761
13. 433 ;S. 762
14. - 584 30. 746 i

15.- 739 31. 649

16. 719 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 not electrical rating of the unit, there

- may be' occasions-when'the daily average power level' exceeds the 100% line (or the restricted powsr level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TECHOP3\NRC340N1HLY.RFT

  • APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS h

DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Sirles DATE Sect -her 9, 1997 REPORT MONTH Auoust 1997 TELEPHONE 309-654-2241 m CE 8

E8 l 1l.9 lE

- lE

, sICEN EE 8 DURATION g EVENT NOo DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS Nosw I

l TFCHOP3\NRC\ MONTHLY.RPT 1

1

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. APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCMT NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Sirles DATE gant W r 9, 1997 REPORT MONTH Auoust 1997 7ELEPHONE 309-654-2241 ,

a:

to 5

Q H *$

D g E8 $8 E LICENSEE 8 DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NOo DATE Q (HOURS) REPORT

! 9747 8/6/97 F 0 A 5 - -. .- - Performed tend Drop to determine cause of Drywell Equipment Drain Sump increased i inputs and temperature.

1 97-C3 8/13/97 F 0 A 5 --- - - - Performed Load Drop to Furmanits the 2A Moisture Separator Drain Tank Vent Flange.

9749 8/31/97 3 0 B 5 -- -- --

Performed Lead Drop for Weekly Turbine Testing and Control Rod Drive Pattern Test.

(

TECHOp3\NRC\MOKlHLY.RIT

, VI . UNIQUE 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 Steh3. Relief Valve Operations for the reporting period.

B. Control Rod Drive Scram Timina Data for Units One and Two i

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

l TBCHOPMtC\MOPrTHLY.RIT

4 VII. REFUELING INFORMATLQH

- 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.

l l

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TECHOP3\NRCudONTHLY.RIT j

4 QTP 0300-S32 ROvicion 3 April 1997

', QUAD CITIES REFUELING INFORMATION REQUEST

1. Unit: 01 Reload: 14 Cycle:

15

2. Scheduled date for next refueling shutdown: 9/05/98
3. Scheduled date for restart following refueling: 11/14/98
4. Will re ?ueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment:

Yes

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

November, 1997

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 i

Approx. 216 SPC 9X9IX Fuel Bundles QlR15 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 (final) 1

QTP 0300-S32 R3vicion 3 April 1997

', , QUAD CITIES REFUELING INFORMATION REQUEST

1. Units 02 Reload 14 Cycles 15
2. Scheduled date for next refueling shutdown: 2/20/99
3. Scheduled data for restart following refueling: 3/27/99
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, 1998

6. Important censing considerations associated with refueling, e.g., new or differw.c fuel design or supplier, unreviewed design or performance sinalysis 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 precent 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: O 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

7,; '.

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

ACAD/ CAM - Atmospheric ContainmentLAtmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute l 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 - Integrated Primary Containment Leak Rate Test IRM: - Intermediate Range Monitor ISI - Inservice Inspection LER- - 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 l NIOSH -LNational Institute for Occupational Safety and Health PCI. - Primary containment-Isolation PCIONR. --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 Centrol RSDC_ -- Shutdown Coolitig Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor iTBCCW - Turbine Building Closed Cooling Water System - -

TIP . Traversing Incore Probe TSC- - Technical Support Center i

TBCHOPS\NRC\MONTHLYMT

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