ML20132F041

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Monthly Operating Repts for Nov 1996 for Quad Cities Nuclear Station Units 1 & 2
ML20132F041
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 11/30/1996
From: Moore K, Pearce L
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-96-089, LWP-96-89, NUDOCS 9612240098
Download: ML20132F041 (21)
v • d • e


Text

(*ommonucalth Illiv>n Company

  • Quad Citms Generating Station 22710 206th Avenue North Cordova, 11. 61212 97 in Tei .w> 6s t 22 i i LWP-96-089 l

i December 10, 1996 U.S. Nuclear Regulatory Commission ,

ATTN: Document Control Desk l Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 l 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 November 1996.

Respectfully, .

i Comed Quad-Cities Nuclear Power Station i

il -

f(A%W Li W. Pearce Station Manager ,

LWP/dak Enclosure cc: A. Beach, Regional Administrator C. Miller, Senior Resident Inspector 2300S! I q

STMGRW8996.LWP Th s

iiI 9612240098 961130 PDR ADOCK 05000254 R PDR A Unicom company

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_ QUAD-CITIES NUCLEAR POWER STATION 1

i UNITS 1 AND 2 l

i MONTHLY PERFORMANCE REPORT i

NOVEMBER 1996 1

. COMMONWEALTH EDISON COMPANY i

! AND j MID-AMERICAN ENERGY COMPANY i

t l NRC DOCKET NOS. 50-254 AND 50-265 1

LICENSE NOS. DPR-29 AND DPR-30 i

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. 1 TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two '

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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  ;

i 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 i

VII. Refueling Information 4

VIII.- Glossary 1TrHOP3\NRC\ MONTHLY.RPT

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I. INTRODUCTION j 4

Quad-Cities Nuclear Power Station is composed of two Boiling Water l l

Reactors and Steam Turbine / Generators, each with a Maximum Dependable Capacity  ;

j of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by ,

1 Commonwealth Edison Company and Mid-American Energy Company. The Nuclear l l

Steam Supply Systems are General Electric Company Boiling Water Reactors. The i Architect / Engineer was Sargent & Lundy, Incorporated, and the primary j i

construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license 1

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numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, I I

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 Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively. j ITCHOI'3\NRC\ MONTHLY.RIT 4

l II. SUPMARY OF OPERATING EXPERIENCE l

A. Unit One l

I Quad Cities Unit One started the month of November 1996 reducing power to troubleshoot and repair the 1A Gland Seal Condenser Level Control Valve. Testing was completed and the unit ascended to full power on November 7, 1996.

I B. Unit Two Quad Cities Unit Two was on-line the entire month of November 1996. A l

few load drops were performed for Weekly Turbine Testing, however the average daily power level remained at 80% or greater.

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l III. PLANT OR PI'0CEDURE CHANGES. TESTS. EXPERIMENTS.

AND SAiETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Snecifications l

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

B. Facility or Procedure Chanaes Reauirina NRC Acoroval i i

There were no Facility or Procedure changes requiring NRC approval for i the reporting period.

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

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IV. LICENSEE EVENT REPORTS 4

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.

i j UNIT 1

Licensee Event Report Number Q11g Title of occurrence

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!96-023 11/24/96 "B" Control Room HVAC Inoperable due to Make Up Flow Inaccuracy.

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! UNIT 2 Licensee Event l Report Number Qalg Title of occurrence ~

4 96-003 11/12/96 U2 LPCI Inoperable due to 2D RHR Pump i 1 Discharge Check Valve Failure. l i

i TECHOP3\NRC\ MON 1MLY,RIT

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 1TfHOP3\NRC\ MON 1MLY.RPT

,. . j APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 .

UNTT One DATE December 10, 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 110196

1. REPORTING PERIOD 2400 113096 OROSS HOURS IN REPOR77NG PERIOD 720
2. CURRENTLY AITTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769

% ION ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVELTO WHICH RESTRICTED (IP ANY)(MWe-Net): N/A
4. REASONS POR RESTRICTION (IF ANY):

THIS MONTH YR 70 DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL 720.00 3301.70 163765.20
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90
7. HOURS GENERATOR ON LINE 720.00 3025.70 158784.90
8. UNTT RESERVE SHITTDOWN HOURS 0.00 0.00 909.20
9. OROSS THERMAL ENERGY GENERATED (MWH) 1624770.00 6935335.90 345341133.50
10. GROSS ELECTRICAL ENEROY GENERATED (MWH) 528362.00 2211268.00 111825349.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 506112.00 2109582.00 105583958.00
12. REACTOR SERVICE FACTOR 100.00 41.07 75.83
13. REACTOR AVAILABILTTY FACTOR 100.00 41.07 77.41
14. UNrr SERVICE FACTOR 100.00 37.63 73.52
15. UNrr AVAILABILTTY FACTOR 100.00 37.63 73.94
16. UNTT CAPACTrY FACTOR (Using MDC) 91.41 34.12 63.57
17. UNrr CAPACfrY FACTOR (Using Design MWe) 89.09 33.26 61.%
18. UNTT PORCED OUTAGE RATE 0.00 3.72 7.52
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): N/A
20. IF SHLTTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INITIAL CRfTICALT!Y INfflAL ELECTRICfrY COMMERCIAL OPERATION j

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71rHOP3\NIK.NLY.RPT j l

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2 APPENDIX C OPERATING DATA REPORT I DOCKET NO. 50-265 UNTT Two DATE December 10, 1996 COMPI VTED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS C000 110l%

1. REPORTING PERIOD: 2400 113096 OROSS HOURS IN REPORTING PERIOD: 720

, 2. CURRENTLY AITTHORIZED POWER LEVEL (MWL): 2 fit MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 l

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) NWe-Net): N/A l
4. REASONS FOk RESTRICTION (IF ANY):

l THIS MONTH YR TO DATE ' JMULATIVE

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5. NUMBER OF HOURS REACTOR WAS CRTilCAL 720.00 5772.10 159842.55 l
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80 720.00 5605.80 155505.35 1 HOURS GENERATOR ON llNE
8. UNTI RESERVE SHUTDOWN HOURS 0.00 0.00 702.90  ;

, 9. GROSS THERMAL ENERGY GENERATED (MWH) 1773379.00 13577339.90 337918560.82

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 571483.00 4310784.00 108456319.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 548225.00 4128036.00 102780922.00
12. REACTOR SERVICE FACTOR 100.00 71.79 74.55
13. REACTOR AVAILABILITY FACTOR 100.00 71.79 75.94
14. UNrr SERVICE FACTOR 100.00 69.72 72.53 j
15. UNrr AVAILABILrrY FACTOR 100.00 69.72 72.85
16. UNIT CAPACrrY FACTOR (Using MDC) 99.01 66.77 62.34
17. UNrr CAPACfrY FACTOR (Using Design MWe)  %.50 65.07 60.76
18. UNrr FORCED OLTTAGE RATE 0.00 30.28 11.22
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MOffrHS (TYPE. DATE, AND DURATION OF EACH): 3/1/97
20. IF SHtTFDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:
21. UNrrs IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INITIAL CRITICALITY INrrIAL ELECTRICrrY COMMERCIAL OPERATION

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1.10-9 710tOPMNkC\ MON'DILY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE December 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH November 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 549 17. 784
2. 387 18, 784
3. 377 19. 784
4. 379 20. 784
5. 379 21. 785
6. 378 22. 785
7. 643 23. 779
8. 780 24. 785
9. 765 25. 785
10. 784 26. 785
11. 784 27. 783
12. 783 28. 785
13. 783 29. 785
14. 782 30. 779
15. 783 31.
16. 767 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.

1.16-8 TECHOPS\NRC440N1MLY.Pff

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l APPENDIX B

! AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-265 UNIT Two 1 DATE December 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH November 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 502 17. 763
2. 772 18. 774
3. 702 19. 775
4. 774 20. 774
5. 776 21. 774
6. 777 22. 766
7. 776 23. 757
8. 776 24. 760
9. 774 25, 773
10. 773 26, 772 11, 774 27. 771 12, 775 28. 772
13. 774 29, 772
14. 775 30. 772
15. . 775 31.
16. 776 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.

1.16-8 TICHOP3\NRC\MONDILY.RFT

APPENDIX D UNIT SHUTDOWNS AND PotiER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE December 10. 1996 REPORT MONTH November 1996 TELEPHONE 309-654-2241 m

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k. l E LICENSEE

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O DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 96-05 11/1/96 F 0 A 9 --- ----- -- ---- Repairs to the I A Gland Seal Condenser level Control Valve.

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APPENDIX D i UNIT SHUTDOWNS AND POWER REDUCTIONS

! DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore l DATE December 10, 1996 REPORT MONTH November 1996 TELEPHONE 309-654-2241 l l

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$ LICENSitE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT None for ec month of Novenber.

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TirHOIWRC\ MON 1NLY.RIT

VI. UNIOUE REPORTING RE0VIREMENTS The fn11owing items are included in this report based on prior commitments to l the tennission:

A. Main Steam Relief Valve Operations ,

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

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

l The basis for reporting this data to the Nuclear Regulatory Commission are  !

specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complet9 summary of Units One and Two Control Rod Drive Scram timing for the reporting period. All scram timing as performed with reactor pressure greater than 800 PSIG.

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RESULTS OF SCRAM TIMING MEASUREMENTS

  • PERFORMED ON UNIT 1 E 7 CONTROL - *:

ROD DRIVES, FROM 01/01/96 TO 11/30/96 l AVERAGE TIME IN SECONDS AT % MAX. TIME ,l l INSERTED FROM FULLY WITHDRAWN , FOR 90%

INSERTION DESCRIPTION NUMBER 5 20  ! 50  ! 90 Technical Specification 4.3.D, 4.3.E E DATE  ! OF RODS '

O.375 0.900  ! 2.00  ! 3.5 1 7 sec.  ! 4.3.F (Averace Scram Insertion Timei l l l l l l 1/13/96 29 1 0.339 l 0.708 l 1.459 2.538 l 2.91 l Scram Time Test for Viton Issue U-2 l l l l (K10) i i  ! l  ! l 2/09/96 , 30 l 0.325 l 0.691  ! 1.436 l 2.495  ! 2.71 l Scram Time Test for Viton Issue l l l (M-8) at EOC U1 l l 2/25/96 l 18 0.349 !' 0.722 1.496 l 2.577 3.07 I scram Time Test for viton Issue U-2 ll l , (M-8) l 4/22/96 , 1 0.32 0.69 1.46 l 2.54 2.54 PMTV for Scram Valve Leak on U-2 l

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l i 5/05/96 l 177 0.308 0.713 1.543 , 2.700 3.03  ! Beginning of Cycle for U-1 l l (N-7)  !

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l l 8/16/96 l 177 0.330 ll 0.707 l 1.473 l 2.569 2.85 PMTV for SSPV Maintenace U-2 l 1 I (F-6)

I l 1 9/06/96  ! 12 0.319 0.703 1 1.478 l 2.573 2.79 l PMTV for various Maintenance U-1 l l l (F-6) l  ! ,

9/26/96 l 10 0.358 0.734 l 1.497 l'2.602 i 2.78 STT for Viton Issue U-2 l ,

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11/04/96 1 0.31 0.69 1.46 j 2.54 l 2.54 PMTV for Scram Valve U-1

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11/08/96 l 10 0.36 0.73 , 1.50 2.57 2.68 STT for Viton Issue U-2 l (G-15) ncscawnumu

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RESULTS OF SCRAM TIMING MEASUREMENTS ,

PERFORMED ON UNIT 1 & 2 CONTROL '

ROD DRIVES, FR9M 01/01/96 TO 11/30/96 C l AVERAGE TIME IN SECONDS AT % l MAX. TIME l '

l INSERTED FROM FULLY WITHDRAWN l FOR 90s l

! INSERTION ' DESCRIPTION l NUMBER S  ! 20 1 50  ! 90 Technical Specification 3.3.C.1 &

DATE  ! OF RODS 0.375 ! 0.900  ! 2.00  ! 3.5 '

7 sec. 3.3.C.2 fAveraoe Scram Insertion Time) i l i i I .

11/11/96 1 0.31 0.67 1.40 l 2.42  ! 2.42 1 PMTV for F-15 on U-2

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l 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. i 0'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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3 TTCHOP3\NRC\ MONTHLY.RPT

i Revisten 2 QUAD CITIES REFUELING Octcher 1989 INFORMATION REQUEST

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1. Unit: 01 Reload: 14 Cycle: 15
2. Scheduled date for next refueling shutdown
2/10/98 j 3. Scheduled date for restart following refueling: 4/1/98
4. W111 refueling or resumption of operation thereafter require a Technical l i

Specification change or other license amendment:

/ No l

l S. Scheduled date(s) for submitting proposed licensing action and

,i supporting information:

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! 6. Important Itcensing considerations associated with refueling, e.g., new i

or different fuel design or supplier, unreviewed design or performance i

analysis methods, significant changes in fuel design, new operating procedures: i i

i Approx. 216 SPC 9X9IX Fuel Bundles Q1R15 will be loaded.

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7. The number of fuel assemblies.

i l , a. Number of assemblies in core: 724 i

j. 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 l N planned in number of fuel assemblies:

i a. Licensed storage capacity for spent fuel: 3657 1

l b. Planned increase in licensed storage: 0 i 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1 t APPROVED ,

4 (final) 14/0395t -I- OCT 3 01989 C).C.O.S.R.

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'~l Revision 2 l QUAD CITIES REFUELING Oct:bar 1989

', INFORNATION REQUEST

1. Uni t
Q2 Reload: 13 Cycle: 14
2. Scheduled date for next refueling shutdown: 3/1/97
3. Scheduled date for restart following refueling: 5/23/97
4. Will refueling or resumption of operation thereafter require a Technical
Specification change or other license amendment
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! 5. Scheduled date(s) for submitting proposed licensing action and 1 supporting information: ,

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i 6. Important licensing considerations associated with refueling, e.g., new I or different fuel design or supplier, unreviewed design or performance i analysis methods, significant changes in fuel design, new operating j procedures:

I 216 Siemens 9X91X Power Corporation Fuel Bundles will be loaded j during Q2R14.

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!_ 7. The number of fuel assemblies.

l l , a. Number of assemblies in core: 724 j b. Number of assemblies in spent fuel pool: '

2727

{ 8. The present licensed spent fuel pool storage capacity and the size of j any increase in licensed storage capacity that has been requested or is y planned in number of fuel assemblies:

. a. Licensed storage capacity for spent fuel: 3897 1

, 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 Ilcensed capacity:

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i APPROVED ,

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14/0395t OCT 3 01989 Q.C.O.S.R.

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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 Sy.; tem 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 t 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 1 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 i 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 TTDIOP3\NRC\ MON 1MLY.RPT

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