Text

Monthly Operating Repts for May 1993 for Quad Cities Nuclear Station,Units 1 & 2
	ML20036C256
Person / Time
Site:	Quad Cities
Issue date:	05/31/1993
From:	Michael Benson, Walsh R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RJW-93-17, NUDOCS 9306150405
	Download: ML20036C256 (27)
	v • d • e

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' O Commonwealth Edison Ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 i

RJW-93-17 1

June 3, 1993 r

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

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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 1993.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

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Robert J. Walsh Tech Staff Supervisor RJW/MB/dak j

Enclosure i

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B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector

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QUAD-CITIES NUCLEAR POWER STATION' UNITS 1 AND 2

.. y MONTHLY PERFORMANCE REPORT i

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COMMO!MEALTH EDISON COMPANY AND t

IOWA-ILLINOIS GAS & ELECTRIC COMPANY-P NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

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I TABLE OF CONTEhTS j

I.

Introduction i

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II.

Summary of Operating Experience i

A.

Unit One B.

Unit Two 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' IV.

Licensee Event Reports i

t V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level l

C.

Unit Shutdowns and Power Reductions i

VI.

Unique Reporting Requirements l

t A.

Main Steam Relief _ Valve Operations

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B.

Control Rod Drive Scram Timing Data i.j VII.

Refueling Information f

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Glossary t

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INTRODUCTION i

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 Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The

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Architect / Engineer was Sargent & Lundy, Incorporated, and the primary l

construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license f

4 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

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l 18, 1971, and April 26, 1972.

Commercial generation of power began on

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f February 18, 1973 for Unit One and March 10, 1973 for unit Two.

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This report was compiled by Matt Benson and Debra Kelley, telephone number i

309-654-2241, extensions 2995 and 2240.

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II.

SUMMARY

OF OPERATING EXPERIENCE F

P A.

Unit One Quad Cities Unit One began the month at full power and remained on line for the entire month of May 1993. Numerous load drops were performed on orders from bulk power operations. Only one of these i

load drops caused the daily average net power generation to drop below l

20% of full load.

This occurred on May 2 with an average load of 585

MWe, B.

Unit Two L

Quad Cities Unit Two was in its twelfth refuel outage at the start of i

May 1993.

The unit entered the outage on March 6 and exited on May 26 when the reactor was made critical at 09:02 hours. Start up testing was performed and the generator was synchronized to the grid at 17:52 hours on May 27.

On May 30 at 12:35 while the reactor was shutdown due to a leak on the feed water system.

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l III.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, j

AND SAFETY RELATED MAINTENANCE l

i A.

Amendment # to Facility License or Technical Specifications Technical Specification Amendment No. 141 to Facility Operating License No. DPR-29 and Amendment No. 136 to Facility Operating License No. DPR-30 were issued on May 13, 1993 for Quad Ciles Nuclear Power Station, Units 1 and 2, respectively. The amendments delete Technical Specifications (TS) Section 3.11/4.11, "High Energy Piping Integrity (Outside Containment)," TS Section 3.12/4.12, " Fire Protection Systems," the Fire Brigade manning requirements from TS 6.1.C, and change the licenso conditions regarding fire protection.

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B.

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

C.

Tests and Experiments Requirina NRC Approval i

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

l D.

Corrective Maintenance of Safety Related Eauipment j

The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting

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period. This summary includes the following: Work Request Numbers, l

Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent j

Repetition.

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r UNIT 1 MAINTENANCE SUbMARY WORK REQUEST SYSTEM WORK REQUESTED WORK PERFORMED Q05017 1000 Repair test taps for RHR Found test taps stripped and pump discharge pressure damaged.

Replaced damaged switches 1-1053E, 1-1053F, fittings with new ones.

1-1053H, and 1-1053J.

Q06306 6700 Replace cup bearing nut on Found castle nut will not allow movable arm on 4kV breaker proper tightening or cotter. pin 1/2-6700-038.

installation.

Installed the proper castle nut.

Q06470 6700 Repair racking screw on 4kV Found shutter latch assembly breaker 1/2-6700-016.

damaged.

Replaced shutter latching with like part.

Q06541 6700 Replace SBM switch on 4kV Found high resistance on several breaker 1/2-6700-033.

contacts.

Replaced SBM switch with a new switch.

006780 2500 Replace indicating light on Replaced lamp for trips #1 and ACAD pressure switch 1-2540-

2.

20.

Q06919 6700 Repair auto start relay for Repaired internal control wire of U-1/2 diesel generator, 1-emergency auto start relay.

6705-1.

006954 6700 Adjust stationary auxiliary Adjusted linkage, contacts for 1/2 diesel generator output breaker, 1-6705-1.

Q06980 6700 Repair auxiliary switch Removed, adjusted, and modified linkage for breaker 1-6705-the linkage connection pin.

A 1.

hole was drilled so a cotter pin could be used to hold the linkage more firmly in place.

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Q07236 1000 Replace 1C RHR service water Replaced sight glass.

low pressure pump outboard sight glass.

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UNIT 2 MAINTENANCE SUbNARY WORK REQUEST SYSTEM.

WORK REQUESTED WORK PERFORMED Q00568 2300 Repair control station for Replaced resistor at the 2-2301-35 HPCI downstream pushbutton station.

torus suction valve.

002360 7100 Repair bus 28 cubicle 284C, Found racking screw mechanism 1/2 diesel generator cooling bent.

Lubricated racking screw, water pump breaker.

cleaned and cured breaker.

Q03036 1100 Repair 2-1105A, SBLC pump Set relief valve to 1520 psig.

discharge relief valve.

QO3366 4600 Repair diesel generator Found valve leaking by.

starting air receiver 2C and Installed new valves for the C 2D drain valves, 2-4699-and D drain receiver.

117(118).

Q06147 902-5 Replace cracked light bulb Found switch plunger broken.

holder in 902-5 SBLC B squib Removed old indicator and

circuit, removed necessary hardware to install'on new indicator.

Q06289 7800 Replace or repair MCC 28-1B Installed new breaker in compartment A4.

Failed trip cubicle.

test.

Q06320 1300 Replace bad bearing on Restacked bearing.

mechanical snubber 2-1313-135.

006498 5700.

Repair sealtite to 2A core Installed new sealtite.

spray room cooler motor.

Q06562 7800 Replace breaker in MCC 28-1B Removed old breaker and compartment D4; breaker installed a new one, failed EQ inspection.

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Q06690 261 Repair or replace recirc Found internals heavily pump B differential pressure corroded.

Replaced, and indicating switch 2-0261-'

calibrated new switch.

DP cell 35D.

was not replaced.

Q06732 7100 Inspect and repair / clean MCC Cleaned and tested all contacts.

28/29-5 cubicle A2.

Q06787 7800 Repair MCC 28-1B compartment Installed screw into lower coil E1, drywell cooler blower 2F retainer.

Replaced lugs.

coil.

Q06791 1700 Install missing supports on Installed new conduit supports.

120V AC power cables.

Q06905 30 Repair air leak in Changed interior seal and condensate pump room vault adjusted exterior seal.

B, penetration MK-1031.

Q06909 30 Repair air leak in RHR Cleaned pipe and installed new service water pump suction inner seal.

header room, penetration MK127.

Q06910 30 Repair air leak in RHR Cleaned pipe and replaced inner service water pump discharge seal.

header room, penetration-MK36.

Q06953 8300 Inspect / repair possible Found wire' pinched between a ground on 125 VDC from bus bolt head and' insulating board.

28' cubicle 4C.

Cut bad spot out and spliced back together.

Q06955 6700 Adjust new stationary Adjusted linkage.

auxiliary contacts for 1/2 diesel generator output breakers.

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i Q06964 902-17 Investigate drop out of seal Cleaned both 108B and 109B i

in contact for 109B relay.

relays.

Cleaned and regreased the main contact carrier.

Contacts were shown to open and close.

Q06995 263 Repair ATWS reactor level Found 1 of 4 master trip units indication and master trip unacceptable.

1 master trip unit.

unit will be repaired or rejected on another work request.

l 007007 1600 Repair weld at fluted end of Seal welded 1/4" plug.

Removed reactor water clean up by grinding the unconsumed penetration 2-1600-X14.

portion of the consumable ring.

Q07021 7600 Correct wiring discrepancies Removed field side jumper.

in cubicle 28/29-5 cubicle Moved wire 22508 at terminal 18 B2, reactor water recirc from cubicle side to field side.

pump discharge 2A valve.

j Q07032 263 Replace termination in wide Repaired wire connection and range transmitter 2-0263-verified operation.

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Q07036 6600 Investigate cause of diesel Fcund slight carbon deposits in generator tripping 2 minutes eductor tubes and a small amount after tart on crankcase of oil in crankcase pressure high 1 essure.

detector.

Ground washer off 3

eductor tube and replaced with gaskets.

l Q07052 6600 Investigate / repair diesel Installed a new switch and

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generator lube oil crankcase verified it to be operational pressure swit9h 2-6641-CPS.

and consistent.

Q07057 6600 Investigate cause of diesel Installed 5/8" tubing in place engine tripping 1 minute 45 of 1/2" tubing between the turbo.

seconds after start on high and the eductor.

crankcase pressure.

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Q07089 5200 Repair leaks on U2 diesel Tightened fittings on suction j

generator engine driven fuel side.

pump.

Q07118 7800 Repair back stab lead on MCC Found 2 auxiliary contacts with 29-6 cubicle A1, 2C drywell high resistance.

Installed 2 cooler.

new auxiliary contact assemblies.

Installed new lead on C phase.

Q07154 220 Repair recirc piping on 2-Found a loose union, loose sight 202-5B bonnet vent line.

glass nuts, and part of the gasket missing.

Retightened the union, installed a new gasket, and tightened the bolts.

Q07167 7800 Repair MCC 29-3 cubicle F1, Found broken mounting screw.

drywell cooler blower 2E.

Replaced brass mounting screws with stainless steel mounting screws.

Q07217 263 1-

<r^,igate Yarway wide Removed both sealing plugs and e a local level indicator reinstalled with washers and l

2 263-151B.

tightened.

No leaks observed.

Q07236 1000 Replace RHR service water Replaced sight glass.

low pressure pump outboard sight glass.

j Q07265 6600 Repair cables and wiring for Found U-2 bus duct with a hole

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U-2 diesel generator.

worn in it.

Hole was created by

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large steam line support bolt rabbing against the bus' duct.

Installed a patch on the bus duct.

Support bolt was determined to be unnecessary and will be removed.

- Q93730 20 Repair HPCI submarine door.

Found door seal damaged.

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Replaced door seal.

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Q93947 220 Repair pressure regulator Found glass and needle missing for AP valve 2-220-45.

on gauge.

Calibrated and installed a new gauge.

Installed a new regulator.

Q99331 203 Repair terminal block on EQ' Found a mounting screw broken.

junction box 2-203-2D.

Relanded all wires on a new-terminal strip.

Replaced terminal mounting screws.

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IV.

LICENSEE EVENT REPORTS

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There were no Licensee Event Reports for Unit 1 and Unit 2 for this reporting period.

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DATA TABULATIONS The following data tabulations are presented in this report:

l A.

Operating Data Report B.

Average Daily Unit Power Level

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Unit Shutdowns and Power Reductions f

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APPENDIX C OPERATING DATA REPORT DOCKLT NO.

50-254 UNTT One DATE June 3,1993 COMPLETED BY Matt Benson l

TELEPiiONE (309) 654-2241 OPER ATING STATUS 0000 050193

1. kEPORTING PERIOD: 2400 053193 GROSS IlOURS IN REPORTING PERIOD: 744

2. CURRENTLY Atrrl10RIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789 L

3, POWER LEVEL TO WlilCil RESTRICTED ('IF ANY)(MWe-Net): N/A

4. REASON 5 FOR RESTRICTION (IF ANY):

TIIIS MONTil YR TO DATE CUMULATIVE

5. NUMitER OF llOURS REACTOR WAS CRIMAL 744.00 3568.30 146329.20

6. REACTOR RESERVE $11UTDOWN }{OURS 0.00 0.00 3421.90 j

7. liOURS GENERATOR ON LINE 744.00 3547.10 141938.70 I

8. UNTT RESERVE SilUTDOWN llOURS 0.00 0.00 909.20

9. GROSS TilLRMAL ENERGY GENERATED (MWil) 1733023.20 8499117.60 306080941.40

10. GROSS ELEETRICAL ENERGY GENER ATED (MWil) 565786.00 2769667.00 99188757.00 i1. NET ELECTRICAL ENERGY GENERATED (MWil) 542626.00 2661344.00 93536856.00

12. REACTOR SERVICE FACTOR 100.00 98.49 78.98

13. REACTOR AVAILABILTTY FACTOR 100.00 98.49 80.83

14. UNIT SERVICE FACTOR 100.00 97.91 76.61

15. UNTT AVAILABILITY F ACTOR 100.00 97.91 77.10

_10. UNIT CAPACITY FACIOR (Using MDC) 94.84 95.52 65.65

17. UNIT CAPACITY FACTOR (Using Design MWe) 92.44 93.10 63.99

18. UNTT I ORCED OUTAGE R ATE 0.00 2.09 5.73

19. SilUTDOWNS SCIIEDULED OVER NEXT 6 MONT115 (FYPE, DATE, AND DURATION OF EAC}f);

20. IF SIIUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

f-ORECAST ACllIEVED INITIAL CRITICALITY INTTIAL ELECTRICTTY

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1 COMMERCl AL OPERATION 1.10-9 TitHOP3nNRC. MONTHLY.RFTg

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APPENDIX C l

OPERATING DATA REPORT DOCKET NO.. 50 265 UNTT Two DATE May 1,1993 f

i COMPLLTED BY Matt Benson TELEPIIONE (309) 654-2241 OPERATING STATUS t

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0000 050193

l. REPORTING PERIOD: 2400 053193 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX > DLPEND> CAPACITY: 769

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DESIGN ELECTRICAL RATINO ${We-NLT): 789

3. IOWER LEVEL TO WillCH RESTRICTED (IF ANY)(MWe-Net): N/A

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4. REASONS FOR RESTRICTION (IF ANY):

THis MONTH YR TO DATE CUMULATIVE i

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5. NUMBER OF HOURS REACTOR WAS CRTTICAL 99.60 1491.20 140666.45 6 REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 2985.80 i

7. IlOURS GENERATOR ON LINE 66.70 1423.50 137064.95 I

8. UNTT RESERVE SHUTDOWN llOURS 0.00 0.00 702.90 1

9. GROSS TilERM AL ENEROY GENERATED (MWH) 57844.80 3368196.00 296031605.20

10. GROSS ELECTRICAL ENERGY GENERATED (MWH)

- 15921.00 1100582.00

- 95126143.00

11. NET ELECTRICAL ENERGY GENERATED (MWil) 9239.00 1043021.00 90073764.00 i,

12. REACTOR SERVICE FACTOR 13.39 41.16 76.57 i

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13. REACTOR AVMLABILITY FACTOR 13.39 41.16 78.19 4

14. UNIT SERVICE FACTOR 8.97 39.29 74.61 j

15. UNIT AVAILAB!!JTY FACTOR 8.97 39.29 74.99

16. UNTT CAPACfrY FACTOR (Uning MDC) 1.61 37.44 63.76 l

17. UNIT CAPACTTY FACTOR (Using Design MWe) 1.57 36.49 62.14

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18. UNIT FORCED OUTAGE RATE 34 67 14.38 7.85

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19. SliUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE, AND DURATION OF EACH):

I 2 IF SHUTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP:

21. UNTTS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED i

INITIAL CRITICALITY

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INITIAL ELECTRICT"Y COMMERCIAL OPERATION j

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 10-254 UNIT.One-DATE June'3. 1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH May 1993 DAY AVERAGE DAILY POWER LEVEL IJAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)-

1.

727 17.

704 2.

585 18.

714 3.

698 19.

765 4.

728 20, 738 5.

763 21.

719 6

708 22.

716 7.

732 23, 702 8.

780 24.

739 9.

705 25.

-729 10, 719 26, 701 11, 723 27.

708-i 12, 782 28.

697 13.

785 29.

767 14, 751 30.

785 15.

767 31, 779 16.

689 INSTRUCTIONS On this form, list the average daily unit power level in MWe Net for each day-

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in the reporting month.

Ccapute 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.

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may be occasions when the daily average power level exceeds the 100% line (or

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the restricted power. level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

1.16-8 TM1 TOP 3WRCAtON'DILY.RPT

i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO 50-265 UNIT. Two DATE June 1.

1993 COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MONTH May 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I

(MWe-Net)

(MWe-Net) 1.

-8 17

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2.

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-8 19.

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-8 6.

-8 22.

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7

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-8 8.

-8 24.

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-8 25.

-8 l

10.

-8 26.

-8 11.

-8 27.

9 12.

-8 28.

137 I

13.

-8 29.

294 14.

-8 30.

162 15.

-8 31.

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INSTRUCTIONS

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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 raonth. 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.

1.16-8 DKMOPJ S RCMONNLY,RM j

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.30-254 UNIT HAHE One COMPLETED BY Matthew P,enson CATE June 3, 1993 REPORT HONTH May, 1993 TELEPHONE 309-654-2241 oc N

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CORRECTIVE ACTIONS / COMMENTS NO.

DATE (HOURS) 8 Load Drop Per Chicago Load Dispatcher 93-09 05-01-93 S

5.3 F

5 93-10 05-02-93 S

31.9 F

5 93-11 05-04-93 S

5.4 F

5 93-12 05-06-93 S

7.0 F

5 93-13 05-07-93 S

5.9 F

5 93-14 05-09-93 5

8.8 F

5 93-15 05-10-93 S

5.8 F

5 93-16 05-11-93 S

6.1 F

5

?3-17 05-14-93 S

4.6 F

5 93-18 05-15-93 S

1.5 F

5 93-19 05-16-93 S

9.5 F

5 93-70 05-17-93 S

5.8 F

5 93-21 05-18-93 5

7.7 F

5 93-22 05-20-93 S

5.5 F

5 93-23 35-21-93 S

6.4 F

5 93-24 35-22-93 5

7.7 F

5 93-25 35-23-93 S

8.6 F

5 93-26 15-24-93 5

5.8 F

5 93-27 15-25-93 S

6.3 F

5 93-28 15-26-93 S

6.5 F

5 93-29

)3-27-93 S

7.4 F

5 93-30 15-28-93 S

7.9 F

5 93-31 15-29-93 S

3.4 F

5

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VI.

UNIOUE REPORTING REOUIREMENTS i

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

A.

Main Steam Relief Valve Operations Relief valve operations during the reporting period.are summarized in the l

following table. The table includes information as to which relief valve E

was actuated, how it was actuated, and the circumstances resulting in its actuation.

i Unit: Two Date: May 27, 1993 1

Valve Actuated:

No. & Tvoe of Actuation:

2-203-3A 5 Relief Valve Actuations 2-203-3B 2-203-3C 2-203-3D

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Plant Conditions: Startup from Q2R12, Rx. Press.'930 psi

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Descriotion of Events:

Post Maintenance and Normal Surveillance Testing.

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Control Rod Drive Scram Timina 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.

t' 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 i

performed with reactor pressure greater than 800 PSIG.

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' s RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 &2 CONTROL ROD DRIVES, FROM 01/01/93 TO 12/31/93 AVERAGE TIME IN SECONDS AT %

MAX. TIME IN3ERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION NUMBER 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 (Averace Scram Insertion Timg) 01-28-93 1

0.30 0.67 1.42 2.15 H-12 For Accumulator Replacement 2.15 02-12-93 1

0.33 0.72 1.54 2.77 D-5 Accumulater Replacement U2 Q05404 2.77 02-26-93 1

0.32 0.69 1.46 2.61 K-7 Scram Inlet valve'U2 Q05593 2.61 05-28-93 177 0.32 0.705 1,49

-2.60 D-9 U2 Start Up Scram Timing Q2R12 3.47 l

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' NRC/SCRMTIME.FRM

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l VII.

REFUELING INFORMATION

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i 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 l

Request for Pefueling Information", dated January 18, 1978.

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n TirHOPLNRC\\ MONTHLY.RPT 1

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I QTP 300-532-Revision 2 QUAD CITIES REFUELING-October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

12 Cycle:

13 2.

Scheduled date for next refueling shutdown:

-)

09-24-94 1

3.

Scheduled date for restart following refueling:

12-04-94 i

4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

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NOT AS YET DETERMINED.

5.

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

NOT AS YET DETERMINED.

t 6.

Important licensing considerations associated with refueling, e.g., new l

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

NONE AT PRESENT TIME.

s 7.

The number of fuel assemblies.

+

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool.:

2583 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

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9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:2009 t

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APPROVED' (final) 14/0395t ggg O.C.O.S.R.

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1 QTP 300-532 1

Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

01 Reload:

12 13-Cycle

2.

Scheduled date for next refueling shutdown:

3-14-94 3.

Scheduled date for restart following refueling:

6-13-94 3

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 licensing action and supporting information:

NOT AS YET DETERMINED

[

6.

Important licensing considerations associated with refueling, e.g., new r

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

160 GE10' Fuel Bundles will be loaded during Q1R13.

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7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1557 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 i

planned in number of fuel assemblies:

a.