ML20065J028

Monthly Operating Repts for Mar 1994 for Quad-Cities Nuclear Power Station Units 1 & 2

ML20065J028
Person / Time
Site:	Quad Cities
Issue date:	03/31/1994
From:	Michael Benson, Scott A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-09, AMS-94-9, NUDOCS 9404150266
Download: ML20065J028 (22)

Text

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. Commonwealth Edison i I

Quad Cities Nuclear Power Station

( 22710 206 Avenue North Cordova, Illinois 61242

! Telephone 309/654-2241 1

AMS-94-09 i -

April 6,1994 l

l U.S. Nuclear Regulatory Commission ,

ATTN: Document Control Desk l Washington, D.C. 20555 l 1

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SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 l l Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 l

Enclosed for your information is the Monthly Performance Report covering the operztion of Quad-Cities Nuclear Power Station, Units One and Two, during the i month of March 1994.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

$YM u' Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc: J. Martin, Regional Administrator T. Taylor, Senior Resident Inspector nrnoP3WRCWONW1J.RFr 9404150266 940331

{DR ADOCK 05000254 PDR

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QUAD-CITIES NUCLEAR POWER STATION  ;

I UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT j March'1994 C0lWONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

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TFOIOP3\NitC\MONDILY.RPT l

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7 TABLE OF CONTENTS d

[ I. Introduction II. Summary of Operating Experience A. Unit One .l B. Unit Two l

i III. Plant or Procedure Changes, Tests, Experiments, and Safety Related 4 d

Maintenance i

-A. Amendments to facility License or Technical Specifications

8. Facility or Procedure Changes Requiring NRC Approval

, C. Tests and Experiments Requiring NRC Approval O. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports i

l V. Data Tabulations

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A. Operating Data Report

! B. Average Daily Unit Power Level

? C. Unit Shutdowns and Power Reductions I

VI. Unique Reporting Requirements i

A. Main Steam Relief Valve Operations l

B. Control Rod Drive Scram Timing Data

VII. Refueling Information i

Vill. Glossary

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1TCHOP3\NRC\ MON 1MLY.RPT i

I. INIR0DEIIM 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 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 l February 18, 1973 for Unit One and March 10, 1973 for unit Two.

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, i l 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 I

i A. Unit One I Quad Cities Unit One began the month of March 1994 in coast down as it approached the refuel outage. On March 13, refuel outage QlR13 was entered by tripping the turbine at 01:28 hours and manually scramming the reactor at 01:58 hours. The scheduled startup for Unit One.is  ;

July 4, 1994. I

! Two load drops were performed on request from Bulk Power Operations (BPO) and one for administrative reasons but none caused the average daily unit power level to drop by 20% or greater.

B. Unit Two l Quad Cities Unit Two began the month of March 1994 at full load and remained on line through out the month.

Numerous load drops were performed for administrative reasons but none j caused the average daily unit power level to drop by 20% or greater.

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TECHOPhNRC\ MONTHLY.RPT

l III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. l AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Snecifications  !

Technical Specification Amendment No. -145 was, issued' on March 11, 1994~

to Facility Operating License DPR-29 and Amendment No. 141 to Facility '

Operating License DPR-30 for Quad Cities Nuclear Power Station. .

The amendments consist of changes to the Quad Cities Technical .  ;

Specifications (TS) that will update the leakage test requirements.of l the Drywell Airlock to the standards of 10 CFR 50, Appendix J, Section  !

III.D.2. This ~is in response to an Unresolved Item listed in i Inspection Report Nos. 50-237/91032 and 50-249/91035.  !

l B. Facility or Procedure Chanaes Reauirina NRC Anoroval l There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Exneriments Reauirina NRC Anoroval There were no Tests or Experiments requiring i4RC approval for the

, reporting period.

D. Corrective Maintenance of Safety Related Eauinment 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, System Component Description and work performed.

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NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q14601 5700 1-5748B Investigate B core Changed set point on temperature spray room cooler TIC switches.

giving high temperature alarm in auto.

Q14768 2400 1-2419-D Repair torus CAM. Found bad relays in chassis.

Monitor indicates Replaced chassis.

failure downscale.

Q14980 6700 1/2-6700- Repair 1B RHRSW pump Replaced release latch monitoring 073 breaker. switch, cleaned and lubricated disconnects.

Q15014 7500 1/2-7500 Troubleshoot / repair B Exercised flow switch and checked SBGT failure to start calibration. Moved wiring to a in standby mode after slightly different location to time delay. allow freedom of movement for the bourdon tube.

Q15223 6700 1/2-6700 Repair 4kV breaker Repaired assemblies.

auxiliary switch assemblies.

Q15497 6600 1/2-6601- Repair overspeed trip Replaced missing cotter pin in OTLS limit switch. Arm has arm nut.

worked loose.

Q60908 6700 1-6706-10 Repair / reject diesel Rejected test linkage. New generator breaker. linkages will be installed.

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Breaker does not' actuate aux switch from the test position.

UNIT 2 MAINTENANCE

SUMMARY

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 001780 2400 2-2419-C Investigate / repair Repaired loose nut and bolt downscale alarm on heater connector. Calibrated local torus rad monitor.

monitor.

Q08028 0300 2-0305-126- Repair instrument air Replaced diaphraJm.

1847 leak on scram inlet valve.

Q08934 0756 2-0756- Troubleshoot / repair Ran I/V curve to correct 32-57 bypassed LPRM. problem.

Q10058 0750 2-0750-7A Troubleshoot / repair Ground cables were installed to 2-0750-7B IRM's drawing wide eliminate inadequate grounding 2-0750-7E bands on recorder. problem.

2-0750-7F Q13610 8350 2-8350 Replace cracked caps on Replaced flame arrestors on 250VDC flame arrestors. batteries 93 and 94.

Q13791 _ 2-1702 Investigate / repair Adjusted thermostat on monitor.

drywell CAM heat tracing.

Q13976 0300 2-0305-125- Repair leakby on scram Replaced accumulator, valve 3451 inlet valve. packing, seat ring, and plug.

2-0305-126- ~

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NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q14113 2200 2-2252-12 Replace broken cover Straightened sheet metal out and over diesel generator installed fasteners to secure exciter cabinet cover.

rectifiers.

Q14160 0300 2-0305-126- Troubleshoot / repair Adjusted seat pressure on scram 2639 cause of rod drifting inlet and outlet valve.

2-0305-127- past "00".

2639 Q14662 0300 2-0305-125- Repair HCU accumulator. Replaced accumulator, 0-rings, 3411 Accumulator failed to and charging " ort connector.

hold a nitrogen charge.

Q14771 2400 2-2402A Repair hydrogen meter. Replaced F,arogen analyzer cell, Meter will not span. catalyst bed assembly, regulator diaphragm, and soft seat nozzle.

Q14893 2300 2-2301-3 Adjust limit switch on Adjusted the open limit switch.

HPCI turbine steam supply isolation valve motor operatov Q14955 1000 2-1001-65A Repair 2A RHE Rebuilt inboard seal.

inboard seal .

Q15221 0756 2-0756-1 Repair APRM.#1. Cleaned edge connector on both Reading unexpectedly averaging cards.

increased from 97% to 99%.

Q15388 0756 2'0756-6 Troubleshoot / repair Cleaned connectors on both APRM #6 spiking high. averaging cards.

Q15405 7500 2-7503 Repair SBGT reactor Found tripper finger assembly building' inlet damper spring broken. Replaced motor.

valve.

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! IV. LICENSEE EVENT REPORTS i I l

l 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 ,

j the reportable occurrence reporting requirements as set forth in sections  !

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

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{ UNIT 1 i '

Licensee Event

' Report Nn=her Title of occurrence Data '

] 94-004 02-01-94 RCIC INOP when Trip Throttle Valve is j tripped. CANCELLED -

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!94-004 01-03-94 Feedwater flow loops reading i erroneously in the nonconservative  ;

i direction due to possible erosion or

] damage to the feedwater nozzles.or -

i instrumentation inaccuracy and  :

I calibration. , j e

j 94-005 03-14-94 1A'MSIV failed LLRT testing.

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i i Licensee Event .

Report Nn=her Qgig Title of occurrence There were no Licensee Event Reports for Unit 2 for this reporting period.

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

i A. Operating Data Report

! B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions l

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APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNTT Oas DATE April 6,1994 COMPl2TED BY Matt Berm.m TELEPHONE (309) 654-2241 OPERATING STATUS 0000 030194

1. REIORTING PERIOD: 2400 033194 GROSS HOURS IN REPORTING PERIOD: 744

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

3. POWER LEVEL TD WH]CH RESTRICTED (IP ANY) (MWe-Net): N/A

4. REASONS FOR RESTRICTION (IP ANY):

THIS MONTH YR1D DATE CUMULATIVE

5. NUMBER OF HOURS REACIDR WAS CRTTICAL 290.00 1706.00 151487.30

6. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 3421.90

7. HOURS GENERATOR ON LINE 289.50 1682.90 146979.20

8. UNTT RESERVE SHUTDOWN HOURS 0.00 0.00 909.20

9. QROSS THERMAL ENERGY GENERATED (MWH) 622185.60 3865794.10 317558981.30

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) 202713.00 1265145.00 102 % 3264.00

11. NET ELECIR] CAL ENERGY GENERATED (MWH) 190067.00 1206708.00 97124706.00

12. REACTOR SERVICE FACIDR 38.98 78.98 78.66

13. REACIOR AVAILABILTTY TACTOR 38.98 78.98 80.44

14. UNIT SERVICE FACIOR 38.91 71.91 76.32

15. UNTT AVAILABIIITY FACTOR 38.91 77.91 76.80

16. UNTT CAPACITY FACTOR (Uning MDC) 33.22 72.65 65.58

17. UNIT CAPACTTY FACTOR (Uning Design MWe) 32.38 70.81 63.92

18. UNTT FORCED OUTAGE RATE 0.00 1.33 6.25

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

20. IF SHUTDOWN AT END OF REPORT PERIOD < ESTDdATED DATE OF STARTITP: 7-4-94

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

FORECAST ACHIEVED INTTIAL CRTTICALTTY INTITAL ELECTRICTTY COMMERCIAL OPERATION 1.16-9 i

IIICHOP3\NRC\ MON'DiLY.RPT I

J APPENDDC C OPERATING DATA REPORT DOCKFrNO. 50-265 UNTT Two a

DATE April 6,1994 I

COMPIETED BY Matt Beeson TEIEPHONE (309) 654 2241 j OPERATING STATUS 0000 030194

, 1. REPORTING PERIOD: 2400 033194 GROSS HOURS IN REPOR11NG PER]OD. 744 4 3. CURRENTLY AUTHmrnn POWER IEVEL (MWt): 2511 MAX > DEPEND > CAPACfrY: 769 DESIGN ELECTRICAL RATING (MWe-NET): 789

3. POWER LEVELTD WHICH RE!rIRICIED(IP ANY)(MWe-Ne0: N/A

4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE d

5. NUMBER OF hlOURS REACIOR WAS CRTriCAL 744.00 1575.40 145476.45

6. REACIDR RESERVE SHUTDOWN HOURS 0.00 0.00 2915.80

7. HOURS GENERATOR ON LINE 744.00 1547.20 141730.35

8. UNTT RESERVE SHITrDOWN HOURS 0.00 0.00 702.90

9. GROSS THERMAL ENERGY GENERATED (MWH) 1801868.00 3583788.90 306364750.80

10. GROSS ELECIR] CAL ENERGY GENERATED (MWH) 586628.00 1164929.00 98474699.00

11. NET ELECIRICAL ENEIL'Y OENERATED (MWH) 563177.00 1111539.00 93254099.00 l ,

12. REACTUR SERVICE FACIDR 100.00 72.94 76.16

13. REACIDR AVAILAREJrY FACTOR 100.00 72.94 77.72

14. UNIT SERVICE FACTOR 100.00 71.63 74.20 j 15. UNTT AVAILABHJTY FACIDR 100.00 71.63 74.57

16. UNTT CAPACTTY FACIOR (Using MDC) 98.43 66.92 63.49 l 17. UNTT CAPACfrY FACTOR (Using Design MWe) 95.94 65.22 61.88 i

18. UNIT PORCED OtfrAGE RATE 0.00 28.37 8.81

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

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

21. UNTI3 IN TEST STATUS (PRIOR TO COMMERCLAL OPERATION):

PORBCA!rT ACHIEVED INTTIAL CRTrlCAIJrY I INTTIAL ELECIRICTTY COMMERCIAL OPERATION

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I APPENDIX B ,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 i UNIT One DATE April 6. 1994 COMPLETED BY Matt 8enson TELEPHONE (309)-654-2241 MONTH March 1994 DAY AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL  !

(NWe-Net) (MWe-Net)

1. 695 17. -8

2. 692 18. -8

3. 689 19. -8

4. 685 20. -8

5. 682 21. -8

6. 674 22. -8 ,

7. 674 23. -8 >

8. 673 24. -8

9. 665 25. -8

10. 669 26. -8

11. 665 27. -8 i

12. 598 28. -8  !

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13. -1 29. -8 l

14. -8 30. -8

15. -8 31. -8

16. -8 ,

INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the 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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! . l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 ,

UNIT Two )

DATE Anril 6. 1994 -

COMPLETED BY Matt Benson TELEPHONE (309) 654-2241-MONTH March 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER' LEVEL (MWe-Net) (MWe-Net)

1. 756 17. 756

2. 757 18. 757

3. 757 19. 758 I

4. 756 20. 752

5. 757 21. 740

6. 755 22. 756

7. 757 23. 757

8. 759 24. 767

9. 739 25. 768

10. 755 26. 746 l

11. 755 27. 761

12. 757 28. 760

13. 756 29. 763

14. 756 30, 762

15. 757 31. 762

16. 758 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the 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 TDCHOP3\NBC\MONDiLY.RPT

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME One COMPLETED BY Matt Benson DATE Acril 6. 1994 REPORT NONTH March TELEPHONE 309-654-2241 l l

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D, b 0 LICENSEE 2.0 DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT 9444 S1194 S 454.5 C 2 --------- --- -- Depa Refuel Outap Q1R13 l

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TECHOP3\NRC\ MONTHLY.RPT

4 APPENDIE D UNIT SHUTDCfdNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Two COMPLETED BY Matt Benson DATE Acril 6. 1994 REPORT MONTH March 1994 TELEPHONE 309-654-2241 2: 0@ N

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$ LICENSEE I DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT i

None for the month of March.

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VI. UNIQUE REPORTING RE0VIREMENTS The following items are included in this report Sased on prior commitments to the commission:

1 A. Main Steam Relief Valve Operations 1

There were no Main Steam Relief Valve Operations for the reporting period.

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] B. Control Rod Drive Scram Timina Data for Units One and Two There was no Control Rod Drive scram timing data for Units One and Two for the reporting period.

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VII. REFUELING INFORMATION 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 Infonsation", dated January 18, 1978.

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3 VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report,

are defined below:

ACAD/ CAM - Atmospheric Containment Atmospheric l Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institute i APRM - Average Power Range Monitor I ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive i EHC - Electro-Hydraulic Control ' System l l EOF - Emergency Operations Facility GSEP - Generating Stations Emergency Plan i HFPA - High-Efficiency Particulate Filter ,

i HPCI - High Pressure Coolant Injection System l HRSS - High Radiation Sampling System  ;

IPCLRT - Integrated Primary Containment Leak Rate Test l IRM - Intermediate Range Monitor

! ISI - Inservice Inspection j LER - Licensee Event Report ,

- Local Leak Rate Test LLRT i 4 LPCI - Low Pressure Coolant Injection Mode of RHRs ,

i LPRM - Local Power Range Monitor  ;

MAPLHGR - Maximum Average Planar Linear Heat Generation Rate  !

MCPR - Minimum Critical Power Ratio  !

MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concentration ]

MSIV - Main Steam Isolation Valve i s 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  ;

RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System j RPS - Reactor Protection System j RWM - Rod Worth Minimizer i SBGTS - Standby Gas Treatment System

SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System 1 TIP - Traversing Incore Probe

. TSC - Technical Support Center i

TBCHOP3WRCWONTHIJ.RPT 1

QTP 300-532 d - -

Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST i

1. Uni t: Q1 Reload: 12 4

Cycle

13 ,

2.  !

i Scheduled date for next refueling shutdown: 3-13-94

3. Scheduled date for restart following refueling

7-2-94 5

4. Will refueling or resumption of operation thereafter require a Technica'1' Specification change or other license amendment: -

YES. Safety Limit MCPR to be changed from 1.06 to 1.07 due to j GE10 Fuel.

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

• i 11-19-93 i

i 4 6. Important licensing considerations associated wtth refueling, e.g., new i

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

j 144 GE10 Fuel Bundles will be loaded during Q1R13.

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j 7. The number of fuel assemblies.

i I L a. Number of assemblies in core: 724 i

j b. Number of assemblies in spent fuel pool: 1557 i

! 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 1

planned in number of fuel assemblies:

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a. Licensed storage capacity for spent fuel: 3657 i

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b. 0 Planned increase in 11 censed storage. 2

9. The projected date of the last refueling that can be discharged to tho' "h i

spent fuel pool assuming the present licensed capacity: 2006 l*

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l APPROVED ,

(fi"*l)

14/0395t -I- DCT 3 01989 3

Q.C.O.S.R.

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Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q2 Reload: 12 Cycle: 13 1

2. Scheduled date for next refueling shutdown: 1-29-95

3. Scheduled date for restart following refueling: 5-21-95

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

YES - Safety limit MCPR to be changed from 1.06 to 1.07 due to GE10 Fuel.

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

7-28-94

6. Important licensing considerations associated with refueling, e.g., new 1

i or different fuel design or supplier, unreviewed design or performance '

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

GE10 Fuel will be loaded during Q2R13.

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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: 2583

8. The present Itcensed 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 i

b. Planned increase in licensec torage: 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2006 d

APPROVED ,

cfinai) 14/0395t DCT 3 0199 Q.C.O.S.R.

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