ML20062N540

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Monthly Operating Repts for Dec 1993 for Quad-Cities Nuclear Station Units 1 & 2
ML20062N540
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1993
From: Michael Benson, Scott A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AMS-94-01, AMS-94-1, NUDOCS 9401180011
Download: ML20062N540 (23)
v • d • e


Text

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                "-      Commonwesith Edison                                          .
      . ,               Quad Cities Nuclear Power Statior,                           l 9,            22710 206 Avenue North 4           Corcova, Illinoic 61242 Telephone 309/654-2241 AMS-94-01 January 5, 1994 U.S. Nuclear Regulatory Commission ATTN: Documefit 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 a'erformance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of December 1993. Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION ff$ Anthony M. Scott System Engineering Supervisor AMS/dak Enclosure cc: J. Martin, Regional Administrator T. Taylor, Senior Resident Inspector 1509 N gof nrMP.hNRCMONDiLY.RPT [ 9407180011 931231 0 PDR ADOCK 0b000254 h4 R PDR

4 QUAD-CITIES NUCLEAR POWER. STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT Decer.ber 1993 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOE. DPR-29 AND DPR-30 TECHOF3WRC4f0NTHLY.RIT i L. .

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E T TABLE OF. CONTENTS e 

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I. Introduction i i II. Summary of Operating Experience A. Unit One B. Unit Two . III. Plant or Procedure Changes, Tests, Experiments, and Safety Related , Maintenance 1 i 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- .j IV. Licensee Event Reports i V. Data Tabulations I A. Operating Data Report ?i B. Average Daily Unit Power Level , C. Unit Shutdowns and Power Reductions VI '. Unique Reporting Requirements R A. Main Steam Relief Valva Operations B. Control Rod Drive Scram Timing Data , f 5 VII. Refueling Information VIII. Glossary  ; 

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l I I. INTRODUCTION t i 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. i;.linois . The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply I 

            -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 i numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. Tho 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. 

                                                                                               <f This report was compiled by Matt Benson and Debra Kelley, telephone number    ,

309-654-2241, extensions 2995 and 2240. ' 

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           . WCHOP3,NRCMONDRN.RM '                                                               t i

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l II.

SUMMARY

OF OPERATING EX"ERIENCE , t i A. Unit One Quad Cities Unit One began the month of December 1993 shutdown while a leak was repaired on the Reactor vessel Level Instrument System. The reactor was made critical at 10:25 hours on December 1 and the generator was synchronized to the grid at 05:05 hours on December 2, 1993. A few load drops were performed for tVt System Power Supply Office but none caused the average daily unit power level to drop by 20% or greater. Unit One turbine tripped and reactor scrammed, on December 16 at 23:55 hours, when a relay failed in the EHC logic system. It was decided to > leave the unit off line and perform additional maintenance on the  ; Unit.

  • The maintenance outage was exited on December 30 when Unit one was made critical at 22:19 hours. Trouble with the scoop tube on the motor generator set and a solenoid in the EHC system c&used the generator to remain off line past the end of December.

B. gpit Two l Quad Cities Unit Two began the month of December 1993 at full power. An invalid low reactor water level signal caused an automatic SCRAM at 16:19 hours on December 2, 1993. The unit trip was caused'by a , pressure spike in the common tapped sensing line during a quarterly reactor high pressure SCRAM calibration and functional test. Foreign , material in an isolation valve was one of the factors leading to this ) ovent. It was decided to leave the unit off line and enter the j maintenance outage scheduled for December 6. The maintenance outage. continued through the end of December. l r i i i i TECHOPENRCatONTHLLRPT 

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III. P_LANT OR PROCEDILRE CHANGER. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE , 1 A. Amendments to Facility Liggnse or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period. j D. Eng1}ity or Procedgre Chances Recuirino NRC ADorov.a1 There were no Facility or Procedure changes requiring NRC approval for , the reporting period. i Revision 1.0 to the Generic Sections of the Offsite Dose Calculation Manual (ODCM) was Onsite Reviewed and accepted on December 15, 1993.  : The revision changed chapters 1, 2, 3, 4, 5, 6, 7, 8, 9, references-and Appendix A, B, C, D, E. This revision incorporates changes based oon the new 10CFR20 which will become ef fective on January 1, 1994.  ; The change is documented in onsite review report Number 93-44 and all i effected pages were transmitted to the NRC by Emergency Preparedness on December 29, 1993.  ; Revision 1.0 to the site specific sections of the Offsite Dose  ; Calculation Manual (ODCM) was Onsite Reviewed and accepted on December 16, 1993. The revision changed chapters 10, 11, 12 and Appendix F; This revision incorporates changes based on the new 10CFR20 which will- .! become effective on January 1, 1994. The' change is documented in , onsite review report number 93-44 and all effected pages were transmitted to the NRC by Emergency Preparedness on December 29, 1993. C. Tests and Experiments Reauirina NRC Acoroval , There were no Tests or Erperiments requiring NRC approval for the l reporting period. I D. CorIgctive Maintenance of Safety Related Ecuipment The following represents a tabular summary of the major. safety related . maintenance performed on Units One and Two during the. reporting j 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. 8 h TEcHoPJSRc\ MON 1HLY.RPT 

                                 ,--                          3                 .--    , . ,

UNIT 1 & 1/2 MAINTENANCE

SUMMARY

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NWR# SYSTEM EPN# WORK REQUESTED WORK PERFORMED 006389 263 1-0263-111D Repair reactor vessel Found gasket on switch cracked pressure switch. and broken. Replaced gasket. Q08258 202 1-0202-6A Replace handwheel on Installed new handwheel and key. recirc cross-tie valve. Q08882 1000 1-1001-90C Investigate / repair Replaced isolation valve with a internal leakage of new one. drywell pressure switch isolation valve. Q09319 6600 1-6657 Repair / replace diesel Replaced motor and rewired. generator lube oil circ  : pump motor. Q09589- '6600 1-6601 Repair oil leak around Cleaned fitting, applied the switch well. permatex, and reinstalled. Q11489 203 1-0203-3C Repair electromatic Replaced control switch and position inCicator. lindt switch. - Q11598 6600 1-6601 Replace brittle wire on Replaced wire with new. E emergency diesel generator power on

  • light panel.

Q11764 1100 1-1165 Repair / replace standby Installed new temperature liquid control pump switch. suction temperature switch. Q11917 5700 1/2-5749 Investigate / repair DG Found dirt, metal shavings,'and cooling water pump room plastic pieces inside alternate cooler-fan will not contactor of fan motor. Cleaned run, motor, reassembled, and returned' it to service. 

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                                                                                                                                                                                                                                    .                  '+.          4 Q11948                     1000        .1-1001-34B             Troubleshoot / repair                           Replaced air valve, worm gear, tripped.thermals.on 1B                          worm, worm shaft, and cetor.

torus spray / cooling stop valve limitorque. Q11992- 6600 1-6601 During diesel generator Installed new. lugs and relanded mod test, ER relay wire. shorted to FSR relay- , repair. 1-2001-15 Replaced solenoid valve on - Q12036- 2000 Investigate / repair valve sticking. operator. , 

          .Q12053-                    1000          1-1001-65C            Investigate / repair if                         ' Installed a pipe plug in place necessary IC RHR                                of the external sight glass.

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IV. I,1CENSEE EVENT REPORTS i The following is a tabular summary of all licensee event reports for Quad- l Cities Units One and Two occurring during the reporting period, pursuant to l the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications. 1 UNIT 1 Licensee Event Report Number Date Title of occurrenp_g 93-023 12-17-93 Rx Scram on apparent low condenser _l vacuum. -l l UNIT 2 t Licensee Event Rf!p_grt Number Date Title of occurrenet 93-023 12-09-93 U2 and 1/2 Diesel Generator operability. 93-024 12-02-93 Rx Scram from Low Level. 93-025 12-05-93 Failed LLRT on "A" Loop MSIV. 93 026 12-24-93 Invalid Low Level Rx Scram. TECllOP3 NRCWONTHLY.RPT

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                                                                                    .t V. DATA TABULATIONS
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The following data tabulations are presented in this report A. Operating Data Report , B. Average Daily Unit Power Level i t 

                                                                                    't C. Unit Shutdowns and Power Reductions                          '

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la ' h APPENDIX C s OITRATING DATA REIORT - F DOCKLT NO, 50-254 UNTT one DATE January 5,1993 COMPLETED BY Matt Benson ' TELEPIIONE (309) 654-2241 OPERATING ST ATUS .[ 0000 120193

1. REIORTINO PERIOD: 2400 123193 GROSS IlOURS IN REIORTING PERIOD: 744 ,

I

2. CURRENTLY AITTilORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACITY: 769 -[

DESIGN LLECTRICAL RATING (MWe Nim: 789

3. IOWER LEVEL TO WHICil RESTRICTED (IF ANY)(MWe-Net): N/A I
4. REASONS FOR RESTRICTION (IF ANY): {

Tills MONTil YR TO DATE CUM UL.ATIVE 5, NUMBER Ol'ilOUR5 REACTOR WAS CRITICAL 399.20 7020.40 149781.30

6. REACTOR RESI2VE SHUTDOWN 110URS 0.00 0.00 3421.90
7. IlOURS GENERATOR ON LINE 344.80 6894.70 145286.30 M. UNIT RESERVE S11UTDOWN llOURS 0.00 0.00 409.20 l
9. GROSS TIIERM AL ENERGY GENERATED (MWil) 770232.50 16111363.40 313693187.20 }
10. GROSS ELECTRICAL ENERGY GENERATED (MWII) 253978.00 5279029.00 101698119.00 j
11. NET LLECTRICAL ENEROY GENERATED (MWil) 239907.00 5042486.00 95917998.00
12. REACTOR SERVICE FACTOR 53.66 80.14 ?8.66 ,
13. REACTOR AVAILABILITY FACTOR 53.66 80.14 80.46
14. UNIT SERVICE FACTOR 46.34 78.71 76.30 :s
15. UNTT AVAILABILTTY FACTOR 46.34 78.71 76.78
16. Uta.T CAPACFTY FACTOR (Using MDC) 41.93 74.85 65.50
17. UNTT CAPACITY FACTOR (Using Design MWe) 40.87 72.96 63.84 I
18. UNTT FORCED OITTAGE R ATE 53.02 15.41 6.32
19. SilUTDOWNS SCIIEDULED OVER NEXT 6 MONTils (TYPE, DATE. AND DURATION OF EACH): r
20. IF SlitTITX)WN AT END OF REPORT PERIOD < ESTIM ATED DATE OF STARTUP:
21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):-

FORECAST ACillEVED INTTIAL CRITICALTTY 4 INITIAL ELECTRICTTY COMMERCIAL OPERATION , 1.16-9 TEOiOP3WRCMONTHLY RPT i i

  • 1, ;

e 1 APPENDIX C OPERATINO DATA REPORT -I DOCKLT NO. 50-265 UNTT Two DAT", knuary 5,1993 , COMPLETED BY Matt Benson TELEPilONE (309) 654-2241 OPERATING STATUS 0000 120193

1. REPORTINO PERIOD; 2400 123193 GROSS HOURS IN REPORTING PERIOD; 744
2. CURRENTLY AUTIIORIZED POWER LEVEL (MWt): 2511 MAX > DEPEND > CAPACTTY: 769 DESIGN ELECmlCAL RATING (MWeNLT): 789
3. POWER LEVEL TO WHICll RESTRICTED (IF ANY)(MWe-Neo: N/A
4. REASONS FOR RESTRICIION (IP ANY):

Tills MONTil YR TO DATE CUMULATIVE

5. NUMBER OF llOURS REACTOR WAS CRTTICAL 40.30 4725.80 143901.05
6. REACTOR RESERVE SHUTDOWN llOURS 0.00 0.00 29u3.30
7. IlOURS GENERATOR ON LINE 4030 4541.70 140183.15
8. UNIT RESERVE SIIUTDOWN IlOURS 0.00 ~0.00 702.90
9. GROSS TilERM AL ENERGY GENER ATED (MWH) 96409.90 10117552.70 302780961.90
10. OROSS ELECTRICAL ENEROY GENERATED (NIWH) 31785.00 3284509.00 97309770.00
11. NET ELECTRICAL ENERGY OENERATED (MWH) 24570.00 3111817.00 92142560.00
12. REACTOR SERVICE FACTOR 5.42 53.95 76.20 s
13. REACTOR AVAILABILTTY FACTOR 5.42 53.95 77.78 i
14. UNTT SERVICE FACTOR 5.42 51.85 74.23  ;
15. UNTT AVAILABILTTY FACTOR 5.42 51.85 74.60 j
16. UNIT CAPACITY FACTOR (Uning MDC) 4.29 46.19 63.45
17. UNTT CAPACTTY FACTOR (Using Design MWe) 4.19 45.02 61.84  :!
18. UNTT FORCED OUTAGE RATE 66.42 26.46 8.53 '8 -

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19. SHUTDOWNS SCl!EDULED OVER NEXT 6 MONTIIS (TYPE, DATE AND DURATION OF EACll):  ;
20. IF SMtTTDOWN AT END OF REPORT PERIOD < ESTIMATED DATE OF STARTUP; I
21. UNITS IN TEST STATUS (PRIOR TO C('MMERCIAL OPERATION):

FORECAST AClllEVED INITI AL CRTTICALITY 

                   .nITIAL ELECTRICITY COMMERCIAL OPERATION .

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           . TEQlOP.hN ROW)NTi!LY.RPT                                                                                                  ,

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er 'U APPENDIX B l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50 254 

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UNIT- One ) DATE . Januarv 5. '1993 -! COMPLETED BY Matt Benson TELEPHONE (309) 654-2241 MCREDI December 1993 l DAY AVERAGE DAILY POWER LEVEL ' DAY AVERAGE DAILY POWER LEVEL , (MWe-Net) (MWe-Net)

1. - 8 17. - 7  :
2. 29 18. - 7 ,

3, 304 19. - 6

4. 665 20. - 7 j

S. 749 21. - 7 I

6. 728 22. - 8 1
7. 769 23. - 8 I
8. 772 24. - ^8 i l
9. 770 25. - 9
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10. 761 26. - 9
11. 761 27 - 8 i
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12. 763 28. - 8
13. 768 29. - 8 760 30.
14. - 9
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15. 769 31. - 8
          '16.                   753                                                                                1 INSTRUCTIONS                                                                                         -

On this fonm, list the average daily unit' pewer level in MWe-Net for each day. .j in.the reporting month. Compute to the nearest whole megawatt. These figures j 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                            i may be occasions when.the daily average power level exceeds the 100% line:(or                           j
         -the restricted power level line).               In such. cases, the average daily unit' power output sheet should be footnoted to explain the apparent anomaly.

l'.16-8 TECHOP3;NRC\ MONTHLY.RM 

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e .; s.'  ; APPENDIX B I AVERAGE DAILY-UNIT POWER LEVEL DOCKFT NO 50-265 .; UNIT Two 

                                                                                         'DATE ggpuary 5. 1993          j COMPLETED BY Matt Benson TELEPHONE   (309) 654-2241 MONTH     December 1993 DAY AVERAGE DAILY POWER LEVEL                           DAY AVERAGE DAILY POWER LEVEL.

(MWe-Net) (MWe-Net)

1. 754 17. - 8
2. 505 18. -7
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3. - 9 19. - 7 I i
4. - 8 20. - 7 l
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5. - 8 21. - 7 l
6. - 8 22. - 8 7 - 8 23. - 8 l
8. - 0 24. - 8
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9. - 8 25. ,[

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10. - 8 26. - 8
11. - 8 27. - 8 ,
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12. - 8 28. - 8  !
13. - 8 29. - 8  ;

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14. - 0 30. - 8 ,

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15. - 0 31. - 8
16. - B .;

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 averagt. 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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1.16-8 TLCHOPKN RC4tONTHLY.RPT 

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J* APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME Qne COMPLETED BY Matt Benson DATE January.,5, 1993 REPORT MONTH December 1993 TELEPHONE 309-654-2241 1 w e m = o ez x ~ 

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D k 3 s A LICENSEE s8 m Vl8 o j m E.c o - DURATION EVENT CORRECTIVE ACTIONS /COMMEh*TS NO. DATE (HOURS) REPORT 93 57 12-1643 F 360.1 A 3 -------- --- ---- SCRAM due to EllC problems. Maintained unit shutdown for MSIV Work. , t 93-58 12 01 93 S 29.1 B 4 -------- --- ---- End of Maintenance Outage.. t a 5 t l l TEGIOP3W RCMON'DH.Y.RPT 

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A APPENDIX D - UNIT SHUTDOWNS AND POWER REDUCTIONS t DOCKET NO. 50-265 [ UNIT NAME Two COMPLETED BY Matt Benson- l DATE' dqnuary 5, 1993 REPORT MONTH December. 1993 TELEPHONE 309-654-2241 l-w O D z o z4 ~ 

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  • DURATION EVENT CORRECTIVE ACTIONS / COMMENTS.

NO. DATE (HOURS) REPORT , 9118 12.-2 9.1 F 79.7 A 3 93 024 --- ----- SCRAM from invalid low level signal. 93-19 12493 $ 6240 B 4 ---- -- --- ---- Entered Selduled Maintenance Osnage. t i I J i 6 

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I u VI. UNIOUE REPORTING REOUIREMENTS 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. -! Unit. One 1 i pa_tg; December 2, 1993 ~ Valve. Actuated: No. & Tvoe of Actuation: [ 1-203-3D 1 Manual Plant Conditions: Reactor Pressure - 922 psig Dercription of Events: PMVT for Work Package , B. Control Rod Drive' Scram Timino Data for Units One and Two-The basis for reporting this data to the Nuclear. Regulatory Commission are- f specified in the surveillance requirements of Technical Specifications j 

                       .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 as performed with reactor pressure greater than 800 PSIG. -t f i e i l l l 4 

                , TECllOP3WRCtMONTHLY.RPT
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E O RESULTS OF SCRAM TIMING MELdCREMEITTS l ~ PERFORMED ON UNIT 1'& 2 CON 1'ROL . RCD DRIVES, FROM 01/01/93 TO 12/31/93 '*- " i

  • 4 AVERAGE TIME IN SECONDS AT 1r -MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 901r l INSERTION DESCRIPTION NUMBER 5 20 50 90 Technica) Specification 3.3.C.1 &
DATE OF RODS 0.375 0.900 2.00 3.5 7'sec. 3.3.C.2 (Averace Scram Insertion Timei 01-28-93 1 0.30 0.67 1.42 2.15 H-12 For Accumulator Replacement
                                                                                                                                                                          -2.15                                                                                                                                      ;

02-12-93 1 0.33 0.72 1.54 2.77 D-5 Accumulator Replacement U2 Q05404 2.77 02-26-93 1 0.32 0.69 1.46 2.61 K-7 Scram Inlet Valve U2 Q05593 2.61 05-28-93 177 0.32 0.705 1.49 2.60 D-9 U2 Start Up Scram Timing Q2R12 3.47 07-13-93 4 0.33 0.73 1.51 2.60 D-9 For WR. Test Q08085 Q07146 Yi 2.69 U2 Q08364 Q07147 , 07-23-93 90 0.31 0.69 1.45 2.53 D-8 U1 SEQA & Q08229 3.4 07-29-93 1 0.32 0.71 1.51 2.66 F-10 U2 Q08629 Accumlator 2.66 08-07-93 1 0.28 0.64 1.37 2.39 -F-15 U1 Q09059 Scram Solenoid i 2.39 08-19-93 1 . 0.28 0.60 1.26' '2.19 A-8 U1 Q09374 Diaphragm' 2.19 4 09-24-93 1 0.32 0.68 1.41- 2.46 C-11 U2 Q08627 Accumulator 2.46 10-23-93 1 0.34 0.71 1.45 '2.51 D-4 U1 Q11022 Scram Valve 2.51 10-28-93 1 0.28 0.65 1:.42 2252 'J-12 U1 Q11231,'Q11151 2 WR 1 CRD 2.52 12-04 113 . 0.30 0.68 1.46 2.56 R-6. U1 SEQ B & WR from Maintenance Outage 3.14 

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4 s. i VII. . REFUELING INFOP14ATION  ; The following information about future reloa'ds 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. J h f t i t i 1 5 7 B I f i t 

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QTP 300-532 Revision 2 s- QUAD CITIES REFUEL.ING October 1989 

   ,                                                                          ~

INFORMATION REQUEST

1. Unit: Q1 Reload: 12 Cycle: 13
2. Scheduled date for next refueling shutdown: 3-12-94
3. Scheduled date for restart following refueling: 7-2-90
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 submitting proposed Itcensing 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 analysis methods, significant changes in fuel design, new operating procedures: ~

160 GE10 Fuel Bundles will be loaded during Q1R13.

7. The number of fuel assemblies.
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:
a. Licensed storage capacity for spent fuel: 3657
b. 0 ,'lr Planned increase in 11 censed storage: l
9. The projected date of the last refueling that can be discharged to thh 3 spent fuel pool assuming the present licensed capacity:2009 APPROVED-(final) 14/0395t -I- W30M Q.C.O.S.R.
 ~

QTP 300-532  ! % RevisiCn 2 ' QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: Q2 Reload: 12 Cycle: 13
2. Scheduled date for next refueling shutdown: 09-24-94
3. Scheduled date for restart following refueling: 12-04-94
4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

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

5. Scheduled date(s) for submitting propoied ;* censing action and supporting information:

5-13-94 i

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 operatirg procedures:

GE10 Fuel will be loaded during Q2R13. k

7. The number of fuel assemblies.
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 2583 ,
8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
a. Licensed storage capacity for spent fuel: 3897
b. Planned increase in licensed 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 (final) 14/0395t ET30 M

_Q.C.O.S.R.  !

l 

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e., VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, I are defined below: ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring j ANSI - American National Standards Instituto APRM - Average Power Range Monitor I 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 j , HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System .f IPCLRT - Integrated Primary Containment Leak Rate Test  : IRM - Intermediate Range Monitor l ISI - Inservice Inspection  ; LER - Licensee Event Report . LLRT - Local' Leak Rate Test  ! LPCI - Low Pressure Coolant Injection Mode of RHRs-LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar 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 I PCI - Primary Containment Isolation ,

PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCW' - React.or Building Closed Cooling Water System RBM - Rod Block Monitor -i RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System RWM - Red Worth Minimi=er 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 , TIP - Traversing Incore Probe TSC - Technical Support Center I t i k b TifHoPr#RC4 tot (nILY.RPT 

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