ML20134M281

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Monthly Operating Rept for Oct 1996 for Quad Cities Nuclear Station
ML20134M281
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 10/31/1996
From: Moore K, Pearce L
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-96-079, LWP-96-79, NUDOCS 9611250005
Download: ML20134M281 (19)
v • d • e


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Commonwealth Illiwn Company

  • Quad Citien Generating Station 22710 2cfith Avenue North Cordova, lL 61212A)740 Tel MP)65 6-22 41 LWP-96-079 November 8, 1996 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 l Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 1

l Enclosed for your information is the Monthly Performance Report covering j the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of October 1996.

Respectfully, Comed Quad-Cities uclear Power Station

, a 2 [blLL L. W. Pearce Station Manager LWP/dak Enclosure j y ng cc: A. Beach, Regional Administrator C. Miller, Senior Resident Inspector &gvf /

i STMGR\079%.1.WP 9611250005 961031 PDR ADOCK 05000254 R PDR A l'nicom compan>

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QUAD-CITIES NUCLEAR POWER STATION l

l UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT  :

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OCTOBER 1996 ,

i COMMONWEALTH EDIS0N COMPANY 1

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MID-AMERICAN ENERGY COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

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

8. Unit Two i

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 ,

Unit Shutdo*:ns and Power Reductions C.

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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I. INTRODUCTION j 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 Mid-American Energy Company. The Nuclear I Steam Supply Systems are General Electric Company Boiling Water Reactors. The i Architect /Eng'ineer was Sargent & Lundy, Incorporated, and the primary l construction contractor was United Engineers & Constructors. The Mississippi -

l 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, )

i respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of j initial Reactor criticalities for Units One and Two, respectively were October 18,-1971, and April 26, 1972. Commercial generation of power began on 4

February 18, 1973 for Unit One and March 10, 1973 for unit Two. l This report was compiled by Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3C70 and 2240, respectively.

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II.

SUMMARY

OF OPERATING EXPERIENCE

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i A. Unit One i Quad Cities Unit One was on-line the entire month of October 1996. A 1 few load drops were performed for Weekly Turbine Testing, however the average daily power level remained at 80% or greater.

B. Unit Two Quad Cities Unit Two was Critical the entire month of October 1996. On October 24, 1996 at 0345 hours0.00399 days <br />0.0958 hours <br />5.704365e-4 weeks <br />1.312725e-4 months <br /> the Turbine was taken off-line to l investigate why the #1 Combined Intermediate Valve drifted closed.

The investigation revealed a hydraulic problem. The unit came back on-line Friday, October 25, 1996, but was forced back off-line Sunday, October 27, 1996 at 2125 hours0.0246 days <br />0.59 hours <br />0.00351 weeks <br />8.085625e-4 months <br />. The forced outage was due to foreign material located in the Moisture Separator Drain Tank Level Control Valves. The unit was synched to the grid October 30, 1996 at 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br />.

DiCHOP3\NRC\ MONTHLY.RPT

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III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MAINTENANCE 1

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 Chanaes Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for I the reporting period. l C. Tests and Experiments Reauirina NRC Acoroval 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 occurring during the reporting period, pursuant to the reportable occurrence reporting requirements of 10CFR50.73.

UNIT 1 Licensee Event Report Number Dalg Title of occurrence 96-014 9/27/96 Electrical distribution weekly surveillance did not document voltage verification in accordance with Technical Specification 4.9E to an inadequate procedure.96-021 10/11/96 B Control Room HVAC System was Declared Inoperable due to Crankcase Heater Power Supply Design Deficiency.96-022 10/28/96 B Control Room HVAC IN0P due to unable to maintain +1/8" Positive Pressure in Control Room Compared to surrounding area.

UNIT 2 Licensee Event Reoort Number Qate Title of occurrence 96-002 10/9/96 High Pressure Coolant Injection Inoperable due to Inadequate Venting.

TECHOP3\NRC\ MON 1HLY.RIT

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V. DATA TABULATIONS I i

i j' The following data tabulations are presented in this report: I l A. Operating Data Report t

B. Average Daily Unit Power Level

. C. Unit Shutdown.s and Power Reductions j l

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TECHOP3\NRC\ MON 1ELY.RPT

_,_.m... . ~ . . _ . . _ . _ . _ _ _ . - _ . _ _ . _ _ . _ _ - . . _ _ _ _ . ~ - _ _ . - _ _ . _ _ _ _ __ _._. .._._ m 4; 3.y , j

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. I APPENDIX C j- OPERATING DATA REPORT i DOCKLT NO. 50-254 l t

( UNrr One l

! DATE Noveinber 8, <

IM y COMPLITIED BY Kristal Moore y TELEPsNE (309) 654-2241 l OPERATING STATUS 1 I

0000 1001 %

1. REPORTING PERIOD: 2400 103196 GROSS HOURS IN REPORTING PERIOD 745
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEFEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Ne0: N/A
4. REASONS FOR RESTRICTION (IF ANY):  !

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 745.00 2581.70 163045.20
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.G0 3421.90 )

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7. HOURS GENERATOR ON LINE 745.00 2305.70 158064.90
8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 909.20
9. GROSS THERMAL ENERGY GENERATED (MWH) 1863336.00 5310565.90 343716363.50 ,
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 604229.00 1682906.00 1112 % 987.00 I1. NET ELECTRICAL ENERGY GENERATED (MWH) 577883.00 1603470.00 105077846.00
12. REACTOR SERVICE FACTOR 100.00 35.27 75.75
13. REACTOR AVAILABILrrY FACTOR 100.00 ,35.27 77.34
14. UNrr SERVICE FACTOR 100.00 71.50 73.43
15. UNTT AVAILABILITY FACTOR 100.00 31.50 73.85
16. UNIT CAPACfrY FACTOR (Using MDC) 100.87 28.49 63.48
17. UNIT CAPACfrY FACTOR (Uning Design MWe) 98.31 27.76 61.87
18. UNrr PORCED OUTAGE RATE 0.00 4.83 7.55 j
19. SHUrDOWNS SCHEDULED OVER NEXT 6 MONTHS CrYPE, DATE AND DURATION OF EACH): N/A l 1
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
21. UNrrs IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A ]

FORECAST . ACHIEVED INrrlAL CRITICALrrY INITIAL [1.ECIRICfrY COMMERCIAL OPERATION l 1.1 F9  !

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APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNrr Two DATE November 8, 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-224i OPERATING STATUS 0000 100196

1. REPORTING PERIOD: 2400 103196 GROSS HOURS IN REPORTING PERIOD: 745
2. CURRENTLY AITTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPActrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. M)WER LEVELTO WHICH RESTRICTED (IF ANY)(MWe-Net): N/A a
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 745.00 5052.10 159112.55 l

, 6. REACTOR RESERVE SHLTTDOWN HOURS 0.00 0.00 2985.80

7. HOURS GENERATOR ON LINE 645.00 4885.80 154785.35 t
8. UNrr RESERVE SHlfrDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 1488014.40 11803960.90 336145181.82
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 453926.00 3739301.00 107884836.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 433048.00 3579811.00 102232697.00
12. REACTOR SERVICE FACTOR 100.00 69.02 74.46 l
13. REACTOR AVAILABILrrY FACTOR 100.00 69.02 75.86
14. UNrr SERVICE FACTOR 86.58 66.75 72.43
15. UNIT AVAILABILrrY FACTOR 86.58 66.75 72.76 l 16. UNIT CAPACfrY FACTOR (Using MDC) 75.59 63.59 62.21 j 17. UNrr CAFACITY FACTOR (Using Design MWe) 73.67 61.98 60.64
18. UNIT FORCED OUTAGE RATE 13.42 33.25 11.27 [
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): 3/1/97
20. IF SHITTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
21. UNrr$ IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A e I FORECAST ACHIEVED  !

INTilAL CRrrlCALITY INITIAL ELECTRicrrY

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, i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE November 8. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH October 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 779 17. 773 l l
2. 777 18. 774 l
3. 780 19, 761
4. 780 20. 776 5, 771 21. 779
6. 778 22. 780
7. 779 23. 781
8. 780 24. 775
9. 780 25. 772
10. 781 26. 749
11. 780 27. 776
12. 759 28, 771 l
13. 780 29. 772
14. 779 30, 775
15. 779 31. 778
16. 778 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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i APPENDIX'B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE November 8. 1996 COMPLETED BY Kristal Moore I

MONTH October 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) a 1.. 767 17. 767

2. 767 18. 768
3. 767 19. 769
4. 767 20. 743 I
5. 760 21. 771
6. 750 22. 771
7. 767 23. 367
8. 767 24. 16 __
9. 767 25. -3
10. 756 26. 324
11. 771 27. 230
12. 770 28. -9
13. 755 29. -9
14. 768 30. 110
15. 767 31. 176
16. 766 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 rest.ricted 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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4 APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254

UNIT NAME Qng COMPLETED BY Kristal Moore 4 DATE November 8, 1996 REPORT MONTH October 1996 TELEPHONE 309-654-2241 a

M h hM M B8 h 2

N al's Hz 58 a $

29

$m LICENSEE O DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS None for the month of October.

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APPENDIX D UNIT StiUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE November 8. 1996 REPORT MONTH October 1996 TELEPHONE 309-654-2241 m

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$Mh LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE 8

(HOURS) REPORT _ _ ,

96-07 10 24-% F 43.7 A 9 --------- --- ---- Turbine Trip to kwfisthoot #1 combined 1 intermediate valve.

96-C3 10-27-97 F 56.3 A 9 --------- -- -- - Tripped Turbine to support inspections of the the Moisture Separator Drain Tank Level i Control Valves. I l

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VI. UNIOUE REPORTING RE0VIREMENTS 1 The following items are included in this report based on prior commitments to- I the commission:

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

I 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. '

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1 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'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

,' QUA0 CITIES REFUELING October 1989

. INFORMATION REQUEST

1. Unit: Q1 Reload: 14 Cycle: 15
2. Scheduled date for next refueling shutdown: 2/10/98
3. Scheduled date for restart following refueling: 4/1/98
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 informat?on: ,
6. Important Itcensing 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 Q1R15 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 and the size of any increase in licensed storage capacity that has been requested or is N planned in number of fuel assemblies:
a. Licensed storage capacity for spent fuel: vs7
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 Itcensed capacity:

APPROVED ,

(final) 14/0395t OCT 3 01989 G.C.O.S.R.

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QTP 300-532

  • Revision 2

. QUA0 CITIES REFlJELING October 1989 i

INFORMATION REQUEST

1. Unit: Q2 Reload: 13 Cycle: 14 i 2. Scheduled date for next refueling shutdown: 3/1/97
3. Scheduled date for restart following refueling: s/23/97 j 4. Will refueling or resumption of operation thereafter require a Technical i

Specification change or other license amendment: -

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! 5. Scheduled date(s) for subaltting proposed licensing action and i supporting information: ,

1 August 1996 -

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) 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 216 Siemens 9X91X Power Corporation Fuel Bundles will be loaded

, during Q2R14.

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7. The number of fuel assemblies.

j , a. Number of assemblies in core: 724 I b. Number of assemblies in spent fuel pool: 2727

8. The present licensed spent fuel pool storage capacity and the size of i any increase in licensed storage capacity that has been requested or is 4

3 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 Itcensed capacity:

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APPROVED ,

J (final) 14/0395t OCT 3 01989 G.C.O.S.R.

0 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 - 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 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 TiiCHOP3\NRC\ MON 1MLY.RPT

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