ML20070D974

Monthly Operating Repts for June 1994 for Quad Cities Nuclear Station Units 1 & 2

ML20070D974
Person / Time
Site:	Quad Cities
Issue date:	06/30/1994
From:	Moore K, Scott A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-19, NUDOCS 9407130243
Download: ML20070D974 (24)

Text

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. s Comm:nwe lth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 AMS-94-19 July 7, 1994 U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC Docket Nos. 50-254 and 50-265 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 June 1994.

Respectfully, I

Comed j Quad-Cities Nuclear Power Station '

hfYW Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc . J. Martin, Regional Administrator C. Miller, Senior Resident Inspector T1 CHOP 3\NRC\ MONTHLY.RPT I 9407130243 940630 5

-1S00f7 goa aoock N"n"

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT June 1994 l

COMV.0FWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY

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l NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

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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. Amer.dments 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 i

VIII. Glossary j TirHOP3\NRC\ MON 11tLY.RIT

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I. INTRODUCTION 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 Unite 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 Kristal Moore and Debra Kelley, telephone number 309-654-2241, extensions 3070 and 2240.

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SUMMARY

OF OPERATING EXPERIENCE j i

A. Unit One Quad Cities Unit one spent the entire month of June 1994 shutdown in Refuel Outage Q1R13. The scheduled startup for Unit One is July 28, 1994.

B. Unit Two Quad Cities Unit Two began the month of June 1994 at full capable load (780 MWe) until a load drop to 565 MWe occurred on June 13, due to a high temperature on the 2A Recirc Pump Motor upper guide bearing. The unit was brought back to full power the next day. On June 21, at 1405 a manual scram was initiated due to Electro-Hydraulic Control (EHC) fluid leaks at #2 control Valve which caused a forced outage. The reactor was made critical at 1633 on June 27, but the generator was not on-line until 0545 on June 28. A Turbine overspeed test was performed at 1024 and synchronized to the grid at 2135 the same day.

A second manual scram occurred on June 29, at 0356 due to high acetylene readings in Transformer 22. The unit remains down for repairs.

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TECHOP31NRC\ MONTHLY.RPT

III. FJJJ'L,QJLEROCEDURE CllAfiQKam TESTB. EXPERIMEU h h@_JhffJY RELATED MAINIZHMiCX A. hmRad'annts to Facilitv Ligenna_.or_Inchn12A1.13RRalf1EAL1Qat Technical Specification Amendment No. 146 was issued on June 10, 1994 to Facility Operating License DPR-29 and Amendment No. 142 to Facility operating License DPR-30 for Quad Cities Nuclear Power Station. The amendments increase the Minimum Critical Power Ratio (MCPR) from 1.06 to 1.07 for Quad Cities Nuclear Power Station, Units 1 and 2, as a result of the planned implan.2ntation of GE DX8ND-3 fuel for Cycle 14 of each unit.

Technical Specification Amendment No. 147 was issued on June 16, 1994 to Facility Operating License DPR-29 an<t Amendment No. 143 to Facility Operating License DPR-30 foe Quad Cities Nuclear Power Station. The amendments propose to revise Technical Specification l 3/4.6 for Quad Cities station to allow Single Loop Operation (SLO) with the recirculation loop suction and discharge valves open.

D. [ Agility or ProcRdgLR_ShBagfuLEnggirina NEC Acoroval Thero were no Facility or Procedure changes requiring NRC approsal for the reporting period.

C. 12RLA Ani h pSrimRDie Roauirino NMC ApRroval There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Carrnctivo Maintanance of SAInty_En1RtRILE2uipmtak The following reprocents a tabular summary of the major safety related maintenance performed on Units One and Two during the reperting period. Thle summary includes the following: Work RoqueAt Numbers, system Component Dameription and work performed.

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UNIT 1 & 1/2 MAINTENANCE SUyNARY

.w NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 003465 1100 1-1101-15 Repair Unit.1 standby liquid Replaced valve disc and ,

control to reactor check valve. disc guide. Lapped in

._ body surfaces.

Q04090 1100 1101-16 Repair Unit 1 standby liquid Replaced valve disc and control injection line check disc guide. Lapped in valve. body seats.

Q08468 0261 1-0261-30C Replace udssing cover gasket on Installed a new gasket.

the 30C pressure switch.

Q11636 0325 1-8325-1A1 Replace corroded cell lug Replaced 7 lug 1-8325-1A2 connectors on 24/48 VDC connectors.

1-8325A battery.

Q13460 6600 1-6601 Repair numerous oil leaks on Replaced flexible hose, diesel generator piping, gaskets, and affected P i ping.

Q14547 0263 1-263-55A, Repair reactor vessel hi Replaced needle valves, B, C, D pressure switch isolation tubing, and associated valves. hardware.

Q14983 0756 1-0756- Troubleshoot / repair LPRM Did diagnostic work on 32-17D reading very low downscale. LPRM. LPRM will be rep? aced under another -

work request.

Q15762 0030 1-0030- Repair penetration due to Adjusted link seal.

MK507 leakage on both sides in RHR service water vault.

Q15864 0030 1-0030- Replace link seal on piping Replaced seal link.

MK475 penetration in RHR service water vault.

NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q15865 0030 1-0030- Repair link seal on RER service Replaced link seal.

MK476 water vault penetration.

Q15866 0030 1-0030- Repair link seal on CRD pit Replaced link seal.

MK483 floor penetration.

Q16115 1600 1-1600 Repair hole in torus bay 15 Weld repaired the hole.

spherical junction.

Q16181 0261 1-0261-34D Repair switch casing on jet Replaced differential pump riser header switch. pressure switch.

Q16190 0203 1-0203-3AA Replace insulation on wiring Installed new connector, for target rock bellows lugs, and new cable.

pressure switch. Reinstalled switch on valve.

Q16304 1600 1-1632-A Troubleshoot / repair cause of Replaced slave trip unit 1-1634-A failure to receive low gross and calibrated.

failure latch indication during surveillance of torus reactor differential pressure switch.

l l Q16332 1000 1-1005A Reinstall hanger on RHR service Adjusted link seal and l water penetration. reinstalled hangers as required.

Q16476 7200 , 1-7200-2A Recalibrate bus 19 r91ays found Adjusted relay. ,

out of tolerance.

Q16509 5200 1-5201 Repair diesel fuel oil transfer Installed valve taken pump discharge relief valve due frcm Unit 2. Wrote work to pump failure to reach rated request to repair valve flow. taken from Unit 1.

l Q16510 5200 1-5201 Repair / replace diesel fuel oil Replaced relief valve.

l transfer pump discharge relief valve.

e NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED G16521 6600 1-6601 Investigate / repair fuel Replaced leaking fuel dilution in the engine lube injectors.

oil.

Q16524 1700 1-1705-16B Investigate / repair 1B fuel pool Replaced indicator, trip 1-1743-B radiation monitor spiking high unit, sensor, and and tripping reactor building converter.

vents.

Q16770 6600 1-6601 Adjust diesel generator fuel Adjusted fucl. racks and racks and injector timing. injector timing with engine at operating temperature on all 20 cylinders.

Q90527 6700 1/2-6700- Repair 4kV breaker. Replaced circuit breaker 063 motor, secondary disconnect, contact fingers, push button switch, prop spring, and cup washer.

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UNIT 2 MAINTENANCE SUMERY NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED Q14781 1000 2-1001-164B Replace downstream drain for Replaced valve and RHR testable check valve. associated hardware.

Q15318 1000 2-1053-J Replace test taps for RHR pump Replaced tubing and test discharge pressure switch. tap fittings.

Q16531 0756 2-0750-10C Troubleshoot APRM #3 drift. Replaced contact block.

Q16722 0756 2-0756-6 Troubleshoot APRM #6 spiking Removed and reinserted hi-hi causing 1/2 SCRAM on RPS cards. Found and channel B. tightened loose mounting screws.

Q16753 0261 2-0261-69A Investigate / repair flow Replaced detector, detector acoustic monitor. accelerometer, preamplifier, and associated hardware.

Q16790 0755 2-0702-17 Troubleshoot / repair IRM 17 Replaced IRM detector.

erratic and spiking. _

Q16821 1700 2-1705-17 Replace loose connector on "C" Replaced connector, main steam line log rad monitor.

Q16843 5650 2-5650-3 Repair conduit elDow Det. ween Replaced conduit washer conduit and local junction box and returned the switch for EHC low pressure trip to service.

switch.

IV. LICENSEE EVENT REPORTS 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.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report Number Date Title of occurrence There were no Licensee Event Reports for Unit 1 for this reporting period.

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

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V. DATA TABULATIONS 1

The following data tabulations are presented in this reports l A. Operating Data Report l l

B. Average Daily Unit Power Level j C. Unit Shutdowns and Power Reductions 6

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APPENDIX C

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OPERATING DATA REPORT l DOCKLT NO. 50-254 UNrr One DATB July 7,1994 COMPLIrrED BY Kristal Moore TELEPHONE (309) 654-2241 OPI2ATING STATUS 0000 060194

1. REPORTING PERIOD: 2400 063094 GROSS HOURS IN REPORTING PIRIOD: 720

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

3. POWER LEVEL TO WillCil RESTRICTED (IF ANY) (MWs-Net): N/A

4. REASONS FOR RESTRICrlON (IF ANY):

N THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF IlOURS REACTOR WAS CRTTICAL 0.00 1706.00 151487.30

6. REACTOR RESERVE SiltfrDOWN llOURS 0.00 0.00 3421.90

7. IlOURS GENERATOR ON LINE 0.00 : 1682.90 146979.20

8. UNrr RESERVE SillrTDOWN llOURS 0.00 0.00 909.20

9. GROSS TilERMAL ENERGY GENERATED (M't.**I) 0.00 3865794.10 317558981.30

10. GROSS ELECTRICAL ENERGY OENERnTED (MWH) 0.00 1265145.00 102 % 3264.00

11. NLT ELECTRICAL ENERGY GENERATED (MWif) 0.00 1206708.00 97124706.00

12. REACTOR SERVICE FACTOR 0.00 39.28 77.78

13. REACTOR AVAILABILrrY FACTOR 0.00 39.28 79.54

14. UNrr SERVICE FACTOR 0.00 38.75 75.47

15. UNrr AVAILABILrrY FACTOR 0.00 38.75 75.93

16. UNrr CAPActrY FACTOR [Using MDC) 0.00 36.13 64.85

17. UNrr CAPACfrY FACTOR (Using Design MWe) 0.00 35.22 63.21

18. UNrr FORCED OtfrAGE RATE 0.00 1.33 6.25

19. SillTTDOWNS SCilEDULED OVER NEXT 6 MOVfils (TYPE, DATE, AND DURATION OF EACif):

20. IF SillTFDOWN AT ERO OF ?*"T PERIOD *' r. STIM ATED DATE OF STAkTUP: 7-28-94

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

Fo*ICAST ACillEVED INrrlAL CRITICALrrY INrrlAL ELECTRICITY ,

COMMERCIAL OPERATION 1.1&9 TirHOP3\NRC\ MONTHLY.RI'T i

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APPENDIX C OPEP ATING DATA REPORT DOCKET NO. 50-265 UNIT Two DATE July 7,1994 COMPLETED BY Krimal Mooro TELEPHONE (309) 654,2241 OPTRATING STATUS 0000 00194

1. REPORTING PERIOD: 2400 f. 3094 GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTilORitED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECTRICAL R, TING (MWe-NET): 789

3. POWER LEVELTO WHICH REST 1tlCTED (IF ANY)(MWe-Net): N/A

4. FEASONS FOR RESTRICTION (IF ANY):

Tills MONTH YR TO DATE CUMULATIVE

5. NUMBEJt OF llOURS REACTOR WAS CRTTICAL 529.00 3568.00 147469.05

6. REACTOR RESERVE SIIUTDOWN HOURS 0.00 0.00 2985.80

7. IIOURS GENERATOR ON LINE 504.80 3515.00 143698.15

8. UNTT RESERVE $11UTDOWN llOURS 0.00 0.00 702.90

9. GROSS TilERMAL ENERGY GENERATED (MWlO 1190163.50 8264655.90 311045617.80

10. GROSS ELECTRICAL ENEROY GENERATED (MW11) 376120.00 2672707.00 99982477.00

11. NET ELECTRICAL ENEROY GENERATED (MW10 360985.00 2564531.00 94707091.00

12. REACTOR SERVICE FACTOR 73.56 82.16 76.33

13. REACTOR AVAILABILTTY FACTOR 73.56 82.16 T7.88

14. UNTT SERVICE FACTOR 70.11 80.93 74.38

15. UNTT AVAILABILTTY FACTOR 70.11 80.93 74.74

16. UNIT CAPACTTY FACTOR (Using MDC) 65.20 76.79 63.75

17. UNTT CAPACTTY FACTOR (Uning Duign MWe) 63.54 74.84 62.13

18. UNTT FORCED OUTAGE RATE 28.40 18.86 8.82

19. SHIITDOWNS SCllEDULED OVER NEXT 6 MONTilS (TYPE, DATE, AND DURATION OF EACil):

20. IF $11UTDOWN AT END OF REPORT PTAIOD< FSTIMATED DATE OF STARTUP:

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

FORECAST ACHIEVED INTTIAL CRTTICALITY INTTIAL ELECTRICTTY ]

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APPENDIX B  !

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One

.DATE Julv 7, 1994 COMPLETED BY Kristpl Moore TELEPHONE f309) 654-2241 i MONTH June 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -8 17. - 8 l

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2. -8 18. - 8

3. -8 19. - 8

4. -8 20. - 8' 'I

5. -8 21. - 8 5

6. -8 22. -

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-7. -8 23. - 5

8. -8 2 4 . ___ - 4 ,

9. -8 25. - 5

10. -8 26. -

6

11. -8 27. - 7

12. -

8 28. - 8

13. -8 29. - 5

14. -8 30. -

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15. -8 31.

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. i 1.16-8 '

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL-4 DOCKET NO 50-265 UNIT Two i DATE July 7. 1994 COMPLETED BY Kristal Moore TELEPHONE (309)~654-2241 MONTH June 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)  !

1. 741 17. 735 i

2. 744 18. 730

3. 748 19. 728 4, 721 20. 729

5. 709 21. 411

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6. -743 22. -6

7. 744 23. -4

8. 731 24. -4

9. 744 25. -4 10, 749 26. -7 11, 742 27. 4

12. 739 28. 83 ,

13. 565 29. 35 j

14. 723 30. -3 ,

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15. 734 31.

16. 737 i

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 not electrical rating ~of the unit, there  !

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

1 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 D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET !IO. 50-254

UNIT NAME One COMPLETED BY Eristal Moore DATE Julv 7, 1994 REPORT MONTH June 1994 TELEPHONE 309-654-2241 m

n z OEh x $

, Em 8 a Na Wa no~ 8<M 08 2

$ e m g8

$ LICENSEE O DURATION EVENT CORRECTIVE ACTIONS / COMMENTS o

NO. DATE (HOURS) REPORT 9404 641-94 5 720.0 C 4 ---------- --- ---- Continued Refuel Outage QlR13 l

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 _

UNIT NAME Two COMPLETED BY Kristal Moore DATE July 7, 1994 REPORT MONTH Jgny 1994 TELEPHONE 309-654-2241 tr;

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M O my< M M B ta. l 9 4

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• LICENSEE DURATION EVENT CORRECTIVE ACTIONS / COMMENTS NO. 'DATE (HOURS) REPORT 9406 61394 F 14,3 A 5 ----.---- -. ...- load drop due to high tangerature of numer upper guide hearing on 2A Racia Pune.

9447 62194 F 159.6 A 2 -...--... ... ---- Manual Scram due to EllC Fluid laaks at #2 Cordrol Valve 94 68 62894 5 11,2 H -- -- -.. ... .--- Turbine Overspeed Test.

14 49 62994 F 44.4 A 2 --...---- --- -..- Manual Scram due to liigh Acetylens reading on T22.

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VI. UNIOUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

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

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

Maill TWO  !

Date June 28, 1994 Valve Actuated: No. & Tvoe of Actuation:

2-203-3A 1 Manual 2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual l

Plant Conditionst Reactor Pressure 920 peig Description of Events: Normal surveillance during startup of Unit 2.

l B. Control Rod Drive Scram Timina Data for Units One and Two l

l 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 l

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

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 01/01/94 TO 12/31/94 .

l l AVERAGE TIME IN SECONDS AT'%' MAX. TIME l l INSERTED FROM FULLY WITHDRAWN FOR 90s  !

! INSERTION ! DESCRIPTION

, NUMBER 5 1 20  ! 50  ! 90  ! l Technical Specification 3.3.c.1 & -

DATE OF RODS 0.375 ! O.900  ! 2.00 3.5 i

1  ! 7 sec.  ! 3.3.C.2 (Averace Scram Insertion Time) i  ! ,

l t 01-27-94 l 1 0.31 l 0.69 1.45 2.53 H-1 l U1 for Maintenance '

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01-29-94' 1 l 0.33 ,' 0.73 l 1.51 l

L 2.58 M-10 U1 for Maintenance l l 2.58 1 1 01-29-94 -177 l 0.32 1 0.69  :

l 1.46 2.56 ,

H-3 U2 SEQ A & B for Tech Spec & Maintenance l l 2.92 1 ,

.02-10-94 1 0.29 l 0.65 1.39 s 2.41 l F-7 l U1-F-7 for WR Q12855 1 ,

l 2.41 l I 1  !

02-19-94 1 0.31 'O.69 1.45 2.53 H-1 l U1 H-1 for WR Q14360 2.53 I .l l 02-23-94 1 0.30 0.68 1.45 2.62 .1 l '

J-3 l U2 J-3 for WR Q14662 4

2.62 06-28-94 7 0.31 0.69 1.45 2.54 2.67 U2 H-5, H-3, E-5, D-13, H-11, D-5 1

' L-3 for WR Q15111 SSPV I

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, 4 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 Information", dated January 18, 1978.

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QTP 300-532 ,

Revision 2 l QUAD CITIES REFUELING October 1989 1 INFORMATION REQUEST

1. Unit: 12 Q1 Reload: Cycle: 13 )

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

3. Scheduled date for restart following refueling: 7-28-94

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 GE10 Fuel.

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

11-19-93

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysts methods, significant changes in fuel design, new operating procedures:

144 GELO Fuel Bundles will be loaded during Q1R13.

7. The number of fuel assemblies.

a. Number of assemblies in core: 0

b. Number of assemblies in spent fuel pool: 2441

8. The present licensed spent fuel pool storage capacity and-the size of any increase in Itcensed storage capactty that has been requested or is '

planned in number of fuel assemblies: l

a. Licensed storage capacity for spent fuel: 3657 j

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b. Planned increase in licensed storage: 0 ,

9. The projected date of the last refueling that can be discharged to thh t spent fuel pool assuming the present Ilconsed capacity: 2006 i APPROVED I

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14/0395t OCT 3 01989 l C1.C.O.S.R.

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_, QTP 300-532 Revision 2

,. QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Reload: 12 13 Q2 Cycle:

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

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3. Scheduled date for restart following refueling: 4-9-95 1

4. N111 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.

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

7-28-94

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed' design or performance analysts methods, significant changes in fuel design, new operating procedures:

I 144 GE10 fuel bundles will be loaded during Q2R13.

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7. The number of fuel assemblies.

a. Number of assemblies in ccre: 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 Itcensed 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: 2006' l

APPROVED (final) 14/0395t M30W Q.C.O.S.R.

a VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined belows ACAD/ CAM - Atmospheric Centainment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Institutta APRM - Average Power Range Monitor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC -

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

High-Efficiency Particulate Filter HPCI -

High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT -

Integrated Primary Containment Leak Rate Test IRH - 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 HAPLHGR - Maxirnum 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 NIOSH - National Institute for Occupational Safety and Health 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 l

i RHRS - Residual Heat Removal System RPS - Reactor Protection System RWM -

Rod Worth Minimizer SBGTS - Standby Gas Treatment System SDLC -

Standby Liquid Control l SDC - Shutdown Cooling Mode of RHRS SDV - r, im Discharge Volume SRM - Source Range Monitor TBCCW - Turbine Building closed Cooling Water System i TIP - Traversing Incore Probe TSC - Technical Support Center T!DIOP3WRL%tONTHLY,RIT

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