ML20086L644

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Monthly Operating Repts for Nov 1991 for Quad Cities Nuclear Station,Units 1 & 2
ML20086L644
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 11/30/1991
From: Losekshort C
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20086L639 List:
References
NUDOCS 9112170023
Download: ML20086L644 (16)
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I QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1991 ,

COMMONHEALTH EDISON COMPANY AND IOHA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE N05 DPR-29 AND DPR-30 9112170023 911202 PDR ADOCK 05000254 R PDR TS 14

4 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 Re!ated Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experin:ents Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. l.icensee 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

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I. IN1RODUCIl0N Quad-Cities Nuclear Power Station is composed of two Bolling Hater Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinols. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Bolling Hater 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 Octo .r 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 Cynthia A. Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240.

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f II. SUMnRLOLDEEBAUNG_EXEGIENCE A. Molt _0nc Unit One began the month of November operating at full pcwer, On November 8th the unit dropped load to perform the Turbine Weekly Surveillance. The unit was scrammed at 0121 hours0.0014 days <br />0.0336 hours <br />2.000661e-4 weeks <br />4.60405e-5 months <br /> on November 22nd and at 2153 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.192165e-4 months <br /> on the 29th for Electromatic Relief Valve work and 250V battery work respectively. After the ERV work was accomplished the unit went critical at 2134 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.11987e-4 months <br /> on November 23rd, and the un*t remained shutdown into December for the 250V battery work.

B. UntLIxo Unit Two also began the month of November operating at full power. The unit remained operational for the entire month with no shutdowns or significant load drops occurring.

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III. El ANT OR PROCERURE CHANGES. TESTSJXEERIMDLTL ANILSAEElY__RELAIED MAINLEh6hCE l l

.A. Amendments to Facility Licent.e or_Terhnical SagtL[ications There were no Amendments to the Facility License or Technical  ;

Specifications for the reporting period. 4 B. Facility or Prongdure Changes Recutrina NRC AngrayAl-1 There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and_ Experiments Requiring NRC Aoproval There'were no Tests or Experiments requiring NRC approval for the reporting period.

D. Catttttiy_e Maintenance of_itfety Related Equipment The following' represents a tabular summary of the major safety related mainti, nance performed on Units One and Two during the reporting-period. This summary includes the following: Hork Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe. Operation, and Action Taken to Prevent Repetition.

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UNIT 2 MAINTENANCE SUMMAM1 SYSTEM EID DESCRIPTION HORK PERFORMED HORK RFOUESI .

2402 Reptir U2 2A Cam Post Accident As Found: Temperature switch TSH-3 will not hold Q96332 (Hydrogen and Oxygen) H2 & 02 Gas setpoint. As Left: Replaced temperature switch Monitor will not zero or span. TSH-3 and calibrated. Also, zero and spanned H2 and 02 monitor.

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IV. LICENSEE _EVENLREE0RIS 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.

UMLLI Licensee Event RepoILNumbe.t DAtt IltlftoL0ctuttence 91-022 11/04/91 Control Room HVAC B Train INOP 91-023 11/26/91 Control Room Vent Isolation UBU_2 91-013 08/19/91 Entering EGC without the required survelliances, TS 14

! V. DATA _TABtLLAIIQllS The following data tabulations are presented in this report:

A. Operating Data Report B. Average ')aily Unit Power Level C. Unit Shutdowns and Power Reductions TS 14

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. .' APPENDIX C

. OPERATING DATA REPORT DOCKET NO 50-254 UNIT One DATE Ear n htt_2. 1991 COMPLETED BY CynthiA_L9tch-lhort TELEPHONE 130.9L654-ZZ41 f

OPERATING STATUS 0000 110191 1.-REPORTING PERIOD: 21QQ 113091 GROSS HOURS IN REPORTING PERIOD: 22.Q.

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 t%X. DEPEND. CAPACITY: 169 DESIGN ELECTRICAL RATING (HWe-Net): 189
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Net): N/f
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUHULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL ........... 649.7 438LL . 13585AJ
6. REACTOR RESERVE SHUTD0kN HOURS .................. 01 0.0 _. _3421.9 e
7. HOURS GENERATOR ON LINE ......................... 639.7 42472 L 131617.0
8. UNIT RESERVE SHUTDOWN HOURS ..................... 0.0 0.Q_ 90h2
9. GROSS THERIML ENERGY GENERATED (MWH)............. J514241 1 9911085A - 282662526.0
10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... _505193.0 3223116.0 91616970.0
11. NET ELECTRICAL ENERGY GENERATED (HWH)............ .488355.0..

3094763.0 8626900410

12. REACTOR SERVICE-FAC10R........................... 9012_ 54.7 _ZIL9
13. REACTOR AVAILADILITY FACT 0R. . . . . . . . . . . . . . . . . . . . . . 90.2 54.7 .6012
14. UNIT SERVICE FACTOR ............................. 88.8_ 53.L 76.5
15. UNIT AVAILABILITY FACTOR ........................ 88.8 53.0 77.0 1
16. UNIT CAPACITY FACTOR (Using HDC) ................ 98.1 SQ L 6LZ
17. UNIT CAPACITY FACTOR IUsing Design HWe) ......... _ 95.6 48.9 63.5 l 18. UNIT FORCED OUTAGE RATE ......................... 1.6 -1G 1 5.6
19. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION ', EACH):
20. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY l

COMMERCIAL OPERATION 1

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. _ - _ _ _ _ _ _ _ _ ~ _ _ _ _ _. ._.

t APPENDIX C OPERATING DATQ REPORT DOCKET N0 h0-265 UNIT Iwo OATE D.eitmher_.22_1931 COMPLETED BY Cyntbla_Lasth-$h2tt TELEPHONE 1309.)_654-2241 OPERATlHG STATUS 0000 110191

1. isEPORTING PERIOD: _2400_ 113091 GROSS HOURS IN REPORTING PERIOD: 22 0
2. CURRENTLY tVTHORIZED POWER LEVEL (HWt): 2511 HAX. DEPEND. CAPACITY: 269 DESIGH ELECTRICAL RATING (HWe-Net): 789
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Net): N/A
4. REASONS FOR RESTRICTION (If ANY):

THIS HONTH YR TO DATE CUHULATIVE

5. NUMBER OF HOURS RCACTOR llAS CRITICAL ............ ZZQ,0 7050.5 _,13213SI
6. REACTOR RESERVE SHUTDOWN HOURS ............... .. Q,Q 0.0 22B5J v
7. HOURS GENERATOR ON LINE ......................... 720.0 600BA . 129275.9
8. UNIT RESERVC SHUTDOWN HOURS ..................... 04 0.0 702.9
9. GROSS THERHAL ENERGY GENERATED (HWH)........ .... 131423SJ 15639423.0 278870744.0
10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... _fl01111Q _10225JhD 89533725,0
11. NET ELECTRICAL ENERGY GENERATED (HWH)............ J1Q2d _4_22190LQ _01134_451,0
12. REACTOR SERVICC FACT 0R........................... _]ahQ 81 S _

77.8

13. REACTOR AVAILABILITY FACT 0R...................... 100.Q 87.9 79.6
14. UNIT SERVICE FACTOR . ........................... _,10LQ 87.2 75J
15. UNIT AVAlt. ABILITY FACTOR ................ ....... 10020 87.2 _]L2
16. UNIT CAPACITY FACTOR (Using HDC) .......... ..... SR,3 79.5 ,,,,

64.6

17. UNIT CAPACITY FACTOR (Using Design rWe) ......... 51.3 77.5 61,Q
18. UNIT FORCED OUTAGE RATE ......................... 0.0 10.7 8,Q
19. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE DATE, AND DURATION OF EACH):
20. IF SHUTDOWN AT DID OF REPORT PERIOO, ESTlHATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY C0tttERCIAL OPERATION . _ _

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. APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-154 '

UNIT Dne DATE D21210ber_1._lS9L_

COMPLETED BY Cynthia Loipk-Short TELEPHONE 1309) 651-2241 l

MONTH November 1991 DAY AVEREAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MWe-Net) (Me-Net'

1. 786 17. __766
2. 722 18, 735 ._
3. 798 19. 795 4 . 7]l8 20. 796 ,

l 5, 797 21, 693

6. 798 22. -4
7. 797 23. -7
8. 797 24, 241
9. 772 25, 704
10. 789 26. UB
11. 789 27s _ 794

'12. 798 28. 796 ,

13. bS 29. 565
14. 797 30. -8
15. 773 31
16. 754 INSTRUCTIONS On this form, list the average daily unit power' level in HWe-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.1001. line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footr.oted to explain the apparent anomaly.

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,. APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-255 _

UNIT Jyo DATE DatemhtL2._1931 COMPLETED BY Cynth1LLoith-Shor_t TELEPHONE 1301L654-2241 MONTH Novembt.r_lS11 DAY AVEREAGE DAILY POWER trVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MHe-Net)

1. ___ 639_.. I7. 515
2. 631 18. _h10
3. 619 19, 547
4. .

636 20, 542 _

5. 631 .
21. 538_ _
6. __ 62fl 22. ._ 548
7. 626 23. 344
8. 623 24, 527
9. 619 25. .144 10, 616 26. SSL
11. 6.QL 27, 554' _
12. 613 28. 511
13. 561 29, 490
14. 551 30, 500
15. 59f 31.
16. 564 INSTEKTIONS On this form, list the average daily unit power level in MWe-Net for each day in thr. reporting month. Compute to the nearest whole megawatt.

Ttese 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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V1. UNLOVElEEDRIlttG_REQUIREMERIS The following items are included in this report based on prior commitments to tte commission:

A. B!Lin_S_teMLRellef_ Valve OperAtlons Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Uall: One DA1.e: November 24, 1991 hhAs_Attuated Ho l lype_of_ Actuation 1-203-3B Manual 1-203-3E Manual Plant Conditions: Reactor Pressure - 923 PSIG QRitr_tRtlan of Evoati: Post Maintenance and Partial test of ERV Operability lest (QCOS-203-3) Tech Spec Ref.

3.5/4.5/D.l.a.

B. Cone , sd Drive Scram Timing Q1ta for Units One_and_l c There no Control Rod Drive scram timing data for Units One and Two for the re s ting period.

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VII. REEUELING.INE0RinIl0N The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandali (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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