Text

Monthly Operating Repts for Dec 1992 for Quad Cities Nuclear Station,Units 1 & 2
	ML20127B944
Person / Time
Site:	Quad Cities
Issue date:	12/31/1992
From:	Michael Benson, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-93-01, GCT-93-1, NUDOCS 9301130225
	Download: ML20127B944 (25)
	v • d • e

G' e

Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Corcova, lilinois 61242 Telephone 309/654-2241 GCT-93-01 January 4, 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 DockeL No W O-254 and 50-263 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 December 1992.

Respectfully, COMMONHEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION lddk Is l

Gerald C. Tietz Technical Superintendent l

I l

GCT/MB/dak l

Enclosure cc:

A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector in"g8gn ggagg;,,

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PDR

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I QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT i

f l

December 1992 l

COMMONWEALTH EDISON COMPANY l

AND IONA-ILLINOIS GAS & ELECTRIC COMPANY l

l NRC DOCKET NOS. 50-254 AND 50-265 B

LICENSE NOS. DPR-29 AND OPR-30 l.

l l

- T814

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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, Experiments, and Safety Related Maintenance 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 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 h

VIII.

Glossary i

TS 14

t I.

IRIRODUCHON Quad-Cities Nuclear Power Station is composed of two Boiling Hater 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 construction contractor was United Engineers & Constructors.

The Mississippi River is the condenser cooling water source.

The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor criticalities for Units One and Two, respectively were 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 309-654-2241, extensions 2995 and 2240.

T$ 14

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9 II. SUMMARLOF OPERAUNG EXPERIENCE A.

Unll_Qan Quad Cities Unit One ended its refuel outage Q1R12 by bringing the reactor critical at 2110 hours0.0244 days 0.586 hours 0.00349 weeks 8.02855e-4 months on December 14, 1992.

The generator was synchronized to the grid at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months on December 16.

The unit had been off line since the start of Q1R12, on September 20, 1992.

During December, Unit One reduced load twice on orders from Chicago Load Dispatch (CLD).

The first reduction was on December 24, to 500 MWe, and the second was on December 28, to 340 MWe.

The only other reductions of more than 20% power on unit one were to 290 MWe on December 29 in order to re-null the thrust bearing wear detector on the main turbine, and the 550 MWe on December 31 for monthly turbine testing.

B.

Unit Two Quad Cities Unit Two was on line for the entire month of December.

A back wash and precoat of the condensate demineralizers caused a load drop to 650 MWe on both December 2 and 28. A monthly test of the main turbine, performed on December 13, required a load drop to 600 MWe.

Seven additional load drops, of more than 201 power, were ordered by the CLD during the month of November for Unit Two.

Each of these power reductions are listed below:

f-DATE POWER 12/07/92 600 MWe 12/17/92 600 MWe 12/18/92 650 MWe L

12/20/92 600 MWe 12/23/92 550 MWe 12/24/92 600 MWe 12/25/92 493 MWe l-12/28/92 650 MWe l

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III.

11ANL0fLERQC.E 0VR E_ CHANG E S..J E. SIS._EXE ERIM ENIS.

ANCLSAFEILRELATE0JiAINTENANCE A.

Ame nduleRt s_t ol0 C Hity.11cen s e ALle c hnic a LS RO CiflC a110ns There were no Amendments to the facility License or Technical Specifications for the reporting period.

B.

facility _or Etocedure_ Changes _ Requiring _HRCJ pprotal There were no facility or Procedure changes requiring NRC approval for the reporting period.

In accordance with Technical Specification Section 6.8,0,1, Revision 0 K has been made to the Offsite Dose Calculation Manual (ODCM) on s

December 28, 1992.

Information to support the change, and documentation that the change has been On-Site and off-Site review approved is included in On-Site Review Report No. 92-54.

C.

Jests-and_Exper.iments_Requirjng_NRCJpproval There were no Tests or Expe-iments requiring NRC approval for the reporting period.

D.

Corre c t1reJ!aint enan ce_oLSafely_ Relate d...Eq uipment 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.

T114

. ~.

UNIT 1 MAINTENANCE

SUMMARY

WORK REOU EI SYSTEM EID DESCRIPTION HORK PERFORMED QO3037 7800 Replace TIP channel #1 drive Replaced circuit breaker.

circuit breaker Q03213 5700 Fabricate upper and lower head Made new covers and replaced old ones.

covers for 1B core spray room cooler.

l Q03257 7800 Repair Ul MCC 18/19-5 cubicle F2 Found local. green indicating light l

Reactor water recirc manifold missing its outer lock nut. Replaced crosstle valve.

local green indicating light.

l 003408 1700

' Troubleshoot Ul "B" main steam Installed new chassis.

j line log rad monitor.

l l

QO3410 8100 Repair cracked contractor coil in Replaced old coil with new coil.

MCC 18-1A cubicle A2.

003510 8100 Replace overload on breaker in New overload relay was installed and MCC 18-1A cubicle B2 for passed test requirements.

l M0-1-1001-186A.

003549

302,

. Repair scram discharge volume Extensive troubleshooting was flow'controlLindicator level performed. The problem disappeared l

switches.

after reassembling the circuit boards. A water drip from the CRD's.

is the suspected cause of the original alarm.

Q03557 330 Repair stripped threads on CR'D Removed stripped nut and welded on a grid work.

new nut.

003650 1200 Replace snap ring on ISI. hanger Found the external retaining ring 120Z-M110.

missing. A new retainer ring was installed.

003653 1000 Cut out RHRSH valve upstream from Removed valve and replaced with a new 1A heat exchanger.

valve.

TS 15

. ~.

UNIT 1 MAINTENANCE

SUMMARY

HORK REQUEST SYSTEM EID DESCRIPTION WORK PERFORMED 003832 6700 Replace broken counter on 4kV horizontal magneblast breaker.

Removed old counter and installed a (NEN #001) new one.

Q03849 7800 Replace defective ring tongue Replaced ring tongue terminal with new terminal on Ul 202-6B cubicle D4 ring tongue.

MCC 18/19-5.

003916 1700 Repair U1 signal isolator for Installed a new signal isolator and SJAE offgas computer point.

calibrated.

003947 203 Replace ruptured diaphragm on IC Replaced disc.

main steam line safety valve.

003948 203 Replace ruptured diaphragm on 10 Replaced disc.

main steam line safety valve.

Q03949 203 Replace ruptured diaphragm on ID Replaced disc.

main steam line safety valve.

Q03992 756 Repair LPRM 16-09B power supply.

Found blown fuse.

Replaced fuse and adjusted power supply to the procer 3

voltage.

004055 6700 Replace missing position Replaced position indicator spring.

Indicator spring on 4kV horizontal magneblast breaker.

(NEN #064)

Q04064 7800 Replace breaker in MCC 18-1A Installed new circuit breaker and cubicle D3 main steam line drain repaired splice.

valve lA.

004158 1000 Realign U1 1001-42D limit switch

-Realigned limit switch.

for ID RHR pump CCST suction valve.

TS 15

i INIT 1 MALNIENMCE SUMMA _RJ 3

HORK RE00EST SYSTEM EID DESCRIPTION HQRK PERFORMED Q04176 7800 Replace transformer lead splices Splices were cut out and' taped.

Motor in MCC 18-1A-cubicle G2 for 1/2 starter and auxiliary contacts were DG vent fan.

replaced.

Q04193 6700 Replace missing position Replaced position indicator spring.

l Indicator spring on 4kV horizontal magneblast breaker.

(NEN #105)

Q04284 202 Troubleshoot and repair Found blue conductor of cable #12499-Limitorque 1A recirc pump suction not landed at MCC 18/19-5 cubicle 81 valve.

terminal 8.

Landed blue conductor at correct terminal.

Q04370 901 Find and fix hard ground in Found knife switch SHS in the 901-34 I

annunciator cabinet 901-34.

panel door 4F had a lug on the bottom shorted to a mounting screw. Knife switch SH5 was relocated and ground cleared.

Q04459 7100 Replace switchgear cubicle 4A Breaker was replaced.

480VAC feed to MCC 18-2.

Q47759 8300 Replace battery cell #9.

Replaced battery cell #9 and #10.

I Q78927 4600 Repair 1-4699-203 and 1-4699-204 Replaced the valves with new ones.

l valves.

Q79246 7800 Repair HCC 19-1 cubicle H2 RNCU Replaced the cracked coil with a new pump 18.

one.

l

.TS 15

UNIT-1 MAINTENANCE

SUMMARY

HORK REOUEST

$1SIEM EID DESCRIPTION HORK PERFORHED

-Q79819 3900 Repair 1/2 Diesel generator Replaced valve and nipple.

cooling water header drain valve.

i Q89350 8350 Repair or replace terminal strip The terminal strip was replaced with a and plastic dividers for MCC like part.

240VDC for 2301-5.

090254 1001 Repair RHRSH heat exchanger flow As found:

Body and disc exhibited control valve.

damage from cavitation. Stem was bent beyond use.

Body had pits. Anti rotational pin was bent on both ends and was tight'against. slots which prevented the valve from fully closing. As Left: Disassembled valve body.

Installed new trim and stem.

Belzond valve body at pitted areas.

Packed valve with graphoil set and spacer set stroke. Reassembled valve and verified operation.

Q90680 2300 Repair HPCI testable check valve Replaced sealtite from check valve to solenoid.

junction box ITB95. Also replaced 45 degree connector and installed all bolts in junction box.

Q90964 202 Repair or replace sealtite for Removed broken sealtite and replaced Limitorque 18 recirc pump suction with new sealtite'and fitting. Also valve.

. installed cover bolt.

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LLCENSEE_1RNLREEORIS 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 6.6.8.2 of the Technical Specifications.

UNilj Licensee Event RepotLNumber Dale Iltle_oL0ccurrence 92-029 10/29/92 111 Rad Door Propped Open Consealing Posting Sign 92-030 12/13/92 IB Recirc PP tripped during A05 Logic Test 92-032 12/21/92 Admin requested commitments for-fire protection not met UNIL2 There were no Licensee Event Reports for Unit 2-for this reporting period.

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DAIA_IABUL&11011S 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 TS 14

APPENDIX C OPERATING DATA REPORT DOCKET NO 50-E5.4 UNIT Dpe DATE J anuArLQ 4._.1993___._

COMPLETED BY tia1LDerson TELEPHONE 1302)._554-2241 OPERATING STATUS 0000 120192

1. REPORTING PERIOD: 14Q0 12319L GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 1h11 MAX. DEPEND. CAPACITY: 169 DESIGN ELECTRICAL RATING (HWo-Net): 2D9

3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe Net): tyA 4 REASONS FOR RESTRICTION (If ANY):

TH.'S HON 1H YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL...

410J_

__h2_492B_

14116h9_

.Q1 02D._

.1421 1 6 REACTOR RESERVE SHUTDOWN HOURS.....

7. HOURS GENERATOR ON LINE......,,

3ZL3_

____616015._

_ 13S391,1

8. UNIT RESERVE SHUTDOWN HOURS..................

0.Q_

QA 90.92L

9. GROSS fHERMAL ENERGY GENERATED (MWH)....

_693191 2_

13514000J 2971610ZLB_

10. GRDSS ELECTRICAL ENERGY GENERATED (MWH).

223MLL

_4344I54 D 3M19E9LQ_

2

11. NET ELECTRICAL ENERGY GENERATED (FMI)...

_11D1D010_

4166144.0 99DZ551LD_

12. REACTOR SERVICE FACTOR.........

5L22 71d5 78.59 5L22 71.15 30 41

13. REACTOR AVAILABILITY FACTOR..

14. UNIT SERVICE FACTOR.

E0 2 10113 7hilS

15. UNIT AVAILABILITY FACTOR...................

50J1 70 d1 76 68 1

16. UNIT CAPACITY FACTOR (Using MDC) 36J3 6L60 6h05

17. UNIT CAPACITY FACTOR (Using Design MWe) 35 99 60 2 63.40

18. UNIT FORCED OUTAGE RATE.......

OdQ 7.81 5162

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

20. IF SHUTDOWN AT END OF REPORT PERIOD. ESTImTED DATE OF STARTUP:

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION To u 1.16-9

APPENDIX C OPERATING DATA REPORT DOCKET NO E0-Zb5 i

i UNIT Jyo DATE lanuLryJ4. 19.23 COMPLETED DY ttailftmon TELEPHONE 1101LM4-ZZ41 OPERATING STATUS 0000 120192

1. REPORTING PERIOD: _24AQ JZ319L GROSS HOURS IN REPORTING PERIOD: _144

2. CURRENTLY AUTHORIZED POWER LEVEL (PMt): 1511 MAX, DEPEND CAPACITY: 169 DESIGN ELECTRICAL RATING (HWe-Net): IS9

3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (HWe-Net): N/A

4. REASONS FOR RESTRICTION (If ANY):

THIS MON 1H YR TO DATE CUMULATIVE

5. NUMDER OF HOURS REACTOR WAS CRITICAL....

744.0A

_.M9L15

_._.139175.15

6. REACTOR RESERVE SHUTDOWN HOURS

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0.Q_

?9B5JQ

7. HOURS GENERATOR ON LINE,.....

744.00 5621.55 135641d5

8. UNIT RESERVE SHUTDOWN HOURS.............

O (L 0.0_

702.90 t

9. GROSS THERMAL ENERGY GENERATED (HWH)..

1811916.00 1Z5795Z3120 Z22163439,20

10. GROSS ELECTRICAL ENERGY GENERATED (HWH).....

J9M19,QQ 40.95aZh00 9AD2516h00

11. NET ELECTRICAL ENERGY GENERATED (MWH)......

_ 171571.00 3a9EE6aJD

_B203.014L00

12. REACTOR SERVICE FACTOR...

100.00 64J1 77.28

13. REACTOR AVAILABILITY FACTOR.....

100.0L 64.81 78a4

14. UNIT SERVICE FACTOR.............................

10Qa0..

64.00 75JZ

15. UNIT AVAILABILITY FACTOR.....................

1QQJQ_

64 QQ

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16. UNIT CAPACITY FACTOR (Using MDC) 99.9Q 57.69 64 22

17. UNIT CAPACITY FACTOR (Using Design HWe) 97 3L 56 2 6L66

18. UNIT FORCED OUTAGE RATE 0.0 Oa 7 18

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

20. If SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16-9 TS$4

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET N0 50-154 UNIT One DATE Jamlary _4m_1933 COMPLETED BY MaiLfenson TELEPHONE 13031.151-22.41 MONTH _Qttember_1332 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE-DAILY _P0HER LEVEL-(MHe-Net)

(MHe-Net) 1.

-8 17.

143 2.

-8 18.

157 3.

-8 19.

350 4.

-8 20.

454 5.

-8 21.

693 6.

-8 22.

771 7.

-8 23, 780 8.

-8 24.

768 9.

-8 25.

' 4S5 '

10.

-8 26, 702 11.

-8 27.

783-12.

-8 28, 721 l

13.

-8 29.

620 14.

-8 30.

654 15.

-8 31.

_126 16.

65 l

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. INSTRUCTIONS On this form, list the average daily unit power level in MHe-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 1007. 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 Ts i4 l-!-

i APPENDIX 0 AVERAGE DAILY UNIT POWER LEVEL DOCKEi NO 50465 UNIT Iwo DATE danuary 04. 1993 COMPLETED BY MatLDenton TELEPHONE 1102L651-2241 MONTH December _1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HHe-Net)

(HHe-Net) 1.

785 17.

151 2.

73 8 18, 763 3.

790 19.

786 i

4, 732 20.

138 5.

787__

21.

738 6.

789 22.

784 7.

753 23.

727 8.

790 24, 732 9.

789 25.

635 10, 790 26.

787 11, 790 27.

'_159 12, 783 28, 754-13, 739 29.

789 14.

777-30.

790 15.

186 31.

7fl8 16.

783 INSTRUCTIONS On this form,-list.the average daily unit power level in HWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

t These figures will be used to plot a graph for each reporting-month.

Note.

that when maxir m dependable: capacity is used for the net electrical rating of the unit, there ncy be occasions' when the daily average power level exceeds the.1007. 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, nu 1.16-8 4.

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APPENDIX D UNIT SHUTDCNNS AND POWER REDUCTIONS DOCKET NO.

050-265 UNIT HAME Unit one COMPLETED BY mthew F.enson DATE January 4, 1993 REPORT MONTH December 1992 TELEPHONE 309-654-2241 N Et 5

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CORRECTIVE ACTIONS / COMMENTS92-043 12/24/92 S

32.2 F

5 Load Drop per CLD 92-044 l'.'28/92 S

10.1 F

5 Load Drop per CLD 92-045 12/29/92 F

7.7 B

5 Null Thrust 13earin>; Wear Det ector 92-046 12/31/92 S

5.3 B

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t VI. UH10VEREPORIINGJE0VIREMENIS 1

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

A.

M a i n _S t e afrtReiji e Lya j y e _0p e r a t i on s Relief valve operations during the reporting period are summarized in the following table.

The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Un1.t :

One Date:

!2/16/92 YA1Yes ACtVated No4_LIype_oLActua tion 1-203-3A Post Maint. on Start-up from Q1R12 1-203-3B 1-203-3C 1-203-3D l-203-3E Plant _Conditiora:

Start-up Descr_lptim_oLEvent s :

Rx Press 920 psig D.

ControLRotDrive_ScranLIJming Datador_ Units _0ne_and_Jwo The following-table is a complete suamary of Units One and Two Control Rod Drive Scram Timing for the reporting period.

All scram timing was performed with reactor pressure greater then 800 PSIG.

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT JJ_2 CONTROL i

ROD DRIVES, FROM 1-1-92 TO 12-31-92 AVERAGE TIME IN SECONDS AT %

MAX. TIME i

INSERTED FROM FULLY HITiiDRAWN FOR 90%

INSERTION DESCRIPTION NUMBER 5

20 50 90 Technical Specification 3.3.C.1 &

I OF_.R0QS 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 (Average Scram Insertion Time) f DATE F

i 2-19-92 2

0.28 0.67 1.43 2.48 J-2 Drive Replacement (J-2), Scram Valve N-7' k

j-2.55

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8 2-20-92 1

0.32 0.69 1.45 2.45 N-5 Scram Valve Hork N-5 i

-2.45 i

I 5-12-92 177 0.31 0.69 1.47 2.58 L-13 Start-up Scram Timing Unit Two i

1.43 i

t' i

f 6-02-92 1

0.31 0.65 1.37 2.30 N-5 Scram Valve Work 2.35 6-26-92 2

0.27 0.62 1.32-2.32 C-13 ACCUM C-13, N-7 I

2.26 i

7-13-92 88 0.28 0.63 1.35 2.36 K-13

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

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QTP 300-532 Revision 2 QUAD CITIES REFUEL!NG October 1989 INFORMATION REQUEST 1.

Unit:

01 Reload:

12 Cycle:

13 2.

Scheduled date for next refueling shutdown:

3-14-94 3.

Scheduleo uste 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 licensing action and supporting information:

NOT AS YET Dt.TERMINED 6.

Iinportant 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.

I 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 planned in number of fuel assemblies:

Licensed storage capacity for spent fuel:

3657 a.

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 (fi"* D 14/0395t

-l-OCT 3 01989

-I o.c.c.S.R.

o QTP 300-532 Revision 2 QUAD CITIES ?EFUELING October 1989 INFORMATION k'E0 VEST 1.

Unit:

02 Reload:

11 12 Cycle:

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:

NOT AS YET DETEPJilNED.

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 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:

?430 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:

Licensed storage capacity for spent fuel:

3897 a.

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

( '

)

14/0395t

-l_

OCT 3 01989 O.C.O.S.R.

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