Text

Monthly Operating Repts for Apr 1983
	ML20023C490
Person / Time
Site:	Quad Cities
Issue date:	05/02/1983
From:	Misak A; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20023C484	List: ML20023C483; ML20023C490;
References
	NUDOCS 8305170376
	Download: ML20023C490 (21)
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT APRIL 1983 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

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TABLE OF CONTENTS I, Introduction II, Summary of Operating Experience A. Unit One B, Unit Two III, Plant or Procedure Changes, Tests, Experhnents, and Safety Related Maintenance A. Amendments to Facliity License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C, Tests and Experiments Requiring NRC Approval D, Corrective Maintenance of Safety Related Equipment 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

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1. INTRODUCTION Quad-Cities Nuclear Power Station is camposed 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 Iowa-Illinois Gas & Electric '

Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was i'

Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The condenaer cooling method is a closed cycle spray canal, and 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 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit I and March 10, 1973 for Unit 2.

This report was complied by Becky Brown and Alex Misak, i telephone number 309-654-2241, extensions 127 and 194.

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II.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE April 1-19: Unit One began the month operating at full power and continued at this level except on three occasions when the unit dropped load to 700 MWe to perform weekly Turbine tests.

April 20-30: On April 20, at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , the unit dropped load at 100 MWe/ hour to 550 MWe for a control rod pattern change. The change was completed at 0145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months on April 21, and the unit increased load normally to full power. The unit continued full power operation for the duration of the month, except for one occasion when load was reduced to 700 MWe to perform weekly Turbine tests.

B. UNIT TWO April 1-22: Unit Two began the month increasing load following an end of March Maintenance Outage. The unit continues to be derated due to end of cycle fuel depletion. In addition, the unit dropped load to 700 MWe three times to perform weekly Turbine tests.

April 23-30: At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , on April 23, the unit dropped load at 100 MWe/ hour to 400 MWe for control rod drive scram timing and MSIV timing. At 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months , on April 24, timing was completed, and the unit began increasing load normally. At 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months , the increase was terminated due to Condensate pump problems. At 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months , the unit again began increasing load normally and reached full power of 740 MWe at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months on April 25

III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications On January 20, 1983, the NRC issued Amendment 85 to License DPR-29 This atendment permitted temporary operation with isolation valva M0-1-220-1 inoperable due to excessive leakage.

On March 3,1983, the NRC issued Amendment 79 to License

DPR-30. This amendnent added a footnote to allow the barrier fuel ramp cell to exceed the Technical Specifica-tion LHGR Limit by no more than 10 percent during the end of cycle 6 barrier fuel ramp test.

j B. Facility or Procedure Changes Requiring NRC Approval i

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

C. Tests and Experiments Requiring NRC Appro al There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety i related maintenance performed on Unit One and Unit Two during the reporting period. This summary includes the i following headings: Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Ef fects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION -

Q25168 83-14/03L Unit 1 250 VDC A cell in the battery The cracked cell was The cell was replaced.

Battery 8350 was cracked. removed and j umpered.

The loss of one cell did not prevent the bat tery f rom performing its function.

Q20511 82-17/03L Core Spray Water was leaking into The valve was taken out The valve operator was injection Valve the operator, of service in the open disassembled and 1-1402-25B position, and the in- repaired. The valve line-24B was closed. was st roked and i ts Core Spray Subsystem logic circuit was was fully operable. successfully tested.

Q25570 83-18/03L M0-1-1001-5B The anti-rotation The 'B' loop of The anti- itation Valve pin had fallen out. Con ta i n nen t Cooling was pin was replaced and inoperable; all the limits were required surveillances adjusted. The valve were successfully was then stroked and performed. The redundant its position verified.

loop was fully operable.

UNIT TWO liAINTENANCE SUtiMARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACT10N TAKEN TO NUMBER NUMBER COMPONENT MALFUNCT10N SAFE OPERATION PREVENT REPETIT10N There were no Work Requests for Unit Two reporting period of April 1983

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4 IV . LICENSEE EVENT REFORTS 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 ONE Licensee Event

Report Number Date Title of Occurrence 83-15/03L 4-5-83 Reactor Building Ventilation Auto-Isolation 1

83-16/03L 3-31-83 RHR Discharge Pressure

} Greater Than 90 PSIG 83-17/03L 4-12-83 1C RHR Service Water Pump Out of Service to -

Repair Leak i

83-18/03L 4-12-83 IB Containnent Cooling Loop Inoperable 83-19/03L 4-12-83 Core Spray Discharge Pressure Greater Than 90 PSIG l

UNIT TWO

! 83-6/03L 4-24-83 2D MSIV Limit Switch I (RPS) Failure i

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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

OPERATING DATA REPORT

~ DOCKET NO. 50-254 UNIT ONE DATEMov 02 1983

~ ~~~~ COMPLETED ~BYAlex Misok

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TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 040183

~1. Reporting period:2400 043083 Gross bours in~ reporting' period: '719

2. Currently authorized power level (MWt): 2511 Max. Depend capacity

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~(MWe-Net): 769*~ Design' electrical roting~(MWe-Net): '789

3. Power level to which restricted (if any)(MWe-Net): NA

4. keasons for restriction (if any):

This~ Month ~ Yr'.~to Date Cunulative

5. Number of hours reactor was critical . . . - - --

719.0_- -

2721.4 77892.6_ -

6. Reactor reserve shutdown hours 0.0 0.0 3421.9 ,

2692.~9

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719.0

7. Hours generator' on line 7477'7.5

8. Unit reserve shutdown hours. 0.0 0.0 909.2 9, Gross thermal energy generated (MWH) 1765482 6504574 152717565 10.' Gross electrical' energy generated (MWH) 586692 2139592 49261473' ii. Net electrical energy generated (MWH) 554675 2014478 45843386

12. Reactor service factor 100.0 94.5 81.0

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13.~ Reactor ovallobility factor 100.0 94.5 84.6

14. Unit service factor 100.0 93.5 77.8

15. Unit availability factor 100.0 93.5 78.7 91.0.

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16. Unit capacity factor (Using MDC) 100.3 62.0

17. Unit copocity factor (Using Des.MWe) ,

97,8 88.7 60.4

10. Unit forced outoge rote 0.0 2.3 6.6 ,

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~ 19 . Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of each):

20. If shutdown at end of report period,estinated date of startup NA

The MCC nay be lower than 769 HWe during periods of high unbient temperature due to the thueal perfernance of the sprop canal.-

D6FFICIAL CCMPANY HMERS ARE USED IN THIS REPORT

OPERATING DATA REPOR' DOCKET NO. 50-265 UNIT TWO DATEMov 02 1983 COMPLETED BYAlex Misak

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TELEPHONE 309-654-2241x194 OPERATING STATUS 0000 040183

1. Reporting period:2400 043083 Gross' hours in reporting period: 719

2. Currently authorized power level (MWt): 2511 Mox Depend capacity (MWe-Net): 769* Design electrical ruting-~(MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

'This Mon'th Yr.to'Date Cunulative

5. Number of hours reactor was critical 719.0 2615.0 74878.4

6. Reactor reserve shutdown hours 0,0 0,0 2985,8

7. Hours generator on line

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719,0 2585,7 72173.8

8. Unit reserve shutdown hours. 0,0 0.0 702.9

9. Gross thermal energy generated (MWH) 1593322 5821733 150413227

10. Gross electrical energy generated (MWH) 517642 1866434 47903969

11. Het electrical energy generated (MWH) 486020 1750560 44934127

12. Reactor service factor 100.0 90.8 78.6

13. Reactor evollobility factor 100.0 90.8 81,7

14. Unit service factor 100,0 89,8 75,8

15. Unit ovellability factor 100.0 89.8 76.5 L6. Unit capacity factor (Using MDC) 87,9 79,1 61.3 j

17 Unit capacity factor (Using Des.MWe) 85,7 77,1 59.8

18. Unit forced outage rote 0,0 3,9 9,0

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each ):

20. If shutdown at end of report period, estimated date of startup __}A __________

The MDC nay be lever than 769 MWe during perieds of high ambient temperature due to the thernal perfernuce of the spray canal,

$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-254 UNIT ONE DATEMay 02 1983 COMPLETED BYAlex Misak TELEPHONE 309-654-2241xi94 MONTH A p r' i l 1983 DAY AVERAGE DAILY POWEC LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 778,8 17, 759,0

2. 776,5 18, 766,4

3. 758,2 19, 785,i 4, 773,9 20, 764,7

5. 793.7 ' 21 ~. 615,4

6. 792.4 22. 714.3

7. 768.3 23. 753.0

8. 781,5 24. 751,4

9. 782,8 25, 785.4

10. 767.3 26, 781,3

'11, 781,9 27, 782.1 12, 790.8 28, 781,1

1. 3 . 777.7 29. 783,5 14, 782,5 30. B19,4 15, 783,6

16. 779,6 INSTRUCTIONS On this forn list the overage daily unit power level in MWe-Net for each day in the reporting month, Compute to the nearest whole,negewett.

These figures Will be vsed to plot a graph for each reparting nenth, Note that when posinin dependable copocity is used for the cet electrical rating of the snit there noy be occasions when the daily overage power level exceeds the 1018 line (or the restricted power level line).,In such cases,the overage daily unit power evtput sheet should be footnoted to explain the apparent onenoly

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEMov 02 1983 COMPLETED BYAlex Hisak

. TELEPHONE 309-654-2241x194 MONTH Arvil 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

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1. 720.3 17. 674.4

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2. 719.4

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~18. A71,~ 8 3, 713,i 19. _

669,i 4, 714.5 20, 664.5

5. 664.6-

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710.5 21.

6, 713,2 22. 656.3

7. 693.6 23. 657,6 700 i

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2 4 ', 456;8 8.

9. 687.0 25. 677,5 10, 697,4 26, 656,3 I

ii. 693~6 .

27, 736.6_, -I 12, 690.5 28, 567,4 13, 683.8 29, 647.4 1 1

14. 682.9

30. 675.6

15. 681,9 16, 673,3 INSTRUCTIONS On this fern nearest whole, listt. the overage daily unit power level in MW-Net for each day in the reporting nonth Conpete to negawat These figsres will be ssed to plot a graph for ecch reporting month. Hete that when meninen dependable capacity is used for the net electrical rating of the init there may be occasions when the daily overcge power level exceeds the 1981 line (or the restricted power level line),In. such cases,the overage daily snit power output sheet shecid be feevneted to explain the apparent anonaly

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y y 3 .. . ...y ID/SA Al'I'ENil X 1) QTI' 300-S13 IINIT SiltlTDOWNS AND POVEH IEI)tlCTIONS Hevision 6 August 1982 1)OCKET NO. _050-254 _ _ _ _ _

IINIT NAtlE _ Quad-C_i t _i e s_Un i _t 1 Cotil'I.ETED HY Alex flisak,.cxt 194 I) ATE _May__2,_1983 _____ imi'OHT llONTil ,_ AP RI L .1983. . _ _ _

TEI.EPilONE 109-654-224I m 8 e-m z Rb* n s Ex 8 8 d I,ICENSEF ISM da go DlJHATION d

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EVENT

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ColtRECTIVE ACTIONS /CollflENTS NO. DATE (flollHS) H El'O H T N O .

a ---- -

83-23 830402 s 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine l

test 83-24 830410 s 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine test 83-25 830416 s 0.0 B 5 liA XXXXXX Reduced load to perform weekly Turbine test s RB CONROD Reduced load for control rod pattern 33-26 830420 0.0 H 5 change 33-27 830423 s 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine test APPROVED AUG ! G 1982 (final) (,c y 3 g

n n n n FTTE M M P W M M FIE3 K'CI F825 PTE'1 n n n p ID/SA AI'I'ENDIX D QTi' 100-S1:1 IINIT SilllTDOWNS AND l'OWElt REDilCTIONS Revision 6 DOCKET NO. 050-265 Annust 1982 llNIT NAtlE Quad-Cities Unit 2 COill'I.ETED llY Alex Misak, ext 194 UATE May 2, 1983 REPORT ilONTil APRIL 1983 TEI.El'IlONE ~109-654-224I N $ H m - .

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< 8"d I.ICENSEl. tJ mo a sa g gu no gu w DtlRATION d EVENT u

NO. DATE (llollRS) REPORT NO. CORRECTIVE ACTIONS /CortflENTS a

83-31 830403 5 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine test 83-32 830407 5 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine test 83-33 830416 S 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine test 83-34 830423 5 0.0 B 5 RB CRDRVE Reduced load for cont rol rod drive scram timing and MSIV timing APPROVED (final) ygg3g

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

B. CONTROL R0D DRIVE SCRAM TIMING 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 Specification 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 was perforred with Reactor pressure greater than 800 psig.

I RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1 TO 12-31-83 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION

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NUMBER 5 20 50 90 Technical Specification 3.3.C.1 s DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Time) 4-24 88 0.29 0.66 1.42 2.50 2.72 Unit 2 Hot Scram Time "A" Sequence (H-9)

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VII. REFUELING INFORMATION t

.l The following inforcation 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

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QUAD-CITIES REFUELING tiarch 1978

( INFORMATION REQUEST r- ,

I L; 1. Unit: Q1 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: 9-6-82 3 Scheduled date-for restart following refueling: 12-18-82

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: Yes R

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

] Information: 8-19-82: Tech. Spec. changes submitted to the :TRC.

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

'different fuel design or supplier, unreviewed design or performance analysis n methods, significant changes in fuel design, new operating procedures:

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a) All 7x7 fuel assemblies vill be removed f rc: the core.

b) MAPL:iG3 curves for fuel types in the core are being extended to LC,000 T4D/ST.

) MCPR limits vill be determined by GE's CDEI computer code.

d) The vessel pressure safety limit is being modified to accc rodate the h[

I potential for higher reactor pressures as c"'a'"d t7 CDE!

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'l li r1 7 The number of fuel assemblics.

[ a. Number of assemblies in core: 724 d

b. Number of assemblies in spent fuci pool: 300 n

[j 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 r, in number of fuel assemblies:

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a. Licensed storage capacity for spent fuel: ?6R7 n

y b. Planned increase in licensed storage: 3 u

9. The projected date of the last refueling that can be discharged to the I spent fuel pool assuming the present licensed capacity: 2003 v

20 P P R C) V E E) e E APR 2 01978 e

C). CL C). S. R.

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1 QTP 300-S32 Rtvision 1

[ QUAD-CITIES REFUELit:G Harch 1978

( INFORMATION REQUEST e ,

1. Unit: Q2 Reload: 6 Cycle: 7

- 2. Scheduled date for next refueling shutdown: 9-11-83 a

3 Scheduled date~for restart following refueling: 11-20-83

4. tlill refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

Depending upon the Licensing analyses, a MCFR limit change may be needed.

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5. Scheduled date(s) for submitting proposed licensing action and supporting "1 . Information: 8-22-83 (if necessary) m

6. Important Ilcensing considerations associated with refueling, e.g., new or

'different fuel design or supplier, unreviewed design or performance snalysis methods, significant changes in fuel design, new operating procedures:

n 1 NFS intends to apply 10CFR50.59 to the Q2R6CT reload unless MCFR Technical Specification change is require d.

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7 The number of fuel assemblies.

@ a. Number of assemblies in core: 72h

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b. Number of assemblies in spent fuel pool: 1103 r1 b 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 n in number of fuel assemblies:

S d a. Licensed storage capacity for spent fuel: 3397

b. Planned increase in licensed storage: 0 9 The projected date of the last refueling that can be discharged to the I spent fuel pool assuming the present licensed capacity: 2003 0 PPROVED y

.. APR 2 01978 Q. C. O. S. R.

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F VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Re por t , 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 Uithout Scran BWR -

Boiling Water Reactor CRD -

Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Onergency Operations Facility GSEP - Generating Stations Emergency Plan H EPA - High-Ef ficiency Particulate Filter IIPCI - High Pres sure Coolant Injection Syst em HA3S -

High Radiation Sampling System IPCLRT - Integrated Primary Containment Leak Rate Tes t IRM - Intermediate Range Monitor ISI - Inservice Inspection LER - Licensee Event Report LLRT -

Local Leak Rate Test LPCI - Low Pressu re Coolant Injection Mode of RHRS LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR -

Minimum Critical Power Ratio M FLCPR - Maximum Fraction Limiting Critical Power Ratio MPC -

Maximum Permissible Concentration MS IV -

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 REM -

Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal Syst em RPS - Reactor Protection System RRM -

Rod Worth Minimizer SBGT S - Standby Cas Treatment System 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 in-Core Probe TSC - Technical Support Center

ML20023C490

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