ML20046D153

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Monthly Operating Repts for Jul 1993 for Quad-Cities Nuclear Station,Units 1 & 2.W/930802 Ltr
ML20046D153
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 07/31/1993
From: Michael Benson, Scott A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-93-03, AMS-93-3, NUDOCS 9308160219
Download: ML20046D153 (25)
v • d • e


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.. *1; Commonwrith Edison Quad Cities Nuclear Power Station

' 22710 206 Avenue North Corcova, lilinois 61242 Telephone 309/654-2241 AMS-93-03 1

August 2, 1993

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 l

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 ,

Monthly Performance Report NRC Docket Nos. 50-254 and 50-265  ;

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 July 1993.

Respectfully, COMMONWEALTH EDISON COPJANY QUAD-CITIES NUCLEAR POWER STATION f

Anthony M.-Scott System Engineering Supervisor AMS/dak Enclosure cc: J. Martin, Regional Administrator T. Taylor, Senior Resident _ Inspector noionWRrMONm13.RPT

/f g 9309160219 930731 .F j PDR ADDCK 05000254 PDR 0.60026

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QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 [

MONTHLY PERFORMANCE REPORT 1

JULY 1993 COMMONWEALTH EDISON COMPANY  ;

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IOWA-ILLINOIS GAS & ELECTRIC COMPANY

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NRC DOCKET NOS 50-254 AND-50-265 r

e LICENSE NOS. DPR-29 AND DPR-30 I

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TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience f 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 e C. Tests and Experiments Requiring NRC Approval 'l D. Corrective Maintenance of Safety Related Equipment f

IV. Licensee Event Reports V. Data Tabulations '!

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions .

i VI. Unique Reporting Requirements .

A. Main Steam Relief Valve Operations

k VII. Refueling Information F

VIII. Glossary

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I. INTRODUCTION

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Quad-Cities Nuclear Power Station is composed of two Boiling Water f t

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 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 1 i

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 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 Matt Benson and Debra Kelley, telephone number l

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309-654-2241, extensions 2995 and 2240.

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i II.

SUMMARY

OF OPERATING EXPERIENCE .

t A. Unit One '

f Quad Cities Unit One began the month of July 1993 shutdown as repairs continued on the HPCI system. (For information on HPCI problem see I June issue of this report.)

  • s On July 20, at 07:44 hours, the reactor was made critical. The 3 generator was synchronized to the grid at 06:18, on July 21 and the  ;

unit was brought to full load on July 23. l Two load drops were performed on orders from Bulk Power Operations  !

(BPO). The first was on July 30, to 650 MWe, and the second was on July 31, to 500 MWe.

B. Unit Two Quad Cities Unit Two began the month of July 1993 shutdown as change {

out of the main transformer continued. (For more information on the a main transformer problem see June issue of this report.)

)

The unit was made critical at 22:12 hours on July 8, but was manually  ;

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SCRAMMED at 11:04 on July 7. The shutdown was required because HPCI was inop due to level switch leads on the drain pot were reversed. l On July 11, at 02:23, the reactor was again made critical and the generator was synchronized to the grid at 18:17 hours on July 12. On July 15, at 20:29, the reactor was manually SCRAMMED to allow for maintenance on condensate piping.

On July 25, at 19:19 hours, the reactor was made critical and the ,

generator was synchronized to the grid at 20:45 on July 26. The unit remained on line at approximately 25% power through the end of the month.

TinlOP3 NRCMoNTELY.Rrr

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PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, III.

AND SAFETY RELATED MAINTENANCE l i

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 Recuirino NRC Accroval l i

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

i C. Tests and Erperiments Recuirino NRC Approval I There were no Tests or Experiments requiring NRC approval for the 6 reportii., period.

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

Repetition.

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l UNIT 1 & 1/2 MAINTENANCE

SUMMARY

NWR# SYSTEM . EPN#' WORK REQUESTED WORK PERFORMED 002689 6600 1/2-6699- Repair diesel generator Found circ pump suction check 146 lube oil circ pump. valve loose and leaking.

Installed new check valve. ,

i Q04789 6600 .1/2-6662 Reinstall diesel Found valve installed backwards.

generator cooling water Removed and reinstalled in the expansion tank valve. correct direction.  !

Q05397 263' 1-263-72A Investigate and repair Fcund 2 cables landed at  !

lack of voltage on incorrect terminals. Lifted and reactor level ECCS relanded 2 cables at the correct switch. terminals.

Q06417 2000 1-2001-245B Investigate / repair Installed new pump.

cause of drywell equipment drain sump pump breaker trip.

Q08086 702 1-702-14 Repair IRM 14. Lubricated worm gear inside gear box and adjusted bearing tension.

Q08215 3700 1-3703 Investigate / repair Cleaned and lubricated valve cause of dual stem.

indication on RBCCW return from drywell outboard valve.

Q08256 . 6700 1-6704-15 Repair bus 14 cubicle Found auxiliary switch linkage

15. had fallen off and' operating arm was bent. Repaired and cleaned

-linkage and reinstalled in ,

cubicle.

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w r mies es- 9s; ele =--me---m4 wT '!w **h-m'emaam eau _ahshaueC*4Rtk-T et*u 9s '-=e* T a m mm W -st wwa 'er1.9<ee*p-4+-emt

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. d Q08314 6700 1-6705-1 Repair ground on 1/2 Found two wires pinched behind diesel generator to bus the upper door hinge. Installed -

13-1 breaker. splices for the wires and ensured

  • wires would not get pinched in door again.

Q08331 300 1-305-129 Repair / replace Installed new switch, accumulator level switch.

Q08335 7500 1/2-7509A Replace charcoal- Installed new filters, adsorber trays. Failed methyl iodide analysis.

Q08355 6600 1/2-6641- Investigate cause of Installed a new switch and ran CPS diesel engine trip on diesel from no load to full load.

high crankcase pressure Readings were found acceptable.

10-20 seconds after starting.

Q08528 1000 1-1001-47 Inspect and repair Overhauled valve and replaced shutdown cooling bearings.

suction header downstream stop valve.

Q77688 7800 1-78194-A2 Replace bad SBGT fan Replaced transformer.

control transformer with a new one.

Q93110 7500- 1/2-7506B Replace defective SBGT- Replaced flingers.

E fan motor shaft flingers.

- Q95247 7500 1/2-7506B Replace grease fittings Found Chevron grease and Mobil 28 on "B" SBGT fan motor. mixed together. Removed and with grease plugs. replaced motor rotor and bearings. Balanced rotor.

Reassembled and filled with Chevron grease only.

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' Q96845' 7500 1/2 7506B Install missing washers Installed missing washers and on SBGT fan motor skid. tightened all bolts.

Q97799 6600 1/2-6601 Remove / reseal diesel Removed overspeed trip device, generator overspeed installed a new frequency' ,

trip housing drain generator gasket, adjusted the sleeves. RH2 pot from 771 to 814 rpm, and .

reinstalled trip device.

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UNIT 2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q01082 1000 2-1053-H Replace test fittings Replaced fittings.

2-1053-J on RHR pump discharge pressure switches.

QO3761 300 2-305-111 Repair leaking nitrogen Removed all leaking valves, charging valves on replaced seat and o-rings, and various HCU's. cleaned internals.

Q05249 1000 2-1001-198A Investigate cause of Found broken vire while cleaning alarm not received when switch contacts Repaired

  • expected. broken wire.

006754 1000 2-1000 Repair plugged RHR Removed, repacked, and 2-1001-154A crosstie drain valve reinstalled valves. Also loosed 2-1001-155A line. 3 pipe hangers downstream of 154A valve and cleaned debris out of piping.

Q07019 201 2-201-JP7 Repair / replace damaged Found beam retainer missing on 2-201-JP8 reactor recirc jet pump jet pump #7 and #8. Replaced

  1. 7 and #8. and tack welded set screw on jet .

pump #7.

Q07344 1700 2-1705-3A Repair / replace "A" SJAE Sent chassis to vendor for log rad monitor. repair.

Q07534 220 2-220-85A Repair outboard MSIV Installed new check valve.  ;

accumulator check valve.

Q07919 2400 2-2402A Repair 2A CN4 post Replaced SV-2 solenoid. Cleaned accident H2/02 monitor. both H2 and O2 meters.

Q08000 2300 2-2369 Replace HPCI turbine Replaced switch with a new one.

exhaust steam drain pot mercury level switch.

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1 l Q08228- 2400 2-2406-B Adjust local and remote Calibrated control room i H2 meters. Local recorder.

indicates 0% in drywell, control room indicates 5%.

Q08389 3900 2-3906 Investigate / repair Replaced stem and operator on  :

broken handwheel on valve, diesel' generator cooling water heat exchanger inlet valve.

008390 3900 2-3907 Investigate / repair Replaced stem and reassembled broken handwheel on operator on valve.

diesel generator cooling water heat exchanger inlet valve.

Q08396 2300 . 2-2303 Repair HPCI gland seal Switch was exercised 15-20 hotwell pump level times. Exercise eliminated switch. problem.

Q08501 8300 2-8350 Repla.~e U-2 250VDC Removed U-2 breaker and batter charger output installed U-1/2 breaker.

breaker with U-1/2 breaker.

Q08520 220 2-220-44 Repair 2B recirc loop Replaced solenoid diaphragm with upstream sample stop a new high temperature silicone valve. Valve failed diaphragm.

closed.

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l; IV. LICENSEE EVENT REPCRTS I i

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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 -l the reportable occurrence reporting requirements as set forth in sections l 6.6.B.1 and 6.6.B.2 of the Technical Specifications. [

UNIT 1 t Licensee Event Report Number Date Title of occurrence  ;93-000 07-12-93 Non-conservative settings on Ry Bldg and Fuel pool ARMS.93-009 07-12-93 Both SBGTs INOP.  !

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93-010 07-20-93 HPCI INOP after failing to meet flow reqairements. [

UNIT 2  ;

Licensee Event  !

Report Number Date Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period.  :

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V. DATA TABULATIONS l 4

The following data tabulations are presented in this report:

-1 l A. Operating Data Report

  • B. Average Daily Unit Power Level ,

C. Unit Shutdowns and Power Reductions

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t APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNIT One DATE August 5,1993 COMPLETED BY Matt Bens <m TELEPHONE (309) 654-2241 OPERATING STATUS 0000 070193

1. REPORTING PERIOD: 2400 073193 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWr): 2511 M AX > DEPEND > CAI ACITY: 769 ,

DESIGN ELECTRICAL RATING (MWe-NET): 789 t

3. POWER LEVEL TO WHICH RESTRICTED OF ANY) (MWe-Net): N/A i
4. REASONS FOR RESTRICTION (IF ANY):

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THIS MONTH YR TO DATE ' iMULATIVE -

5. NUMBER OF HOURS REACTOR WAS CRITICAL 256.30 4285.20 147046.10
6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90
7. HOURS GENERATOR ON LINE 233.70 '4240.30 142631.90
8. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 909.00
9. GROSS THERMAL ENERGY GENERATED (MWH) 5145 % .60 10013023.20 307594847.00 f
10. GROSS ELECTRICAL ENERGY GENERATED (Mu11) 164386.00 3259141.00 99678231.00 f
11. NLT ELECTRICAL ENERGY GENERATED (MWH) 151088.00 3119794.00 93995306.00 -p
12. REACTOR SERVICE FACTOR '

34.45 84.24 78.74

13. REACTOR AVAILABILTTY FACTOR 34.45 84.24 80.58
14. UNIT SERVICE FACTOR 31.41 83.36 76.38
15. UNIT AVAILABILITY FACTOR ' 31.41 83.36 76.87
16. UNIT CAPACITY FACTOR (Using MDC) 26.41 79.75 65,45 '
17. UNTT CAPACITY FACTOR (Using Design MWe) 25.74 77.73 63.80 1
18. UNrf FORCED OUTAGE RATE 68.59 16.64 6.18
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): r FORECAST ACHIEVED ,

1 INTrlAL CRrrICALITY INITIAL ELECTRICrrY r

COMMERCIAL OPERATION I LW9 TIGOPINRC%f0NTELY.RI'T

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APPENDIX C OPERATING DATA REIORT  !

DOC}IT NO. 50-265 ,

UNU Two  ;

DATE August 5,1993 i COMPLETED BY Matt Benson  ;

TELEPHONE (309) 654-224I i OPERATING STATUS ,

0000 070193

1. REIORTING PERIOD: 2400 073193 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZEDIOWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTIT: 769 l DESIGN ELECTRICAL RATING (MWe-NET): 789 l
3. POWER LEVEL TO WHICH RESTRICTED GF ANY)(MWe-Net): N/A >

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4. REASONS FOR RESTRICTION OF ANYh  !

THis MONTH YR TO DATE CUMULATIVE 5, NUMBER OF HOURS REACTOR WAS CRITICAL 275.70 2055.70 141230.95 i

6. REACTOR RESERVE SHUTDOWN } LOURS 0.00 0.00 2985.80 f

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7. HOURS GENERATOR ON LINE 197.30 1896.30 137537.75

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8. UNTT RESERVE SHUTDOWN llOURS 0.00 0.00 702.90
9. GROSS THERMAL ENERGY GENERATED (MWH) 142953.60 4060353.60 296723726.80 *
10. GROSS ELECTRICAL ENERGY GENERATED (MWIT) 33283.00 1310388.00 953356d9.00 l
11. NET ELECTRICAL ENERGY GENERATED (MWH) 24718.00 1231615.00 90262358.00
12. REACTOR SERVICE F ACTOR 37.06 40.41 76.27
13. REACTOR AVAILABILITY FACTOR 37.06 40.41 77.88
14. UNIT SERVICE FACTOR 26.52 37.28 74.27 l
15. UNTT AVAILABILITY FACTOR 26.52 37.28 74.65
16. UNTT CAPACITY FACTOR (Uning MDC) 4.32 31.48 63.38 ,

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17. UNTT CAPACITY FACTOR (Uning Der.ign MWe) 4.21 30.69 61.78 '

I8. UNIT FORCED OITTAGE RATE 73.48 39.35 8.44 f I

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

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20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

i FORECAST ACHIEVED INITIAL CRITICALT1Y INTTIAL ELfrTRICITY COMMERCIAL OPERATION rm  ;

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AVERAGE DAILY UNIT POWER LEVEL ;i DOCKET NO 50-254  :

UNIT One {

DATE Auoust 5, 1993 COMPLETED BY Matt Benson j TELEPHONE -(309) 654-2241 .

MONTH July 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' ,.

(MWe-Net) (MWe-Net)-  !

1. -9 17. -11
2. - 9 18. -11 1
3. - 9 19 -11 -

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4. -9 20. -32
5. -9 21. 82 -

64 - 9 22. 114

7. - 9 23. 213
8. -9 24. 771 l

779

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9 25 i

775

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10 - 8 26.

11. -30 27 776' i A

i l'2 -. -12 28. 776  !

13. - 9 29. 776 i

14 - 9 30. 735 l

15. - 9 31. 695 i t

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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 L will-be.used to plot a graph for each reporting month. -Note that,when maximum. l

[- dependable-capacity.is used for the net electrical rating'of the unit, there.

O 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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\VERAGE DAILY UNIT POWER LEVEL  :

d DOCKET NO 50-265 I UNIT Two  !

t DATE- Aueust 5. 1993  :

COMPLETED BY Matt Benson ,

TELEPHONE (309) 654-2241' j MONTH July 1993 t

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY' POWER LEVEL  ;

(MWe-Net) (MWe-Net) d

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1. - 9 17. ' 10
2. - 9 18. -10 l 1
3. - 8 19. -10
4. - 8 20. -11
5. -9 21. -10 ,
6. - 8 22. -9 '
7. -

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23. - 9 3
8. - 8 2 4 '. - 9 l
9. - 9 25. --9 '
10. - B 26. 8
11. -10 27. '120 .
12. 13 28, 202-
13. 109 29 187'  ;
14. 116 30. 107

-15. 97 31. 188

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-INSTRUCTIONS .

On this form, list the. average daily unit power leve1~in MWe-Net for.each day-in the. reporting month. Compute to the nearest'whole megawatt. These figuresL ' l will be used to' plot a graph for each^ reporting month. . Note'that1when 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- -f the restricted power level line) ; . ' In such cases, the. average daily unit power - >

output sheet shouldLbe footnoted to explain the apparent' anomaly. ,

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APPENDIX D .[

UNIT SHUTDOWNS AND POWER REDUCTIONS

.i' DOCKET NO. 50-254 ITAIT NAME One COMPLETED BY Matt Benson i

DATE Autrust 4, 1993 REPORT MONTH July. 1993 TELEPHONE 309-654-2241  !

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m$ LICENSEE 8 DURATION EVENT CORRECTIVE ACTIONS /COMMEITTS NO. DA'IE (HOURS) REPORT ,

93-45 07411-93 F $10.3 B 4 ------ --- ---

HPCI Repair Cutinued From Last Month

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93-46 07-3043 s 9.5 F 5 ------- --- --- load Drop Per Bulk Power Operations 9347 07-31-93 $ 6.8 F 5 ------- --- --- Imad Drop Per Bulk Power Operations  ;

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS ,

1 DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Matt Benson f i

DATE liuoust 5. 1993 REPORT MONTH July, 1993 TELEPHONE .309-654-2241 f e

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E8 m 28 mSE LICENSEE 8  ;

DURATION EVENT CORkECTIVE ACTIONS /CO1WENTS NO. DATE (HOURS) 8  ;

REPORT 9M9 07-12-93 F 282.3 B 4 -

Continued Main Transformer Repair from 'I last Month - ,

f 93-10 07-15-93 F 264 4 B 2 Coraienute Pipe Maintenance o

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VI. UNIOUE REPORTING REOUIREMENTS -

The following items are included in this report based on prior commitments to f the connission:

A. Main Steam Relief Valve Ooerations Relief valve operations during the reporting period are summarized in the 'l following table. The table includes information as to which relief valve  !

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

actuation.

I Unit: One l l Date: July, 20, 1993 I  ;

i Valve Actuated: No. & Tvoe of Actuations i

1-203-3A Normal Surveillance -

1-203-3B Post Maintenance l L 1-203-3C 3 i

1-203-3D 1-203-3E (Twice) e Plant Conditions: 920 psig Rx. Pressure  !

Descriotion of Events: All valves. tested on startup. 3E tested twice to .!

properly seat.

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Date: July, 26, 1993 l t

Valve Actuated: No. & Tvoe of Actuation 1 t

1-203-3B Normal Surveillance - f Post Maintenance

- Plant Conditions: 920 psig Rx. Pressure  ;

f Descriotion of Events: All valves tested on startup.

~l B. 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 .l and 4 3.C.2.  !

The following table is a complete summary of Units One and Two Control' Rod l'

Drive Scram timing for the' reporting period. All scram timing as performed with reactor pressure greater than 800 PSIG. 'I i

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.RESULTS OF SCRAM TIMIWG MEASUREMENTS

PERFORMED ON UNIT 1 & 2 CONTROL . .E ROD DRIVES, FROM 01/01/93 TO 12/31/93 ,

AVERAGE TIME IN SECONDS AT 1 MAX. TIME -

INSERTED FROM FULLY WITHDRAWN FOR 90tr INSERTION DESCRIPTION NUMBER 5 20 50 '90 Technical Specification 3.3.C.1 & .i DATE -OF RODS 0.375 0 900 2.00 3.5 7 sec. 3.3.C.2 (Averace Scram Insertion Time) 01-28-93 1 0.30- 0.67 l'.42 2.15 H-12 For Accumulator Replacement ,

2.15

.02-12-93 1 0.33 0.72. 1,54 2.77 D-5 Accumulator Replacement U2 Q05404 2.77 02 26 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

  • 07-13-93 4 'O.33 0.73 1.51 2.60 D-9 For WR Test Q08085 Q07146 2.69 U2 Q08364 Q07147

'07-23-93 90. -0.31 0.69- 1.45 2.53 D-8 U1 SEQA & Q08229 3.4

.07-29-93 l' O.32 0.71 1.51 2;66 F-10 U2 Q00629 Accumlator 2.66 .

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VII. REFUELING INFORMATION 1

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The following information about future reloads'at Quad-Cities Station was  !

requested in a January 26, 1978, licensing merrorandum (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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OTP 300-532

' Revision 2 QUAD CITIES REFUELING October 1989

, INFORMATION REQUEST

1. Unit: ol Reload: 12 Cycle: 13
2. Scheduled date for next refueling shutdown: 3-14-94
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 subeltting proposed licensing action and '

supporting information: ,

NOT AS YET DETERMINED

6. Important Itcensing 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: _

160 GE10 Fuel Bundles will be loaded during Q1R13.

7. The number of fuel assemblies. i
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 1557 l
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:

3657 .{

a. Licensed storage capacity for spent fuel:
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

l APPROVED i (final) 14/0395t 00T 3 01989 C).C.O.S.R. 4

j ..

QTP'300-532 o

- 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
3. Scheduled date for restart following refueling: 12-04-94
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 licensing action and supporting information: ,

NOT AS YET DETERMINED. -

6. Important Ilcensing 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: 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 stort.ge: 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 14/0395t NE Q.C.O.S.R.

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VIII. GLOSSARY ~

The following abbreviations which may have been used in the Monthly Report, are defined below:

{

ACAD/ CAM - Atmospheric Containment Atmospheric

  • Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute -

-L APRM - Average Power Range Monitor f

ATWS - Anticipated Transient Without Scram _j BWR - Boiling Water Reector l CRD - Control Rod Drive  !

EHC I

- Electro-Hydraulic Control System EOF - Emergency Operations Facility GSEP - Generating Stations Emergency Plan .,

HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System j HRSS - High' Radiation Sampling System }

IPCLRT - Integrated Primary Containment Leak Rate Test j IRM

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- Intermediate Range Monitor ISI - Inservice Inspection LER - Licensee Event Report

  • LLRT - Local Leak Rate Test -'

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

MAPLHGR - Maximum Average Planar Lineak 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 and Health ~l PCI - Primary Containment Isolation .

PCIOMR - Preconditioning Interim Operating Management Recommendations [

RBCCW - Reactor Building Closed Cooling Water System r RBM - Rod Block Monitor l RCIC - Reactor Core Isolation Cooling System f

RHRS - Residual Heat Removal System  !

RPS - Reactor Protection-System I RWM - Rod Worth Minimizer SBGTS . Standby Gas Treatment System :i SBLC - Standby-Liquid Control f SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge. Volume' '

f SRM - Source Range Monitor

.TBCCW - Turbine Building Closed Cooling Water System .[

TIP_ -Traversing Incore Probe '

TSC . Technical Support' Center I J

70 CHOP.%NRC'. MON'n!LY.RPT I l

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