Text

Monthly Operating Repts for Nov 1992 for Quad Cities Nuclear Power Station,Units 1 & 2
	ML20125E204
Person / Time
Site:	Quad Cities
Issue date:	11/30/1992
From:	Michael Benson, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-92-48, NUDOCS 9212160243
	Download: ML20125E204 (24)
	v • d • e

-

Commonwealth Edison ound Citiet Nuclear Power Station 22710 206 Avenue North Corcovs. lilinois 61242 Telephone 309/654 2241 GCT-92-48 l

l December 4, 1992 l

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

SUBJECT:

Quad Cities Nuclear Station Units I and 2 Honthly Performance Report NRC_ Docket Nos. 50-254 and 50.-lfi5 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 November 1992.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION C aul,/ C Q !p Gerald C. Tietz Technical Superintendent GCT/HB/dak l

Enclosure cc:

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

l l

l

.1000;;0 9212160242 921130

\\j ADOCKOS00g24 g

PDR R

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 HONTHLY PERFORMANCE REPORT November 1992:

CCHMONNEAL1rl EDISON COMPAM.

AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY.

NRC DOCKET NOS. 50-254 AND 50-265' LICENSE NOS. DPR-29 AND DPR-30 TS 14 j.

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 VIII. Glossary 4

TS 14

I.

1HIR0DUCIl0N Quad-Cities Nuclear Power Station is composed of two Bolling 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 Bolling Hater 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 Debre Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

T914

II. SUB8ARY OF OEEfM11tfG_EXEERIEEE A.

Valt_One Quad Cities Unit One continued with refuel outage 01R12 for the entire month of November.

The unit was taken off Itne September 20 and is scheduled to return to service on December 14.

B.

Un1LIxo Quad Cities Unit Two was ordered by the Chicago Load Dispatch (CLD) to reduce power to 600 MHe on November 1 and to 450 HWe on November 29. A test of the HSIV closure time, performed on November 14, required a load drop to 400 MWe. Unit Two was lowered to 208 MWe, on November 22, for an entry into the drywell.

CLD ordered Unit Two to drop to 600 MHe on November 26, but the subsecuent load increase was delayed due to problems with the condensate cemineralizers.

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

T914

III.

PLANT QLP_RQCEDURLCRMiGES. TESTS. EXPERIMENTS.

BiLSARILBELAIID_tWHIllMCE A.

&mendmenti_tQ_Ltc 111 t v L i c ense_pr TtchtlicLLSatc t f I c at t on s Technical Specification Amendment No. 139 was issued on November 4, 1992 to facility Operating License DPR-29 for Quad Cities Nuclear Power Station, Unit 1 The amendment reflects a modification to the High Pressure Coolant Injection turbine steam exhaust line.

The amendment adds the requirements for the new containment isolation valves which are part of the modification.

Technical Specification Amendment No. 140 was issued on November 12, 1992 to Facility Operating License No. DPR-29 and Amendment No. 135 to facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

The amendmenti delete from the Technical Specifications the isolation function and survelliance requirements for the Control Room Ventilation system chlorine and sulfur dioxide analyzer.

B.

Facility or Procedure Changes Reguirina NRC Anoroval There were no facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Experiments Regujritig NRC ADproy31 There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety RaltifL Equipment 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:

Hork Request Numbers, Licensee Event Report Numbers, Components, Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

TS 14

4 UNIT 1 MAINTENANCE

SUMMARY

HORK RE00EST SYSTEM EID DESCRIPTION NORK PERFORMED Q03519 8300 Repair Connections between cells Took apart affected connections then cleaned, on 125V DC Battery.

greased, and retorqued them.

Q88861 901 Repair cracked raceway on RPS bus Replaced raceway.

terminal strip protector on 901-15 panel.

Q94233 1000 Rewire Unit 1 RHR outboard Valve was rewired and the thermal overloads were injection valve 1-1001-288.

restored.

Thermal overloads were bypassed.

'Q98709

.2300 Repair HPCI pump inboard bearing As found: Sightglass and drain plug leaking. As oil leak.

Left: Removed and cleaned plugs and sightglass and installed new thread sealant.

001741 2500 Investigate and repair low Replaced light bulb.

pressure light on ACAD system pressure switch 1-2540-20.

Q01808

'756 Investigate and repair LPRM 32-41. Replaced circuit board with a new unit.

003038 7800 Replace Unit 1 MCC 18-1A overload Found the left overload relay cracked. Replaced relay.

the cracked relay.

Q03153 1000 Adjust indication for Unit 1 LPCI Found two conductors missing some insulation manual injection valve 1001-338.

Inside the local pull box next to the 1C limit switch. One conductor was broken. Installed a butt splice where the broken conductor was and wrapped tape around the other conductor.

QO3315 6700 Replace primary contact on Unit Found movable primary contact en 'C' phase was IA Core Spray Pump Breaker #17 bent. Replaced with a new contact.

TS 15

~

~~

UNIT 1 MAINTENANCE

SUMMARY

'HORK REOUEST

- SYSTEM EID DESCRIPTION HORK PERFORMED Q03376

- 8300 Locate and repair U1 125 VDC Found water.and sludge inside 1A and 3A limit ground.

switches for 203-2C outboard MSIV. Cleaned out j

water and sludge and replaced covers after drying. Ground cleared.

l

-QO3412'

- 6700 Replace insulating block on Unit

. Installed now insulation plate.

{

1 Bus 14-1 Cubicle 4 1D RHR pump Breaker #45.

l

.003548 0300 Calibrate CRD accumulator Replaced switch with a new one and calibrated the

[

pressure switch 42-55._

new switch.

'QO3635_

5200 Repair 1/2 Diesel Generator' Replaced pump with new fuel pump from stock and i

engine driven fuel pump.

reassembled all threaded pipe joints.

I l

078391 7800 Repair or replace cracked coils Removed old coils and replaced with new coils.

F on MCC 18-1B cubicle 63 1A RHR pump suction valve 1001-43A.

Q88547 7800 ReplaceLcoil on MCC 18-1B cubicle Found coil with a crack in it. Replaced coil with C1.

an new one.

Q88731 7800 Replace circuit breaker 25 in Breaker was found with cracks and chips with distribution panel #25.

pieces missing.

Installed new breaker and torqued

screws per GE instructions.

V Q88938 0901-Repair broken terminal strip in Removed broken block and replaced with a new one.

l i

901-17 panel.

e i

090206

- 1400 Rep;1r Essential Service Water Disassembled valve and performed a blue check of fill pump discharge to IB Core the seating surface. Reassembled valve, tested i

Spray suction valve.

operation, and left valve in closed position.

i i

3.

j l

1 TS 15

UNIT 1 MAINTENANCE

SUMMARY

~

HORK REOUEST SYSTEM EID DESCRIPTION HORK PERFORMED Q90243

'2500 Investigate'and repair if Installed a new *0* ring and cover. Cleaned up necessary terminal side of ACAD some corrosion on the terminal side of the drywell pressure transmitter transmitter. Disassembled the transmitter and 1-2541-Olla.

found no moisture present. Reassembled and calibrated the transmitter.

Q90352 2200 Replace valve handle and nut for Found handle gone. Replaced with a new handle.

j 1-2201-9 impulse drain line valve.

I Q92891 1000 Repair broken seal tight on Replaced seal tite.

1 Limitorque IB Core Spray Pump Suction Valve 1-1001-168.

1 4

i t

b r

[

l i

1 TS 15

~~

UNIT 2 MAINTENANCE SIM4ARY WORK RE00EST

. SYSTEM

.EID DESCRIPTION HORK PERFORMED 001743 2500 Investigate and repair ACAD air Replace light bulb.

receiver low pressure light.

003404 2300 Repack Unit 2 HPCI-' testable check Tightened packing nut. Leakage could not be valve 2-2301-7.

entirely stopped.

Q03411 0220

' Repair solenoid valve 2-220-45.

Found solenoid was bad. Replaced solenoid with a new one..

QO3486 8800

. Increase stroking speed of Unit 2 Found a couple of small leaks on the supply line Oxygen Analyzer valve 2-88010.

to the ASCO solenoid. Removed teflon tape and used pipe sealant to get rid of the air leaks.

Valve closed in approximately 2 seconds.

Q99756 0263' Calibrate narrow range reactor Calibrated both "A" and "B" Yarways and made water level Yarways.

slight adjustments. Slight adjustments were also made to the trip switches and signal converters.

TS 15 u__.

z.

l l

1-I i

IV.

LICElGELEYBLREEORIS i

The following is a tabular summary of all licensee event reports for 4

Quad-cities Units one and Two occurring during the reporting period, pursuant j

to the reportable occurrence reporting requirements as set forth in sections q

6.6.B.1 and 6.6.B.2 of the Technical Specifications.

)

There were no licensee Event Reports for Unit I and Unit 2 for this reporting period.

1 i

l l

1 e

1 l

l l

4 1

1 5

i TS 14

.~

. ~ -....

4 V.

DAIA_JABULAIl0liS 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 P

T814 -

APPENDIX C OPERATING DATA REPORT 1

DOCKET No 50_.2kt UNIT Qtte OATE Ettt!!!b1I Ad291 COMPLETED BY tiaLLBtoton TELEPHONE 11Q21_L54-2241 j

l l

OPERATING STATUS 0000 110192 i

1. REPORTING PERIOD: 1400 113_Q21_ GROSS HOURS IN REPORTING PERIOD: 720 l

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511___

HAX. DEPEND. CAPACITY: 59 DESIGN ELECTRICAL RATING (HWe-Net): 789 J

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

4. REASONS F0k RESTRICTION (IF ANY):

THIS HONTH YR TO DATE CUMULATIVE I

5. NUMBER OF HOURS REACTOR WAS CRITICAL...........

02L

__._5832dQ

....._1423$hlD

6. REACTOR RESERVE SHUTDOWN HOUd5..................

0.0.

0.L 3dZh9_

4

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

0.0_

5186,20 138017 32

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

0.0.

0.0 902,2_

9. GROSS THERNAL ENERGY GENERATED (HWH).............

O 0__

128HfDh6 196B0363ZdQ t

j

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

0.L

.4121111 0

.96195447.0 5

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

0,0_

32M4daiQ_

_90664012iL

12. REACTOR SERVICE FACT 0R...........................

0.Q.

72J2

_28J9

13. REACTOR AVAILABILITY FACT 0R......................

0.D_

7242 80 58 1

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

0.0 71.97 76.29

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

Qt0_

._ _ 71.97 76.79

16. UNIT CAPACITY FACTOR (Using HDC)................

0.0 63.98 65.17 4

17. UNIT CAPACITY FACTOR (Using Design HWe).........

0.Q_

62.35 63.52 f

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

0,0Q 8.34 SJ3

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:

12-14-92

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

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

.ww-Y

.k

<.yy y.--y.

w v.

y

-y*r- +.

~

'e' 7

APPENDIX C OPERATING DATA REPORT DOCKET HQ 59-Zf5 UN!1 Ira DATE Qtiember_4.1932 -

COMPLETED BY titiLBtrison TELEPHONE 13Q9) 654-2241 OPERATING STATUS 0000 110192

1. REPORTING PERIOD:.2400 113092. GROS $ HOUR $ IN REPORTING PERIOD:

720

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 tux. OEFEND. CAPACITY: 769 DESIGN ELECTRICAL RATING (HWe-Net): 289

3. POWER LEVEL TO WHICH RESTRICTED (!F ANY) (HWe-Not): N/A

4. REASONS FOR RESTRICTION (IF ANY):

THl$ HONTH 1R TO DATE CUHULATIVE

5. NUMBER OF HOUR $ REACTOR WAS CRITICAL............

720.00 4940255

_ 1.394 1 Z5

6. REACTOR RE$ERVE $HUTDOWN HOUR $..................

0.0 0.0 2985dQ

7. HOUR $ GENERATOR ON LINE.........................

_. 720200

__4S E 55 134891145

8. UNIT RI$ERVE $HUTDOWN HOUR $.....................

.DA 0.0 702 9A

9. GRO$$ THERHAL ENERGY GENERATED (HWH).............

1714790240 10lbl50Z120 2900514 & ZQ-

10. GROS $ ELECTRICAL ENERGY GENERATED (M41)..........

5b2827.0A 3499192,00 93429782.0A

11. NET ELECTRICAL ENERGY GENERATID (HWH)............

. 5431Z9202 1324997.00 80_459172 00

12. REACTOR SERVICE FACT 0R...........................

100,00_

61.55 77.J3

13. REACTOR AVAILABILITY FACT 0R......................

100.00 61.55 78.85

14. UNIT $ERVICE FACTOR.............................

100.00._

6DJ1 75.22

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

100.0D 60.62 75.61

16. UNIT CAPACITY FACTOR (Using HDC)................

98.17 53.70 64.14

17. UNIT CAPACITY FACTOR (Using Design HWe).........

95.68 52d2 62.51

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

0.0 0.0 7.82

19. $HUTDOWNS $CHEDULED OVER NEXT 6 HONTHS (TYPE. DATE. AND DURATION OF EACH):

20. If $HUTDOWt1 AT END OF REPORT PERIOD. ESTlHATED DATE OF STARTUP:

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16-9 79 14 1

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE De.Ctaber 4. 1992 COMPLETED BY Hatt_flenson TELEPHONE 1309L654-2241 HONTH _ROYember__1922 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(HWe-Net) 1.

-8 17.

-7 2.

-7

18...

-7 3.

-7 19.

-7 4.

-7 20.

-7 5.

-7 21.

-7 6.

-8 22.

-8 7.

_2 23.

-8 8.

-8 24.

--8 9.

-7 25.

-8 10.

-7 26.

-7 11.

-7 27.

-8 12.

-7 28.

-8 13.

-7 29.

-8 14.

-8 30.

-8 15.

-7 31.

16.

-7 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 1001. 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 l

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Iwo DATE Noy1mber 5. 1992 COMPLETED BY HatLBioson TELEPHONE (309) 654-2241 i

l HONTH HQYtmb.tr_1221

?

)

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(HWe-Net) 4 l

l 1.

725.

-17.

794 2

1 2.

713 18.

795

}

j 3.

790 19.

793 j

4.

779 20.

783 i

j 5.

~768 21.

776 i

j 6.

789 22, 426 l-7.

756 23, 742 I

l 8.

78.8 24.

776 1

9.

775 25.

-790 3

i

.10, 788 26.

633 j

i j

11.

767 27.

749

-12.

779 28, 767 13.-

792 29.

697 14.

681 30.

788 i-15.

789 31.

~

16, 793 e-f INSTRUCTIONS.

j i

On this form 11st:the average daily unit power level-in HWe-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 l

the unit, there may be occasions when the daily average-power level exceeds the 1001. 11ne (or the restricted power level line).

In such cases,--the i

average daily unit power output sheet should be footnoted to explain the apparent anomaly, va n --

1.16-8 j-I-

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APPENDIX D UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO.-

50-265 INIIT MAME Unit Two COMPLETED BY Mathew Benson November 1992 DATE December 4.

1992 REPORT N T"LEPHONE 309-654-224I k

h, @w M

M X

w w

o a

3 g8 g5

}

R LICENSEE DURATION E

EVENT E"

o" NO.

DATE (MOURS)

REPORT NO.

CORRECTIVE ACTIONS / COP 9 TENTS Load Drop per Chicago Load Dispatcher 92-85 11-01-92 S

7.4 F

5 92-86 11-14-92

.S 6.8 B

5 MSIV Closure Timing

^

Rod Shuffle /Drywell Entry 92-87

.11-21-92 S.

30.3 F

5 92-88 11-25-92 F

31.7 A-5 Load Drop per Chicago Load Dispatcher /

DEMI.N Probleras

~

Load Drop per Chicago Load Dispatcher 92-89 11-29-92 S

7.2 F

5 e (final)

VI.

URl0ULREEOR11RG_REQUlRWLttIS The following items are included in this report based on prior commitments to the commission:

A.

titilLSt e aln_ReiteLVAls e_0p ention s Relief valve operations during the reporting period are summarized in the following table.

The table includes information as to which relief va5ve was actuated, how it was actuated, and the circumstances resulting in its actuation.

URLt:

Two Qtte:

11/7/92 Vahes_ Actuated HomLIype_of_Ac tuatjon 2-203-3A Manual 2-203-3B Hanual 2-203-3C Hanual 2-203-30 Hanual 2-203-3E Manual Plant Conditioni:

Run Mode Dftirr.lation of Eveati:

Normal Semi Annual Surveillance B.

Control Rod Dr.tve Scram Timina Data for_Unj_ts_0ne 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.

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.

TS 14

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNTT 1 & 2 CONTROL ROD DRIVES, FROM 1-1-92 TO 12-31-92 AVERAGE TIME IN SECONDS AT 7.

MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 907.

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 (Average Scram Insertion Time) 2-19-92 2

0.28 0.67 1.43 2.48 J-2 Drive Replacement (J-2). Scram Valve N-7 2.55 2-20-92 1

0.32 0.69 1.45 2.45 N-5 Scram Valve Work N-5 2.45 5-12-92 177 0.31 0.69 1.47 2.58 L-13 Start-up Scram Timing Unit Two 3.43 6-02-92 1

0.31 0.65 1.37 2.35 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 2.26 7-13-92 88 0.28 0.63 1.35 2.36 K-13 Unit 1 "B" Sequence 2.79 7-22-92 1

0.29 0.64 1.36 2.41 D-2 127 Diaphragm D-2 Unit 2 2.43 11-22-92.

88 0.32 0.69 1.45 2.53 F-5 Unit 2 "B" Sequence 3.31 TS 75

VII. REEUEL1H U RE0RMAIl0N The following information about future reloads at Quad-Cities Station was

.x requested in a January 26, 1978, licensing memorandum (78-24) from O. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

T814

4 OTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 j

INFORMATION REQUEST i

1.

Unit:

of Reload:

12 Cycle:

12 2.

Scheduled date for next refueling shutdown:

o-20 o2*

Actual Shutdown at 0104 hrs.

3.

Scheduled date for restart following refueling:

12-14-92

)

4.

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

]

1.

Modification to HPCI turbine exhaust steam line.

f i

S.

Scheduled date(s) for submitting proposed licensing action and 4

supporting information:

)

1..

06/30/92

)

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 j

procedures:

}.

NONE AT PRESENT TIME.

l l

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 4

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:

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:

i APPROVED (final) 14/0395t OCT 3 01989 O.C.O.S.R.

QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1

Unit:

Q2 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 DETERMINED.

S.

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:

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 i

(final) 14/0395t OCT 3,01969 O.C.O.S.R.

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j VIII. GLOSSARY l