ML20044C039

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Monthly Operating Repts for Feb 1993 for Quad-Cities Nuclear Stations,Units 1 & 2.W/930305 Ltr
ML20044C039
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/28/1993
From: Michael Benson, Walsh R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RJW-93-05, RJW-93-5, NUDOCS 9303170035
Download: ML20044C039 (27)
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Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 RJW-93-05 March 5, 1993 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 r Enclosed for your information is the Monthly Performance Report covering the ,

operation of Quad-Cities Nuclear Power Station, Units One ind Two, during the month of February 1993.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION A

Robert J. Walsh Tech Staff Supervisor j RJW/MB/dak Enclosure cc: A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector I I

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' QUAD-CITIES NUCLEAR POWER STATION ,

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UNITS 1 Arm 2 .

MONTHLY PERPORMANCE REPORT i

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February 1993 COMMONWEALTH EDISON COMPANY AND i

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IOWA TETTNOIS GAS & ELECTRIC COMPANY..

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..C DOCh4T NOS. 50-254 AND 50-265 i LICENSE NOS. DPR-29 AND DPR-30 i

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L TABLE OF CONTENTS I. Introduction T

II. Summary of Operating Experience i

A. Unit One B. Unit Two r

III. Plant or Procedure Changes, Tests, Experiments, and Safety Related ,

Maintenance .l A. Amendments to Facility 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 f

IV. Licensee Event Reports

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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 NRCMORPT

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I. INTRODUCTION r

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

i each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, i

Illinois. The Station is jointly owned by Commonwealth Edison Company and [

Iowa-Ill!nois Gas & Electric 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 i

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 I for unit Two.

This report was compiled by Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

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l II. S,gMMARY OF OffRATING EXPERIENCE I

A. Unit one l'

Quad Cities Unit One initiated a load drop to 250 MWe on February 5. for maintenance on the number one bypass valve, the feedwater heaters, and- ']

the control intercept valve. Work was completed and a load increase 1 initiated on February 6.

Unit One was reduced in power to 100 MWe and then scrammed on February j

27. A weekend outage was entered so that maintenance could be performed on the bypass valves and the feedwater heaters. The reactor was made 1 critical at 20:08 on February, 2B but the generator was not on-line until f March 1. i The unit was on line for all periods during the month not mentioned above. Numerous load drops were performed for the Chicago Load Dispatch (CLD). None of these caused the average daily unit power level to drop below 80% of full power.

B. Unit Two Quad Cities Unit Two was returning to full power early on February 1, following a SCRAM late in January. The unit remained on line for the entire month of February, 1993. Numerous load drops were performed per CLD, but none caused the average daily unit power level to drop below 80%

of full power. ,

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III. PLANT OR PROCEDURE CHANGES. TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE ,

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

t C. Tests and Exoeriments Recuirine NRC Annroval f There were no Tests or Experiments requidng NRC approval for the i reporting period.

D. Corrective Maintenance of Safety Related Ecuipment The following represents a tabular summary of the major safety related '

maintenance performed on Units One and Two during the reporting period.

This summary includes the following: Work 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 1 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED -

Q00506 755 Troubleshoot and repair IRM Discovered detectors 14 and 16 11 spiking problem. defective, replaced with new detectors.

Q03418 1100 Replace standby liquid Found temperature indicating

.o control tank temperature controller (TIC) out of cal.

control. Replaced TIC and checked setpoint.

Q04100 300 Repair control rod K-5, 38- Found coupling bolt loose.

19. Drifted past 00 and Adjusted seating pressure and would not withdraw. checked spring tension.

Q04118 261 Repair broken glass cover on Replaced broken glass with new.

recirc pump B DP switch 1-0261-35D.

Q04209 300 Repair CRD 06-43 charging Installed new valve seat, check water check valve 1-0305- valve ball, gaskets, 0-rings, 115. and diaphragm.

Q04226 300 Repair CRD D-12, 14-47, Replaced 0-ring, installed and accumulator. torqued bottom flange bolts.

Q04485 2300 Investigate ground in HPCI Replaced soleno.id 1-2303, HPCI logic. turbine turning gear motor engage. Ground cleared.

Q04621 2300 Repair HPCI torus suction Found valve would not opens valve 1-2301-56. Cleaned linkage and valve opened.

Q04646 1100 Adjust packing, packing nuts Adjusted packing on middle and-on 1B standby liquid control north cylinder. Slow leak still pump 1-1102B. present.

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A Q04647 1100 Adjust packing, packing nuts Adjusted packing on south, on 1A standby liquid control middle, and north cylinder. A pump 1-1102A. decrease in leakage was attained .

in the south and center cylinders. The north cylinder's leakage increased after adjustment of packing.

Q04659 300 Repair scram inlet valve 1- Found a packing leak. Adjusted 0305-126 on CRD 06-43:. packing, set seating pressureu.

and spring tension.

Q04676 2300 Investigate and repair cause Found brushes and brush' holders of inability to place HPCI improperly installed. Installed ,

turbine on turning gear brushes correctly.

locally.

Q04774 300 Repair CRD 30-47 HCU Replaced accumulator, accumulator.

Q04830 263 Repair jet pump pressure Replaced valve.

switch. 1-0263-111D. During surveillance, found pre-pressurization valve would-not hold at reactor pressure.

004899 756 Investigate / repair cause of Installed new trip card for Z28 "C Bypassed" light not. on Rod Block Monitor'#7.

working on LPRM 16-09C'4-rod display.

Q05339 220: Repair solenoidLvalve 1- Found no problems. Replaced 0220-45, 1B recirc loop solenoid valve and put in'new sample. sealtite fittings as a preventive measure.

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Q05735 2300 Repair HPCI torus suction Found disc misaligned on seat.

check valve 1-2301-39. Right hold down bolt was. loose Fails to seat properly. and lock washer was broken.

Bushing was loose in flapper.

Reassembled valve and properly-aligned the disc.

Q88581 7800 Replace cracked case on Removed old breaker from MCC and spare breaker 1-781911-1. replaced with a new one. ,

Q88583 7800 Replace cracked case on Removed old breaker from MCC and-spare breaker 1-781911-30. replace with a new one.

Q94647 1000 Repair tube leak on 1B RHR- Replaced old bellows. Weld heat exchanger. repaired floating head in places. Installed new gasket on inner head flange. Reassembled heat exchanger.

Q98680 5700 Repair liquid line solenoid -Found thin oil with a very fine i valve 1/2-5741-339 on B grit present. Rebuilt valve, Control Room HVAC. replaced wire nuts, and verified Compressor. free movement of piston.

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UNIT 2 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED Q00566 1000 Investigate and repair local Bent the tab inside the green control station 2-1001-16A. bulb socket out so it would make contact with the bulb. Replaced the bulb as a preventive measure.

Q00825 2300 Repair'or replace HPCI Put new pipe thread teflon on differential pressure connector at pressure switch.

indicating switch 2-2341-1. Loosened and retightened all connections. Pressure test at 55 psi saw no leaks. i Q03133 700 Repair IRM 17. Installed new detector. .

Installed' connector on detector. t Taped connectors and installed guard tube.

QO3271 2000 Investigate and repair 2B Found pump not working.

reactor building floor drain- Replaced oil, breaker in cubicle sump. H2-MCC 28-3, and screws that hold the breaker in. Installed new sump pump.

QO3422 1100 Replace standby liquid Installed new TIC in existing control temperature case.

indicating recorder (TIC) 2-1154.

Q03626_ 2500 Repair ACAD air receiver Found'D2 zener'5.'6V diode bad.

switch 2-2540-020. Installed new zener and performed.a loop calibration of4 '

the transmitter, ETU, and PI.

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QO3738 2300 Repair cover on pull-box Found cover hanging by wire and located next to junction box tape. Removed tape and wire and 2-2RB-54. installed screws and washers to .

hold cover on.

Q04778 7800 Repair MCC 28-2 cubicle D3 Removed old contacts and hydrogen seal oil vacuum replaced with new ones. Lubed pump breaker. all contacts and installed contact kit for main contactors.

Q04901 300 Repai[ nitrogen leak where Removed pressure gauge and pressure gauge connects to calibrated. Removed fitting the instrument block of CRD from instrument block and 22-23. replaced the O-ring. Lubricated and reinstalled 0-ring.

Reinstalled gauge. Snooped for leaks and found none.

005187 203 Repair flange. leakoff'line Found drain extension line for 2B main' steam line sheared off. Replaced drain electromatic relief valve 2- extension to the flange.

0203-3E.

Q05233 2300 Investigate / repair cause of Found loose connection on fuse lights failing to illuminate F12 #1 terminal. Tightened on HPCI motor gear unit. connections.

Q05243. 2300 Repair HPCI-turbine oil Removed, Cleaned,_ calibrated,  :

pressure switch 2-2341-10. and reinstalled the switch.

'005253 902-17 Repair-or. replace U2 #4 stop Checked for loose wiresfand- '

valve relay 590-124H. replaced the position switch for the #4 stop valve.

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Q05404' 300 Replace water piston on Installed new accumulator with accumulator 2-0305-125. new O-rings and torqued flanges.

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Q05493 1000 Repair blown gasket on 2A Installed new gasket. Furmanite RHR pump seal cooler, was contracted to seal the '

flange leak. A rubber boot was .

placed around the flange to prevent further' leakage from i potentially spraying the motor.

Q05598 300 Repair CRD 14-19 HCU Found ground in level switch. .,

accumulator 2-0305-125. Installed new switch. Ground Fuses are repeatedly being, disappeared.

blown.

Q05605 1000 Inject the 2A RHR pump seal Injected Furmanite. Leakage cooler with'Furmanite, reduced to approximately 1 drop per second.

Q05606 1600 Repair personnel-hatch 2- Found key on gear 3 sheared.and 1600-X2. Locking mechanism the set screw cracked. Replaced appears to be loose or key and screw. .

broken.

, Q05736 2300 Repair HPCI torus suction Found minor pitting on valve -

check' valve 2-2301-39. disc to seat face. Aligned disc to seat and reassembled valve.

Q74866 756 Investigate / repair:APRM #1. Rejected to: vendor.

Plus side of power. supply tripped causing channel "A" ,

1/2 SCRAM.

QB2182 '1000 Repair RHR. cross tie north ~ Found switches worked fine while stop valve ~ 2-1001-19A. valve was'OOS.- Unable:to verify i Valve would not operate from proper operation. ,

local valve operator station.

Q88123 756 Repair LPRM 24-49 detector No problem found.

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QP9907 902-21 Repair area high temp alarm Cleaned all connectors and F spuriously caused by pushing switch contacts. Replaced 2 . .

" Read" button. 1040-8C with-new switch. Alarm ,

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IV. UCENSEE 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.

-t UNIT 1 Licensee Event {

ReDort Number pate Title of Occurrence ,93-001 02-09-93 HPCI/RCIC Auto transfer of suction .i relays not tested.

UNIT 2 Licensee Event ReDort Number Date Title of Occurence i

There were no Licensee Event Reports for Unit 2 for this reporting period.  ;

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V. DATA TABULATION _S i

The following data tabulations are presented in this report:

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A. Operating Data Report B. Average Daily Unit Power Level ,

C. Unit Shutdowns and Power Reductions ,

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i APPENDIX C I

'. OPERATING DATA REPORT DOCKET NO 50_2E4 .

UNIT' Ope  !

DATE. March 5. 1993  ;

i COMPLETED BY MalLEensan TELEPHONE (309) 654-2241

-OPERATING STATUS ,

0000 020193

1. REPORTING PERIOD: 2400 022B23_ GROSS HOURS IN REPORTING PERIOD: EZ2 {
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX. DEPEND. CAPACITY: 769  !

DESIGN ELECTRICAL RATING (MWe-Net): ZS9

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 14/A >
4. REASONS FOR RESTRICTION (If ANY): ,

THIS MONTH YR TO DATE CUMULATIVE'

5. NUMDER OF HOURS REACTOR WAS CRITICAL ......... . 631.6 1375.6 144136.5
6. REACTOR RESERVE SHUT 00RN HOURS ...... ........... OtD_ 0.0 3421.9 ,
7. HOURS GENERATOR ON LINE ............. ....... ... 627.1 1371.1 139762.7 B. UNIT RESERVE SHUTDOWN HOURS .................. . 0.0 0.0 909.2
9. GROSS THERMAL ENERGY GENERATED (HWH)............. 1503945.6 3319968.0 300901791.8
10. GROSS ELECTRICAL ENERGY GENERATED (MWH)........... 491596.0_ 1084280.0 97503370.0 i
11. NET ELECTRICAL ENERGY GENERATED (MWH)............ 470715.0 1038609.0 91914121.0
12. REACTOR SERVICE FACT 0R........................... 93.99 97.15 78.73-
13. REACTOR AVAILABILITY FACT 0R...................... 93 92 97.15 80.60' -
14. UNIT SERVICE FACTOR ............................. 93.32 96.83 76.34 4
15. UNIT AVAILABILITY FACTOR ........................ 93.32 96.H3. 76.84
16. UNIT CAPACITY FACTOR (Using MDC) ................ 91.03 95.38 65.29
17. UNIT CAPACITY FACTOR (Using Design MWe) ......... 88.78 92.96 63.63
18. UNIT FORCED OUTAGE RATE ........................ 6.68 3.17 5.79 i
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:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED '

INITIAL CRITICALITY +

INITIAL ELECTRICITY I

COMMERCIAL OPERATION f

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APPENDIX C ,

. . ' OPERATING DATA REPORT DOCKET NO 50-265 ,

UNIT lyo ,

DATE M@tch 5.1993  :

COMPLETED BY Hatt Benson TELEPHONE (3091 654-2241 OPERATING STATUS g 0000 020193 >

1. REPORTING PERIOD: 2400 022Q23_ GROSS HOURS IN REPORTING PERIOD: _522
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX. DEPEND. CAPACITY: 169 DESIGN ELECTRICAL RATING (MWe-Net): ZS9  ;
3. POWER LEVEL TO WHICH RESTRICT 3 (If ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (If ANY): ,

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL ............ 672.00 1251 32 140426.55
6. REACTOR RESERVE SHUTDOWN HOURS ..................

Q10_ 0.S. 2985.8D'

7. HOURS GENERATOR ON LINE ......................... 672.00 1Z15152 136857.95
8. UNIT RESERVE SHUTDOWN HOURS ..................... 0.0 0.0 702.90 '
9. GROSS THERMAL ENERGY GENERATED (MWH)............. 1657855.20 2254043.20 295627452.40
10. GROSS ELECTRICAL ENERGY GENERATED (MWH).......... _542074.00 971463.00 94996724.00'
11. NET ELECTRICAL ENERGY GENERATED (MWH)............ 519781.00 _RZ9342,00 _B2262692.00
12. REACTOR SERVICE FACT 0R............. ............. 10a QQ_ 88.37 77.37
13. REACTOR AVAILABILITY FACT 0R...................... ___192100_ BS131 79.01
14. UNIT SERVICE FACTOR .................... ........ 1HQtaQ_ B5.91 75.42 -
15. UNIT AVAILABILITY FACTOR ........................ 10QtDQ_ 85.91 75.79
16. UNIT CAPACITY FACTOR (Using MDC) ................ 100.58 B514Q 641 45  ;
17. UNIT CAPACITY FACTOR (Using Design HWe) ......... 98.03 63 tZf 62.82
18. UNIT FORCED OUTAGE RATE ......................... 0.0 14.09 7.84  ;
19. SHUTDOWNS SCHEDULED DVER NEXT 6 MONTHS (TYPE. DATE, AND DURATION OF EACH): $
20. IF SHU1DOWN AT END OF REPORT PERIOD,. ESTIMATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

'I FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY .

COMMERCIAL OPERATION 1.16-9 TS 14 ,

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE March 5. 1993 COMPLETED BY Matt Benson '}

TELEPHONE (309)'654-2241 I MONTH February 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL {

(MWe-Net) (MWe-Net)

1. 760 17. 785
2. 762 18. 786 '
3. 738 19. 785
4. 733 20. 785
5. 754 21. 756 t
6. 344 22. 783 [
7. 757 23. 783 .
8. 755 24, 784
9. 759 25. 783  !
10. 785 26. 751 [
11. 740 27, 20
12. 787 28. -8 i
13. 787 29.

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14. 774 30,
15. 787 31.

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16. 785 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 ne vouasions 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

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s APPENDIX B AVERAGE DAILY UNIT POWER LEVEL ,

DOCKET NO 50-265 UNIT Two DATE March 5, 1993 COMPLETED BY Matt Benson  !

TELEPHCNE (309) 654-2241 MONTH February 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ,

(MWe-Net) -(MWe-Net)

1. '644 17 _ 787
2. 737 18. 762
3. 788 19. '786 I

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4. 738 20. 787
5. 787 21. 787 ,

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,8 22, 783

7. 769 23, 782
8. 789 24. 777 i
9. 788 25. 777
10. 758 26, 779 i
11. 758 27. 784 i
12. 774 28. 786 .:
13. 787 29. '!

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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. i restricted power level line) . In such cases, the average daily unit power output i sheet should be footnoted to explain the apparent anomaly.

1.16-8 NRCMORPT .j

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APPENDIX D

- DOCKET NO. 50-254 X

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UNIT NAME One COMPLETED BY Matthew Benson

. DATE March 5, 1993 REPORT HONTH February, 1993 TELEPHONE 309-654-2241' w $~

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w NO. DATE REPORT.NO. U (HOURS) g CORRECTIVE ACTIONS /C0ft1ENTS 93-01 02-06-93 F 16.3 B 5 ---- -- -----

Load Drop for #1 BPV/lleater/CIV Maintenance 02 02-27-93 S '44.9 B 2 ---- -- -----

Outage for Bypass Valve and lleater Maintenance.

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTICNS DOCKET NO. 50-265 ,

4 UNIT NANE Unit Two COMPLETED BY Matthew Benson DATE March 5, 1993 REPORT HONTH February, 1993 TELEPil0NE 309-654-2241 '

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w DURATION R til g EVENT UV o NO. DATE (HOURS) "g REPORT NO. U CORRECTIVE ACTIONS / COMMENTS There were no power reductions of greater than 20% over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period for the month of February, 1993.

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9 VI. UNIOUE REPORTING REOUIREMENTS l

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The following items are included in this report based on prior commitments to the commission: [

i A. Main Steam Relief Valve Ooerations '

t Relief valve operations during the reporting period are summarized in the j following table. The table includes information as 'to which relief valve was i actuated, how it was actuated, and the circumstances' resulting in its [

actuation. [

Unit; One i Date: February 28, 1993 Valve Actuated: 1-203-3C' No. & Tvoe of Actuation: Post Maintenance  :

Plant Conditions: Reactor Pressure - 920 PSIG  :

i Descriotioin of Events: -Tested on startup from short outage.

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l B. Control Rod Drive Scram Timino Data for Units One'and Two  ;

i 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 performed with reactor pressure greater than 800 PSIG. >

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD-DRIVES, FROM 01/01/93 T0.01/31/93 .

AVERAGE TIME IN SECONDS AT % MAX. TIME .

INSERTED FROM FULLY HITHDRAHN FOR 90%'

INSERTION DESCRIPTION NUMBFR 5 20 50 90 Technical Specification 3.3.C.1 &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Averaae Scram Insertion Time)

'01-28-93 '1' O.30 0.67 1.42 2.15 H-12 For Accumulator Replacement 2.15 02-12-93 l' O.33 0.72 1.54 2.77 D-5 Accumulator Replacement-U2 005404 2.77 02-26-93 1 0.32 0.69 1.46 2.61 K-7 Scram Inlet Valve U2 Q05593 2.61 T3 75

. ~,  !

?

L VII. REFUELING INFORMATION 3

h 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 I to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC Request '!

f or Refueling Information, dated January 18, 1978. [

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.i NRCMORPT i

OTP.300-532

- Revision 2 QUAD CITIES REFUELING October 1989  :

INFORMATION REQUEST

1. Unit: Q1 Reload: 12 Cycle: 13 2.

i Scheduled date for next refueling shutdown: 3-14-94 5

3. Scheduled date for restart following refueling: 6-13-94 *
4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: .

NOT AS YET DETERMINED .

5. Scheduled date(s) _for submitting proposed 11 censing action and  :

supporting information: ,

NOT AS YET DETERMINED 6.

Important licensing considerations associated with refueling, e.g.,-.new or'different fuel design or supplier, unreviewed_ design or performance i

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

1

/!

NONE AT PRESENT TIME.

-[

_i

7. The number of fuel' assemblies.
a. Number of assemblies in core: 724-
b. Number of assemblies in spent fuel pool: -1557 i
8. q The present licensed spent fuel pool storage capacity:and the size of...  !

any increase in licensed storage capacity that has been requested or is :t planned in number of fuel assemblies:

1 h

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: 2009 i APPROVED  !

14/0395t -1 .00T 3 01969 i O.C.O.S.R.

l

_.ew,

QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q2 Reload: 11 Cycle: 12
2. Scheduled date for next refueling shutdown: 03/06/93
3. Scheduled date for restart following refueling: 06/05/93
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:

NO SUBMITTALS REQUIRED.

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:

NONE AT PRESENT TIME.

7. The number of fuel assemblies.
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 2439
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: 3897
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: 2009 APPROVED ,

(final) 14/0395t - OCT 3 01989 -

O.C.O.S.R.

l

+

E 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 hater Reactor.

CRD - Control Rod Drive EUC - 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

LPCI - Low Pressure Coolant Injection Mode of RHRs LPRM. - Local Power Range Monitor. ,

MAPLHGR - Maximum Average Planar Linear Heat Generation Rate i 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 land Health PCI - Primary Containment Isolation

SRM. - Source Range Monitor

-TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center f i

NRCMORPT i

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