ML20210K523

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Monthly Operating Repts for Jul 1997 for Quad Cities Nuclear Station,Units 1 & 2
ML20210K523
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/31/1997
From: Pearce L, Sirles K
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LWP-97-082, LWP-97-82, NUDOCS 9708190286
Download: ML20210K523 (20)
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Text

V t kimmonw ralth Illiwn Osmguny Quad riors Gent rating Station 22710 Jtx>th Asenuc North Ginlos a.11. 612 i2 97 60 1ti w>ost 22 si LWP-97-082 August 8, 1997 i

U.S. Nuclear Regulatory Commission 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 Eaclosed 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 July, 1997.

Respectfully, Comed Quad-Cities Nuclear Power Station h%

L. W. Pearce Station Manager LWP/dak Enclosure [ /

cc: A. Beach, Regional Administrator C. Miller, Senior Resident Inspector STMORW8297.1.%T 9708190286 970731 l!!E ,ll1,lilll!il'll*'.Illllllllll.li PDR ADOCK 05000254 R PDR ,

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.,~ 4 4 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY 1997 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 DCHOP3\NRC\MONTNLY.RFT

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TABLE OF CONTENTS

1. . 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 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 s

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I. INTRODUCTION l

l l 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 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. lhe 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.

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SUMMARY

OF OPERATING EXPERIENCE A. Unit One Quad Cities Unit One was on-line the entire month of July 1997. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on July 1, 1997, a load drop was performed to everse Condenser flow. A few load drops were performed throughout the day to clear and reset Condenser Vacuum Low Alarms and reverse Condenser flow due to the high river water temperatures. Several other load drops were performed due to Weekly Turbine Testing, high river water temperatures and at the request of Bulk Power Operations, llowever the average daily power level _ remained at 80% or_ greater.

B. Unit Tu-Quad Cities Unit Two was on-line the entire month of July 1997. On July 15, 1997 at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />, a load reduction was initiated in preparation for Fuel Assembly Testing due to increased Off-Gas activities. Test results from Reactor and off-gas sampics verified fuel failure. The SJAE monitors indicate that the defect developed on July 13,1997 at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />. The one-cycle old GE bundle has been located and is being suppressed. On July 20, 1997-at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> a load drop was performed for Control Rod Shuffles and Weekly Turbine Test.

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.' 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.

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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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 100FR50.73.

UNIT 1 Licensee Event Report Mu-her ga.it Title of occurrence 97 017 6/23/97- Unit 1 entered a 12 Hour Hot Shutdown Limiting Condition for Operation Contrary to the Bases for Technical Specification 3.0.A due to Cognitive Personnel Errors when Scheduling Surveillances.97-018 7/21/97 Missed Tech Spec Surveillance TIP Squib Valve Continuity 4.7.0.5.a UNIT 2 Licensee Event Report Number QAlg Title of occurrence 97-006 7/29/97 Cable relied upon for Safe Shutdown is located in fire area which requires use of cable.97-008 6/29/97 Five Control Rod Drives Did Not Receive Required Scram insertion Time Testing Prior To 40% Power Due To An Operations Programmatic Deficiency.97-009 7/14/97 Control Room personnel misread an indication delaying discovery of abnormal Offgas radiation readings which interfered with proper completion of a Technical Specification surveillance due to a cognitive personnel error.

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

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4 V.. DATA TABULATIONji

-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 ThrHOPMNit(hMON1NLY.RFI m.

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APPENDIX C OPERATING DATA REPORT l DOCKLTNO. 50-254 UNTT One DATE August 8.1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 OPERATING WATUS 0000 070197

1. REPORTING PERIOD: 2400 ' 073197OROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY ALTTHORIZED POWER LEVEL (MWth 2511 MAX) DEPEND > CAPACTTY 769 DESIGN ELECmlCAL RATING (MWe-NET): 789
3. POWER LEVEL TO WHICH RESTRICTED OF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):

THl3 MONTH Yk TO DATE CUMULATIVE

5. NUMRER OF HOURS REACTOR WAS CRTTICAL 744.00 4468.10 168977.30
6. REACTOR RESERVE SHtTTDOWN HOURS 0.00 0.00 3421.90

. 7. HOURS DENERATOR ON LINE 744.00 4379.50 163908.40

8. UNIT RESERVE SHtTTDOWN HOURS 0.00 0.00 909.20
9. OROSS THERMAL ENEROY GESERATED (MWH) 1799232.00 10282758.00 357455640.50
10. OROSS ELECTRICAL ENEROY GENERATED (MWH) 563400.00 3291976.00 115713406.00
11. NET ELECTRICAL ENEROY OCHERATED (MWit) 536678.00 31%$91.00 109299560.00
12. REACTOR SERVICE FACTOR 100.00 87.83 76.18
13. REACTOR AVAILABILTTY FAJ',OR 100.00 87.83 77.73
14. UNTT SERVICE FACTOR 100.00 86.09 73.90
15. UNIT AVAILARILTTY FACTOR 100.00 86.09 74.31
16. UNIT CAPACTTY FACTOR (Using MDC) 93.80 80.39 64.08
17. UNTT CAPACTTY FACTOR (Using Design MWe) 91A2 78.35 62.46
18. UNTT PORCED OLTTAGE RATE 0.00 13.91 7.67
19. SHtTTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH): N/A
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTNATED DATE OF STARTUP: N/A
21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST AClllEVED INTTIAL CRTTICALTTY INTTIAL ELECmlCTTY COMMERCIAL OPERATION l.1 r9

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  • APPENDIX C OPERATING DATA REPORT DOCKET NO. 50 265 UNIT Two DATE August S.1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 OPFJtATINO STATUS 0000 070197
1. REPORTING PERIOD: 2400 073197 OROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY Al/THORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND) CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789
3. POWER LEVELTO WHICH PESTRICTED (IF ANY)(MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMRER OF HOURS REACTOR WAS CRITICAL 744.00 2395.80 162982.35
6. REACTOR RESERVE SHUTDOWN HOURS 0 110 0.00 2945.80
7. HOURS OENERATOR ON LINE 744.00 2338.60 158587.95
8. UNIT RESERVE SHtTTDOWN HOURS 0.00 0.00 702.90
9. OROSS THERMAL ENEROY OENERATED (M Vil) 1753272.00 $479746.60 345151835.42 QO. OROSS ELECIRlCAL ENEROY OENERATED (MWH) 550644.00 1735410 00 l10752547.00
11. NIrr ELECTRICAL ENEp 1Y OENERATED (MWH) 527521.00 1661179.00 104980900.00
12. REACTOR SERVICE FACTOR 100.00 47.10 74.00
13. REACTOR AVAILABILrrY FACIVR 100.00 47.10 75.36
14. UNTT SERVICE FACTOR 100.00 45.97 72.01
15. UNrr AVAILABILTTY FACTOR 100.00 45.97 72.33
16. UNIT CAPACTTY FACTOR (Using MDC) 92.20 42.46 61.98
17. UNIT CAPACrrY FACTOR (Using Design MWe) 89.86 41.39 60.41
18. UNrr FORCED OtTTAGE RATE 0.00 0.49 11.03
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MOKrilS (TYPE. DATE. AND DURATION OF EACH): Q2iUI 10/4N7 1 10/24/97
20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP: N/A
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): N/A FORECAST ACHIEVED INITIAL CRrrlCALITY INrrlAL ELECTRICrrY COMMERCIAL OPERATION 1.1 +9 TFrHOP3\NitC\ MONTHLY.RFr

6 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-254 UNIT One DATE Auaust 6, 1997 COMPLETED BY Eristal Sirles TELEPHONE (309) 654-2241 MONTH July 1997 __

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 631 17, 718
2. 659 18. 709
3. 727 19. 695 4, 734 20. 686
5. 699 21. 707
6. 710 22, 745
7. 749 23. 752
8. 749 24. 747
9. 747 25. 735 10, 716 26. 721
11. 741 27. 677
12. 744 28, 695
13. 751 29, 699
14. . 748 30, 748 15, 740 31. 738 16, 730 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 morth. 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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4 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Two DATE Auoust 8. 1997 COMPLETED BY Kristal Sirles TELEPHONE (309) 654-2241 MONTH July 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net)

1. 741 17, 568
2. 739 18, 729
3. 750 19, 699
4. 700 20. 451 5, 758 21. 663
6. 712 22. 725
7. 759 23. 702
8. 760 24, 757
9. 762 25. 749 10, 762 26, 737
11. 757 _ 27. 669
12. 757 28. 744
13. 731 29, 732
14. 742 30. 754 _
15. 651 31. 755 16, 450 INSTRUCTIONS On this form, list the average dail.y 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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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. }p,-254 UNIT NAME One COMPLETED BY Kristal Sir 133_

DATE Auoust 8. 1997 .

REPORT MONTH July 1997 TELEPHONE 309-654-2241 so OE W W H H E LICENSEE DURATION EVENT

-NO. DATE (HOURS) REPORT CORRECTIVE ACTIONS / COMMENTS 97 10 71-97 s 0 H 5 .. +.... ... -.. Imd Drop to Reverne condennet ilow O

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Kristal Sirles DATE Auaust 8. 1997 REPORT MONTH Juiv 1997 TELEPHONE 309-654-2241 M OE b 2 hu n8 se E*a he m $

LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 9745 7/15/97 P 0 A 5 .......... ... .... Initiated lead Dny in preparation for Fuel Annend>ly Testing.

97 06 7/20/97 5 0 8 5 ......... ... .... Load Dny for control Rod Shufne and Turt>ine Testing.

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. ,- VI. UNIOVE REPORTING REQUIREMENTS 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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_ . - . _ . . _ - _ _ - - . . _ _ _ _ _ _ ._.._-___._._m -_ _ _ _ _ _ _ _ _ _ . _.m.

h RESULTS OF SCRAM TIMING MEASUREMENTS ~

PERFORMED ON UNIT 1 & 2 CONTROL * - i ROD DRIVES, FROM 01/01/97 TO 06/30/97 [

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.l i l AVERAGE TIME IN SECONDS AT % l MAX. TIME l i l  ! INSERTED FROM FULLY WITHDRAWN l FOR 90% .

!-  !  ! INSERTION ! DESCRIPTION

,l NUMBER j 5  ! 20  ! 50  ! 90  ! j Technical Specification 3.3.C.1.& I DATE '! OF RODS  ! 0.375 ! 0.900  ! 2.00  ! 3.5  ! 7 sec. ! 3.3.C.2 (Averaae Scram Insertion Time) i 3>, -

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~2/17/97 l 14 l 0.314 ! 0.712  ! 1.528  ! 2.671 l 3.010 l STT for Viton Issue U-1 (Core Wid Ave. Times) 3 l l l l '!- l (J-14) l l  !  !  !  !  !  ! .

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3/29-31/97 l 21  ! 0.316 l 0.708 j 1.513 'l 2.645 .l 3.010 l STT for Tech. Spec (19) (Core Wide Ave. Times)- i j j j i l l (J-14) l PMTV (2)  !

: l l 4/25/97 l 1- l'O.29  ! O.64 j 1.37-  ! 2.4 1 3.010  ! Post Maintenance Test for Accumulator Replacanent ;
j. j j j  ! l (J-14) j Unit 1 I

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! 5/31/97 l 14 j 0.354 ! O.725 l 1.497 l 2.576 j 2.77  ! STT for viton Issue - U1 i 1 i  : i l- (c-15)  ;  ;

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l 6/23/97  ! 13 l 0.297 l 0.681 .! 1.478 . 1! 2.615 l 2.95  ! Post Outage Scram Test Timing and PMTV U2

. l  ! l l l l (M-12) l  !

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i-6/29/97 l 4 l 0.278 l 0.630 l 1.348- ! 2.350 -l 2.46  ! Post Outage Scram Testing and PMTV - U2 [

i  !  !  !  ! l l (P-6) l 4

l l l  !  !  ! i 7/16/97 l 1 l 0.280 l 0.630  ! 1.324' l 2.306 l 2.306 l PMTV - U2 l l l l l l l (N-6) l l t

!  !  ! l l  ! I j 7/20/97 32  ! 0.312 : 0.701 1.497  ! 2.617 l 2.67 j TS & SSPV Testing U-1 {

!  !  ! I i i  ! (c-15) :  ;

!  !  !  !  !  !  ! l 1 l l l 1  :  !

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NRCISCRMTIME. FILM >

t 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 0300-S32 Revision 3 April 1997 QUAD CITIES REfVELING 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 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:

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:

Approx. 216 SPC 9X91X 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 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) l

QTP 0300-S32 Revision'3

April 1997 QUAD CITIES REFUELING INFORMATION REQUEST
1. L' nit: 02 Reload: 14 Cycle: 15 2.- Scheduled date for next' refueling shutdown: 2/20/99 #
3. Scheduled date for restart following _ refueling: 3/27/99
4. - Will refueling or resumption of operation thereafter require a Technical 4 Specification change or other license amendment: ,

Yes

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

August, 1998

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, n:w operating procedures:

L N/A 7.: 1he number of fuel assemblies,

a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool:- 2943 ,

8.- 'The present licensed spent fuel pool storaga 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: _

0 9.. The projected date of the last refe'. ling that can be discharaed to the spent fuel poc assuming the present $1 censed capacity: 2002

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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 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 cf 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 PCIONR - Preconditior.ing 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 P.PS - Reactor Protection System RWM - Rod Worth Minimizer SBGTS - Standby Gas Treatment System d 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 TECHOP3\NRCWON1MLY.RPT

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