ML20116M679

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Monthly Operating Repts for Jul 1996 for Quad Cities Nuclear Station Units 1 & 2
ML20116M679
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/31/1996
From: Moore K, Pearce L
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-96-059, LWP-96-59, NUDOCS 9608210005
Download: ML20116M679 (19)
v • d • e


Text

i I Commonwealth 1.diwn Company Quad Cities Generating Station  !

22710 206th Asenue Nonh

, Cordova. II. 6124 2-9740 Tel .WMA 4-22 4 i COlvtEd l I I

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LWP-96-059 l August 9, 1996 U.S. Nuclear Regulatory Commission 1

ATTN: Document Control Desk '

Washington, D.C. 20555 '

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-?54 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, j during the month of July 1996. 1 l

l Respectfully, Comed l Quad- Wies Nuclear Power Station i hd W L. W. Pearce i Station Manager LWP/dak i Enclosure cc: A. Beach, Regional Administrator C. Miller, Senior Resident Inspector h l 4

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3 STMGIh03906.LWP l l 9608210005 960731 4 PDR ADOCK 0500 R

A rnwom n mpany

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT l

JULY 1996 .

1 COMMONWEALTH EDIS0N COMPANY l l

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MID-AMERICAN ENERGY COMPANY l l

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

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TABLE OF CONTENTS l l

i I. Introduction j l

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 i B. Facility or Procedure Changes Requiring NRC Approval i

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

l V. Data Tabulations i A. Operating Data Report l B. Average Daily Unit Power Level' C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements ,

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A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary a

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TECHOP3\NIC&40NTHLY.RM

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1. INTRODUCTION l

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

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 Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240, respectively.

TIEHOP3WRC\ MONTHLY.RFT

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II.

SUMMARY

OF OPERATING EXPERIENCE ,

l A. Unit One  !

j Quad Cities Unit One spent the month of July 1996 shutdown in Refuel  ;

l Outage QlR14.  ;

l B. Unit Two '

Quad Cities Unit Two spent the month of July 1996 shutdown in Forced Outage Q2F41.

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3 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.

i B. Facility or Procedure Chances Reauirina NRC Acoroval There were no Facility or Procedure changes requiring NRC approval for l the reporting period. j 1

C. Tests and Experiments Reauirina NRC Acoroval l l

There were no Tests or Experiments requiring NRC approval for the I reporting period.

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IV. LICENSEE EVENT REPORTS I

l l 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 l the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

l i UNIT 1 l

Licensee Event Report Number Qatt Title of occurrence l

96-011 7/7/96 A postulated fire could have caused t

disabling damage to selected motor operated valves required by 10 CFR 50, l Appendix R, to be operable for safe i shutdown of the plant, due to an l inadequate design analysis review.

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l UNIT 2 Licensee Event Report Number Q11g Title of occurrence There were no licensee event reports for Unit 2 for this reporting period.

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V. DATA TABULATIONS a

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 1

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APPENDIX C i I

OPERATING DATA REPORT l DOCKET NO. 50-254 UNTT One DATE August 9,1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPFJtATING STATUS 0000 070196

1. REPORTING PERIOD: 2400 073196 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789  ;

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3. POWER LEVELTO 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 0.00  % 4.10 161427.60 !

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6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90 1
7. HOURS GENERATOR ON LINE 0.00  % 3.20 156722.40
8. UNrr RESERVE SHITTDOWN HOURS 0.00 0.00 909.20
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 2288399.50 340694197.10
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 7343 6.00 110348477.00 i
11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 699244.00 104173620.00
12. REACTOR SERVICE FACTOR 0.00 18.86 75.77 )

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13. REACTOR AVAILABILTTY FACTOR 0.00 18.86 77.38
14. UNTT SERVICE FACTOR 0.00 18.85 75.56
15. UNrr AVAILABILTTY FACTOR 0.00 18.85 73.99
16. UNrr CAPACfrY FACTOR (Using MDC) 0.00 17.79 63.59
17. UNrr CAPACfrY FACTOR (Using Design MWe) 0.00 17.34 61.97
18. UNTT FORCED OLTTAGE RATE 0.00 0.00 7.54
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH): Refuel 2/10/96
20. IF SHITTDOWN AT END OF REPORT PE3tlOD< ESTIMATED DATE OF STARTUP: 8/19/96
21. UNrrs IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INrrlAL CRrrlCALTTY INTTIAL ELECTRICITY j COMMERCIAL OPERATION a 1.16-9 TECHOP3WICJWONTHl.Y.RFr

APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNrr Two DATE August 9,1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 070196

1. REPORTING PER]OD: 2400 073196 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTIIORIZED POWER LEVEL (MWt): 2511 MAX > DF. PEND > CAPACfrY: 769 DESIGN ELECTRICAL 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 CRrrlCAL 0.00 3133.90 157204.35
6. REACTOR RESERVE SHITTDOWN HOURS 0.00 0.00 2985.80
7. HOURS GENERATOR ON LINE 0.00 3125.00 153024.55
8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 7688143.90 332029364.82
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 2465748.00 106611283.00
11. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 2369169.00 101022055.00
12. REACTOR SERVICE FACTOR 100 61.32 74.33
13. REACTOR AVAILABILITY FACTOR O.00 61.32 75.75
14. UNTT SERVICE FACTOR 0.00 61.14 72.36
15. UNrr AVAILABILrrY FACTOR 0.00 61.14 72.69
16. UNrr CAPAcrTY FACTOR (Using MDC) 0.00 60.28 62.12
17. UNTT CAPACrrY FACTOR (Using Design MWe) 0.00 58.75 60.54
18. UNrr FORCED OUTAGE RATE 100.00 38.86 11.15
19. SHITTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE DATE. AND DURATION OF EACH): N/A
20. IF SHITTDOV X AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: Q2F41 - Start Up 8/12/96
21. UNrrS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A l FORECAST ACHIEVED INrrIAL CRrflCALrrY j INrr1AL ELECTRICrrY l COMMERCIAL OPERATION 1.16-9 TECHOP3mmPrDILY.RFr

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One  !

DATE Auaust 9. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH July 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -9 17. -9
2. -8 18. . . . . ,

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3. -8 19. .-9
4. -8 20. -9  !

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5. -8 21. -9 l
6. -8 22. -9
7. -8 23. -9
8. -8 24. -9
9. -8 25. -9
10. -7 26. -10
11. -8 27. -10
12. -8 28. -10 1
13. -8 29. -10
14. -9 30. -9 l

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l 16. -9 INSTRUCTIONS

On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Corapute 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 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265

, UNIT Two

! DATE Auaust 9. 1996 l COMPLETED BY Kristal Moore

! TELEPHONE (309) 654-2241 MONTH Julv 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. -9
2. -7 18. -9 l t j 3. -8 19. -9 '

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5. -8 21. -9
6. -8 22. -9
7. -8 23. -8 7 1

! 8. -8 24. -9 i

9. -8 25. -9 ,
10. -8 26. -9
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11. -8 27. -9
12. -8 28. -9
13. -8 29. -9
14. -8 30. -9
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15. -9 31. -9 j
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! INSTRUCTIONS -

On this form, list the average daily unit power level in MWe-Net for each day  !

j 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  ;

i dependable capacity.is used for the net electrical rating of the unit, there  :

4 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 '

TECHOP3WRCtMONTHLY.RTT I

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. APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Moore DATE Auoust 9, 1996 REPORT MONTH July 1996 TELEPHONE 309-654-2241 ,

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$ :M LICENSEE DURATION EVENT I NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 96-02 07/01/96 S 744.0 C 4 - -- -- -- ---- Continuation of Q1R14 Refuel Outage.

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. APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Moore DATE Auoust 9, 1996 REPORT MONTH July, 1996 TELEPHONE 309-654-2241 1

M OE x U M b MM M M Am O 4 Ho E C lE l3 8 2o8 he m $

$ LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT E05 7-01-M F 744.0 H 2 --------- -- ---- Contantion of Force Outage Q2F41, i

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i VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

A. Main Steam Relief Valve Operations P

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

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

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VII. REFUELING INFORMATION' 1

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 QUAD CITIES REFUEL.ING October 1989 INFORMATION REQUEST

1. Unit: 01 Reload: 14 _

Cycle: 15-

2. Scheduled date for next refueling shutdown: 2/10/96
3. Scheduled date for restart following refueling: 8/19/96
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 Information: ,
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:

232 GE10 Fuel Bundles were loaded during Q1R14.

7. The number of fuel assemblies.

724

a. Number of assemblies in core:
b. Number of assemblies in spent fuel pool: 1933
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 l N planned in number of fuel assemblies:

Licensed storage capacity for spent fuel: 3657 a.

Planned increase in licensed storage: 0 b.

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present Ilcensed capacity:

APPROVED ,,

14/0395t (final)

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QTP 300-S32 Revision 2 1

l . QUAD CITIES REFUELING October 1989

! INFORMATION REQUEST 1 i

1. Unit: Q2 Reload: 13 _ Cycle: 14 l l \

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2. Scheduled date for next refueling shutdown: 2/01/97 '
3. Scheduled date for restart following refueling: 4/23/97 4
4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

I YES

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

l l August 1996 I 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance l analysis methods, significant changes in fuel design, new operating i procedures:

Approx. 216 Siemens 9X91X Power Corporation Fuel Bundles will be loaded during Q2R14.  !

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7. The numb 6r of fuel assemblies.
a. Number of assemblies in core: 724 l
b. Number of assemblies in spent fuel pool: 7777
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:

l 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 i spent fuel povi assuming the present licensed capacity:

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i, APPROVED ,

(final)

OCT 3 01989 4 14/0395t O.C.O.S.R.

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The following abbreviations which may have been used in the Monthly Report, j - are defined below

ACAD/ CAM - Atmospheric Containment-Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute l APRM - Average Power Range Monitor L ATWS - Anticipated Transient Without Scram l BWR - Boiling Water Reactor l CR0 - Control Rod Drive L EHC - Electro-Hydraulic Control System

! E0F - Emergency Operations Facility l GSEP - Generating Stations Emergency Plan ,

HEPA - High-Efficiency Particulate Filter  !

l 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 j LER Licensee Event Report j

- Local Lean Rate Test LLRT-

-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 l SDC - Shutdown Cooling Mode of RHRS
SDV - Scram Discharge Volume i SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System i TIP - Traversing Incore Probe i TSC - Technical Support Center i

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