ML20112J027

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Monthly Operating Rept for May 1996 for Quad Cities Nuclear Station Units 1 & 2
ML20112J027
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 05/31/1996
From: Moore K, Pearce L
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-96-045, LWP-96-45, NUDOCS 9606190135
Download: ML20112J027 (20)
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  • COffif1)OnH raltll I.dNift Cont llany Quad Citics Generating Station

. 227,10 206tli Asenue Nortti Cordova, li. 612 42-9740 Tei .w><,s w2 ii LWP-96-045 June 10, 1996 U.S. Nuclear Regulatory Commission ATTH: 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 l l

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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 May 1996.

Also, please find attached the revised Section 3 Part A on Amendments to facility License or Technical Specifications for the month of April,1996.

Respectfully, Comed Quad-Cities Nuclear Power Station

b. b. &od p L. W. Pearce Station Manager LWP/dak Enclosure >

cc: H. Miller, Regional Administrator C. Miller, Senior. Resident Inspector l

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QUAD-CITIES NUCLEAR POWER STATION f

f UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT May 1996 COMMONWEALTH EDISON COMPANY i

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MID-AMERICAN ENERGY COMPANY

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE N05. DPR-29 AND DPR-30 P

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TABLE OF CONTENTS ,.

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4 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 Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval IV. Licensee Event Reports l V.- Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level

} C. Unit Shutdowns and Power Reductions i VI. Unique-Reporting Requirements A. Main Steam Relief Valve Operations l i B. Control Rod Drive Scram Timing Data VII. Refueling Information b VIII. Glossary i

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t I. INTRODUCTION 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 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 4

number 309-654-2241, extensions 3070 and 2240, respectively.

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II.

SUMMARY

OF OPERATING EXPERIENCE I I

A. Unit One

. Quad Cities Unit One spent the month of May 1996 shutdown in Refuel Outage Q1R14.

B. Unit Two Quad Cities Unit Two began the month of May 1996 on line. On May 10, 1996 high winds suspected to have been caused by a tornado affected Secondary Containment. As a result, Unit 2 shutdown commenced. On May 10, 1996 the generator was removed from the grid at 1431 hours0.0166 days <br />0.398 hours <br />0.00237 weeks <br />5.444955e-4 months <br /> and a manual reactor scram was inserted at 1451 hours0.0168 days <br />0.403 hours <br />0.0024 weeks <br />5.521055e-4 months <br />.

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

AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications RFVISED Technical Specification Amendment No. 170 was issued on April 2, 1996 to Facility Operating License DPR-29 and Amendment No. 166 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments contained issuance of amendments related to TSUP Section 6.0.

B. Facility or Procedure Chanaes Reauirina NRC Acoroval ,

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

C. Tests and Experiments Reauirina NRC Acoroval ,

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

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. . 1 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 as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report Number Q11g Title of occurrence 96-007 5/10/96 A tornado damaged secondary containment at Quad Cities which required a shutdown of Unit 2.96-009 5/23/96 Discrepancies in the cable lengths used in the degraded voltage calculations. .

UNIT 2 l Licensee Event Report Number Q11g Title of occurrence 96-001 5/24/96 HPCI placed in a configuration that was outside UFSAR design requirements.

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, V. DATA TABULATIONS  ;

i The following data tabulations are presented in this report: l A. Operating Data Report B. Average Daily Unit Power Level r c

l C. Unit Shutdowns and Power Reductions 4

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' APPENDIX C [

OPERATING DATA REPORT i 50-254 i DOCKET NO.

UNIT One 7 DATE June 10.1996 -

COMPLETED BY Krissel Moore ,

L TELEPHONE (309) 654-2241 OPERATING STATUS f 0000 050io6

1. REPORTING PERIOD: 2400 053196 GROSS HOURS IN REPORTING PERIOD: 744 j i
2. CURRENTLY AlfrHORIZED POWER LEVEL (MWO: 2511 MAX > DEPEND > CAPACITY: 769  !

DESIGN ELECTRICAL RATING (MWe-NET): 789 t

3. POWER LEVELTO WHICH RESTIUCTED(IF ANY)(MWe-Ne0: N/A
4. REASONS FOR RES'IltlCTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE ,

5. NUMBER OF HOURS REACTOR WAS CRTTICAL 0.00 964.10 161427.60
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90 {
7. HOURS GENERATOR ON LINE 0.00 963.20 156722A0 0.00 0.00 909.20 l
8. UNrr RESERVE SHtfrDOWN HOURS I'
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.00 2288399.50 340694197.10
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 0.00 734396.00 110348477.00 i i

i1. NET ELECTIUCAL ENERGY GENERATED (MWH) 0.00 699244.00 104173620.00 I I

12. REACTOR SERVICE FACTOR 0.00 26.44 76.30 77.91  !
13. REACTOR AVAILABILTTY FACTOR 0.00 26.44 l
14. UNrr SERVICE FACTOR 0.00 26.41 74.07  ;

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15. UNrr AVAILABILTTY FACTOR 0.00 26.41 74.50  ;
16. UNrr CAPACITY FACTOR (Using MDC) 0.00 24.93 64.03 l J
17. UNIT CAPACITY FACTOR (Using Design MWe) 0.00 24.30 62.40
18. UNIT FORCED OLTTAGE RATE 0.00 0.00 7.54
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH): Refbel 2/10/96
20. IF SHUTDOWN AT END OF REPORT PEIUOD< ESTIMATED DATE OF STARTUP: 6/13/96
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INTTIAL CRITICALTTY INrrtAL ELEC110CfrY COMMERCIAL OPERATION 1,la-9 TliCHOPS\NRC940NTHLY.RFr

l APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-265 UNrr Two DATE Juns10,1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 OPERATING STATUS 0000 0501%

1. REPORTING PERIOD: 2400 0531% GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AtrTHORIZED POWER LEVEL (MW): 2511 MAX > DEPEND > CAPACrrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVELTO WHICH RESTRICTED OF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICTION OF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRrrlCAL 230.90 3133.90 157204.35
6. REACTOR RESERVE SHirrDOWN HOURS 0.00 0.00 2985.80
7. HOURS GENERATOR ON LINE 230.50 3125.00 153024.55
8. UNrr RESERVE SHUTDOWN HOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 562627.80 7688143.90 332029364.82 l
10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 180536.00 2465748.00 106611283.00 i1. NET ELECTRICAL ENERGY GENERATED (MWH) IWO45.00 2369169.00 101022055.00

, 12. REACTOR SERVICE FACTOR 31.03 85.93 74.85  ;

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13. REACTOR AVA!LABILrrY FAcrOR 31.03 85.93 76.27 l l

!4. UNIT SERVICE FACTOR 30.98 85.69 72.86

15. UNrr AVAILABILrrY FACTOR 30.98 85.69 73.20 l
16. UNrr CAPACfrY FACTOR (Using MDC) 29.55 84.48 62.55
17. UNrr CAPACITY FACTOR (Using Design MWe) 28.80 82.33 60.97
18. UNIT FORCED OtfrAGE RATE 69.02 14.31 10.39
19. SHVfDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. AND DURATION OF EACH): N/A
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP: N/A
21. UNrr$ IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A

, FORECAST ACHIEVED INrrlAL CRrrlCALrrY INrflAL ELECTRICfrY COMMERCIAL OPERATION 1.1u-9 1TfHOPMNRC\MONDILY.RPT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE June 10. 1996 COMPLETED BY Kristal Moore TELEPHONE (309) 654-2241 MONTH May 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. -7
2. -8 18. -8
3. -8 19. -7
4. -8 20. -7
5. -8 21. -8 _
6. -8 22. -7
7. -8 23. -9
8. -8 24. -9
9. -8 25. -9
10. -9 26. -9  !

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11. -8 27. -9
12. . -8 28. -9 l
13. -6 29. -9 l
14. -6 30. -8
15. -7 31. -9
16. -7 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 4 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 i 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 June 10. 1996 I COMPLETED 8Y Kristal Moore TELEPHONE (309) 654-2241 MONTH May 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 4

(MWe-Net) (MWe-Net)

l. 774 17. -7 ,
2. 771 18. -8 ,

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3. 772 19. -7
4. 772 20. -8
5. 742 21. -7 ,
6. 773 22. -8
7. 772 23. -8
8. 770 24. -9 I
9. 770 25. -8 [
10. 291 26. -8 i
11. -8 27. -8 i 12. -8 28. -8
13. -6 29. -8
14. -6 30. -8
15. -6 31. -8
16. -7 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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,a APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS l 1

l DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Kristal Moore-DATE June 10, 1996 R3 PORT MONTH May 1996 TELEPHONE 309-654-2241 l

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LICENSEE O DURATION EVENT NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 9642 05/01/96 S 744.0 C 4 ------- --- ---- Corninuation of Q1Rld Refuel Outage.

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j APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS l I

DOCKET NO. 50-265 UNIT NAME- Two COMPLETED BY Kristal Moore

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. DATE June 10. 1996 REPORT MONTH May. 1996 TELEPHONE 309-654-2241 l 1

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EM LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 4 05 5 10- % F 513.5 H 2 -- .. - --- ---- Unit 2 was brought oftune due to Tornado l damage.

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. I VI. UNIOUE REPORTING REOUIREMENTS l

l 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 Steam Relief Valve Operations for the reporting period.

B. Control Rod Drive Scram Timino Data for Units One and Two 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 complete 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 6 2 CONTROL ROD DRIVES, FROM 01/01/96 TO 05/31/96 l l AVERAGE TIME IN SECONDS AT % l MAX. TIME l *

.l l- INSERTED FROM FULLY WITHDRAWN -l FOR 90% l

!  ! INSERTION ! DESCRIPTION NUMBER- l 5 ! 20  ! SO 90  !  !- Technical Specification 3.3.C.1 E DATE l OF RODS  ! O.375 ! O.900  ! 2.00 3.5  ! 7 sec.  ! 3.3.C.2 (Averaae Scram Insertion Time) i 1 . l i j i i 1/13/96 1 29- -l 0.339 l 0.708 l 1.459 l 2.538 2.91 l Scram Time Test for Viton Issue l l l l l (K10) l

!  ! I I  !  ! 1 2/09/96_- l 30 l 0.325 l 0.691 1 1.436 l 2.495 l 2.71 l Scram Time Test:for.Viton issue l l 1 l (M-8) l at EOC U1 1 I l l 1-2/25/96 l 18 l 0.349 l 0.722 l 1.496 l 2.577 l- 3.07 l Scram Time Test for viton Issue U-2 l  ! l l l (M-8) l

!  ! l l l t 4/22/96 l 1 0.32 ! O.69 l 1.46 l 2.54 8 2.54 l PMTV for Scram Valve Leak on U-2 l l l l t (K-5)

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

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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 e1 f* Revision 2 October 1989

- . QUAD CITIES REFUELING INFORMATION REQUEST l

Reload: 14 Cycle: n

1. Unit: 01 2/10/96

! 2. Scheduled date for next refueling shutdown:

J 6/13/96 i 3. Scheduled date for restart following refueling:

l - 4. Will refueling or resumption of operation thereafter require a Technical >

j Specification change or other license amendment:

i NO

> 5. Scheduled date(s) for submitting proposed licensing action and

supporting information

,! 6-1-96 submitted 1

6. Important licensing considerations associated with refueling, e.g., new 3

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

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

232 GE10 Fuel Bundles will be loaded during Q1R14.

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7. The number of fuel assemblies.

724

a. Number of assemblies in core:

1933

! b. Number of assemblies in spent fuel pool:

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:

3657

a. Licensed storage capacity for spent fuel:

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

il APPROVED i

( f ' "* D OCT 3 01989 14/0395t O.C.O.S.R.

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Revision 2 QUAD CITIES REFUELING october 1989

' * . INFORMATION REQUEST

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Reload: 13 Cycle:

1. ' Unit: 02 s

i Scheduled date for next, refueling shutdown: 2/01/97 i 2.

Scheduled date for restart following refueling: 4/23/97 3.

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4. Will refueling or resumption of operation thereafter require a Technical -

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Specification change or other license amendment:

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

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August 1996 6.. Important licensing considerations associated with refuef f ag, e.g., new l

or dffferent fuel design or supplier, unreviewed design or performance analysis methods, significant enanges in fuel design, new operating i

procedures:

l Approx. 224 siemens 919II Power Corporation Fuel Bundles will be loaded .during Q2114. ,

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724 i . a. Number of assemblies in core:

2727

. b. Number of assemblies in spent fuel pool:

8. The present Ilconsed spent fuel pool storage capacity and the size of any increase in Itcensed storage capactty that has been requestad or is 1 planned in number of fuel assemblies:

i 3897

a. Licensed storage capacity for spent fuel: -

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b. Planned increase in licensed storage: _

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9. The projected date of the last refueling that can be discharged to the ,

spent fuel pool assuming the present itcensed capactty:

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l APPROVED l . (final > DCT 3 0989

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[; VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report,

-are defined below:

j ACAD/ CAM - Atmospheric Containment Atmospheric 4

Dilution / Containment Atmospheric Monitoring i ANSI - American National Standards Institute 1 APRM - Average Power Range Monitor.

ATWS - Anticipated Transient Without Scram 4

BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System 4

l EOF - Emergency Operations Facility GSEP - Generating Stations Emergency Plan

i. 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 j ISI - Inservice Inspection LER - Licensee Event Report ,

LLRT - Local Leak Rate Test 4 LPCI - Low Pressure Coolant Injection Mode of RHRs  !

LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate t

MCPR - Minimum Critical Power Ratio 2' MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concentration

, MSIV - Main Steam Isolation Valve i

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 i j RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System j RWM - Rod Worth Minimizer i SBGTS - Standby Gas Treatment System l SBLC - Standby Liquid Control

. SDC - Shutdown Cooling Mode of RHRS SDV --Scram Discharge Volume SRM - Source Range Monitor

- Turbine Building Closed Cooling Water System TBCCW TIP - Traversing Incore Probe

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TSC - Technical Support Center t

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