Text

Monthly Operating Repts for Oct 1984
	ML20099E635
Person / Time
Site:	Quad Cities
Issue date:	10/31/1984
From:	Kalivianakis N, Kimler D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NJK-84-344, NUDOCS 8411210461
	Download: ML20099E635 (22)
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QUAD-CITIES NUCLEAR POWER STATION-

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. UNITS l'AND 21'-

y1 MONTHLY PERFORMANCE' REPORT . g~

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OCTOBER 1984- s' se COMMONWEALTH EDISON. COMPANY.

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IOWA-ILLIN0IS GAS & ELECTRIC COMPANY , y, NRC DOCKET NOS. 50-254 AND 50-265 i /

LICENSE NOS. OPR-29 AND DPR-30 i ,

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s TABLE OF. CON' TENTS. ;

I. Introduction

II. . Summary 'of Operating Experience.

"- A. . Unit One-

. . B. : Uni t Two -

III..- Plant or Procedure < Changes, Tests, Experiments, and Safety.

.Related Maintenance

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Amendments .to Facility License:or Technical Specifications -

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B. Facility or Procedure ~ Changes Requiring NRC- Approval C. .TestsLand ExperimentsiRequiring 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 s

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.,x zn II. INTRODUCTION

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.Q'uad-Cities' Nuclear' Power Stat! ion is: composed. of two Boiling

-Water Reactors, each with a 'Ma'ximum Dependablef Capacity of _.769.MWE n

Net,' located in Cordova, Illinois. iThe..Stationcis;, jointly owned by:

Cannonwealth~ Edison Company _and -Iowa-Illinois Gas' & Electric Company.

The. Nuclear Steam ~SupplyjSystems are Generalf Electric' Company :

Boiling Water Reactors. :The_ Architect / Engineer was- Sargent &

Lundy,; Incorporated, andithe-' primary constructionicontractor 'was-United Engineers & Constructors. The Mississippi . River ~ is_~ the =

condenser cooling water source. ' The' plant ,is subject- to license

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numbers DPR-29 and:DPR-30,, issued October 1, 1971, and March 21,.

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1972, respectively;: pursuant ~ to Docket Numbers.50-254~ and 50-265.

1 The date of initial Reactor criticalitiles.for Units One and Two, 1 respectively were' October 18..-1971, and April 26,19/2. Commercial -

. generation of power began on February 18, 1973 for Unit One-and .

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March .10,1973 for Unit Two.

This report was compiled by Becky Brown and Dave Kimler, telephone nusber 309-654-2241, extensions 127 and 192.

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II. -SUMMAR.Y OF 0PERAT,ING _E.XPER,I_E.NC_.E.

A. Unit'One October 1-10: ' Unit One began the month' increasing load to' full' powe'r after-weekly Turbine tests., On October 7, at 2350 hours0.0272 days 0.653 hours 0.00389 weeks 8.94175e-4 months , load was reduced to 700 MWe for weekly Turbine tests.' . At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months the unit began a normal load' increase to full power. .On October 10, at.0855 1hours; load was reduced to 750 MWe to place the unit in Economic Generation Control (ECC).

October 11-19: On October 12,: at 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months ,' loa'd was reduced to change the EGC load setpoint. On October 13, at 0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months , the. unit was off ECC due to computer malfunctions. Load was reduced to.700

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MWe to. perform weekly Turbine tests. On October 19, at 0415. hours, load was reduced to 75015ha to place the unit on EGC.

October 20-31: On October 20, at 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months , the Load Dispatcher requested that the unit be taken off EGC. The unit began a normal load increase to full power. On October 21, at 0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months ,' the load '

increase was stopped'at.790 MWe per-a' Load Dispatcher request. At 0110. hours load was reduced to 750 MWe to place the unit-on EGC.

On October 28, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , load was reduced to 700 MWe for weekly Turbine tests. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .the unit began a normal load increase ro full power.

B. Unit Two October 1-21: Unit Two began the month increasing load to full power af ter weekly Turbine tests. On October 7, at 2355 hours0.0273 days 0.654 hours 0.00389 weeks 8.960775e-4 months , load was reduced to 700 MWe for weekly Turbine tests. At 0155 hours0.00179 days 0.0431 hours 2.562831e-4 weeks 5.89775e-5 months the unit began a normal load increase to full power. On October 10, at 0840 hours0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months , load was reduced to 744 MWe to place the unit on EGC.

On October 21,-at 2355 hours0.0273 days 0.654 hours 0.00389 weeks 8.960775e-4 months , load was reduced to 700 MWe for. weekly Turbine tests. At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months the unit began a normal load increase to full power.

October 22-31: On October 24, at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months , load was reduced 200 FMe/ hour due to a fluid leak in the EHC System. On' October 25, at 0326 hours0.00377 days 0.0906 hours 5.390212e-4 weeks 1.24043e-4 months , the Turbine was tripped and at 0640 hours0.00741 days 0.178 hours 0.00106 weeks 2.4352e-4 months the-Reactor scrammed on high pressure. On October ~27, at 0808 hours0.00935 days 0.224 hours 0.00134 weeks 3.07444e-4 months , the Reactor was critical and at 1615 hours0.0187 days 0.449 hours 0.00267 weeks 6.145075e-4 months the Generator was on line. At 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months load was reduced to 350 HWe due to high Turbine vibration. On October 28, at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months , the unit began increasing load to full power. On October 31, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , load was reduced to perform MSIV tests. At 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months the unit began a normal load increase to full-power.

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>m III. PLANT - OR . PROCEDURE ' CH,ANGES ,;_TSE_STS ,; EXPE_RIMENTS , AND SAFETY :

' RELATED. .M..AI.NTEN.ANCE-Amendments"to Facility License'or Techn'ical' Specifications-

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.There were no Amendments to the Facility License or -

s Technical Specifications forLthe reporting period. -

B. Facility or Procedure' Changes Requiring NRC' Approval-There were no Facility or Procedure. changes. requiring-

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NRC approval'for the-reporting. period.'

C. Tests and-Experiments Requiring NRC Approval-There were no. Tests or-Experiments' requiring NRC'

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approval for.the reporting period ~.

'D. Corrective Maintenance of-Safety Relate'd Equipment' -

1 The following represents-a tabular summary of.the. major '

scfety related maintenance performed on Unit,One and Unit Two'during ths.' reporting: period. ~This summary: -

' includes the following headings: Work Request Numbers,'

LER Numbers,' : Components, Ccuse of. Malfunctions, Results and Effects on Safe Operation,-and Action Taken to.

Prevent" Repetition'.

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a y UNIT ONE MAINTENANCE.

SUMMARY

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, , ; j CAUSE- RESULTS 6. EFFECTS W.R. LER OF' - ON: ' ACTION TAKEN T0sJ u'

~ NUMBER NUMBER COMPONENT- MALFUNCTION' SAFE ~0PERATION ' PREVENT REPETIT10N' 1

Q35138 84-2 A0 1-8803 Not seating tight. .The in-line' valve, A0e Lapped _ seating surfaces-(leaks) 8804,-would have. . .and repacked.1Thei . ~

limited the-leakage'to , leakage was reduced tof 4.9,SCFH. an_ acceptable value.

Q36408 'D' RHR Service Door latch stops' Reference. Deviation ' Adjusted door stops.

Water Vault Door were out ; of . adj us t- : Report 4-1-84-41.

(leaks) ment. Leakage would be small enosagh that the sump pump could have easily;- .

handled the volume ins the unlikely. event; oft -e condensate. pit flooding.-

Q37279 l-261-2C Main Setpoir.t _ drif t. The: Main Steam'Line high~ ReplacedJthesswithh.

Steam.Line - flow Group I: Isolation Replace Mercury would'have: occurred:as Switch (high designed due to the .' '

flow DPIS) . conservative nature'of-the one-out-of-two-twice: ,

logic associated with the;

' differential pressure

switches. . Reference

Deviation. Report: 4-1-84-56.

Q37762 .1-1402-57 Motor stator- Reference Deviation' Report ~ .The'CondensateL. Transfer.

Jockey. Pump - windings shorted , .4-1-84-67.- Dischargeipipe system was. utilized Breaker Tripped to ground.. " pressure was.hrought with- 'until.the pump / motor was? '

When Attempting- ein Technical Specification: replaced;like-for-like..

to Restart Pump limits seven hours before-

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.the required-12. hours was1 up.

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UNIT TUO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS-W.R. LER OF ON . ACTION'TAKEN TO-NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION 4f j Q37592 2-2301-48 Valve Unknown. . Flow could have been jValve was opened,"and ^

'(HPCI)~Will Not ' diverted to the CCST's1 . the operator was l- Open Until if the need for a- rebuilt.

] lianually Cracked- cooling' water-flow path.

Off Seat. had occurred.-

) - Q37683 110 2-1001-18A - Operator to. yoke liinimum flow bypass is Replace with like-for-:

Came Apart From bolts aheated not critical ~or- like' bolts.

i the Stem. .off. necessary for the function of RHR.

, - Q37749 590-103A Relay Insulation A trip of the 'A'. Replace coil with ,

(replace) melted; coil channel of the RPS ; improved high temperature burnt out. - ensued. This is the Century coil.

. conservative direction.

The relay performed.its'.

1 designed . saf ety -

function.' Reference Deviation 1 Report 4-2--

84-59.

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LICENS.EE. EVE.NT_REPOR_TS !: .

The- following is a tabular-.sunnary of -all licensee event reports + '

. for Quad-Cities Units One~ and Two_ occurring during the reporting ': 2.-

period,: pursuant to the reportable' occurrence! reporting requirements-

as' set-forth in sections '6.6.B.1. and 6.6.B.2. .of the Technicali

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Specifications.. ,

UNIT ONE There were no Licensee Event Reports for Unit Oneifor=the- '

. reporting period.

UNIT TWO-Licensee Event.

Report Number .Date Title of Occurrence'-

84-10 10-25 Unit Two Scram in.

Hot Standby' due to High Pressure 3

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V. : DATA;., TAB _U,LA.TIONS. .

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-The following data tabulationsare present.ed in this report:' ,

<- ' A. ~ Operating Data Report -

J- B. 'LAverage Daily. Unit Power Levell

'C. Unit Shutdowns- and Power Reductions e

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4 0PERATING' DATA ~ REPORT i-1 DOCKET'NO. 50-254 UNIT-- ONE DATENovember 5 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 OPERATING STATUS 0000 100184 745

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'i-.-Reporting period:2400 103184 Gross hours in reporting period 2.. Currently authorized' power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769*fDesign electrical rating (MWe-Net): 789

3. Power level to which' restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if-any):

'This Month Yr.to Date Cumulative

5. Number of- hours reactor was critical- '745.0 3357.9 86913.5

6. Reactor reserve shutdrwn hours 0.0 0.0 3421.9

7. Hours generator on line 745.0 3308.2 83656.1

8. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thernal energy generated (MWH) 1782849 7509975 172616681 10 ', Gross electrical energy generated (MWH) 589219 2486015 55744631

11. Net electrical energy generated (MWH) 564401 2350824 51964791

12. Reactor service factor 100.0- 45.9 79.5

13. Reactor ovallobility factor 100.0 45.9 82.6 L4. Unit service factor 100.0 45.2 76.5 15.' Unit ovellobility factor 100.0 45.2 77.3.

L6. Unit capacity factor (Using MDC) 98.5 41.9 61.8

17. Unit capacity factor (Using Des.MWe) 96.0 40.8 60.2 L8. Unitiforced outage rate 0.0 1.3 6.1

19. Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of each):

NA

20. If shutdown at end.of report period, estimated date of startup

The ItDC nay be lower than 769 MWe during periods of high enbient tenperatste due

' to the thernal performmte of the spray ccnal, i L $UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

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COMPLETED BYDAVE KIMLER>

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6 ? OPERATING STATUSl

?0000 100134; . y . , <

~745-

, li'.ERepor. ting period:2400'103184 Gross h'oursiintreporting; periods -

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l' f2 kCurrentlyJuuth'orized power (level:-(MWt)if 2511TMax '. Depend capacit'yc ~ ~

J(MWe-Net) ?.769* Designielectritale rating 1(MWe-Net):?789, _

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53. ! P owerile ve l J t oj whictiJrest r'ic t ed ( if.L an'y ) ( MWe--Ne t ): N A - .

--4.. Reasons forirestrictIon.(if-any).:

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This L M on t h' 'Yr,tojDate: ' Cumulative; 5

.5.l Numb'en of hours rea: tor was critical- 695.9' -5709;6 i __

83627 i-

'6. Reactor reserveishutdown hours 0.0- 0.0 :2985?8

l. 7. Hours generatorfon line 684.2' 5581.0- 80790,8

'8. Un'itureserveTshutdown ho'urs. '702.'9-

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9. Gross-thernal energy generated (MWH) 1606077. 13137864- 168519952

10. Gross:electrital energy generated (MWH) '520137 4236979. 53672759 ii. Het electricalienergy generated (MWH) 498338 '4041829 50375889

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12. Reactor,servic'e factor -93.4 78.0 77.1

' 13." Reactor. availability factor 93.4 78.0 79.9-

- 14'. f un i t service factor 91.8 76.2 74.5-

15.: Unit.avullability factor 91.8 76.2' 75.1

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Unit: capacity factor (Using.MDC) 87.0 71.8- 6 0 ~. 4 -

17. ' UnitC ciapacity factor "(Using Des.MWe) 84.8 70.0 58.9

}i8'. Unit forced outage rate '6.7 3.7 8.3.

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration _of each):

L20. If/shutdowniat endof report per i od , e st ina t ed d at e o f s t ar t up

. __NA__________ .

-8The llDC nep;be lever then 70 IWe during perleds of high unblent tenparatere die f Jte the thernal perfernance of the spray canal. . .

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. - stBINFICIAL- CSNif. IRAWERS ARE.USED Ill THIS REPORT

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! APPENDIX Bl

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' DOCKET NO.- 50--2541 s L/

UNIT ONE-

, ~ -DATENovember 5 ,'

COMPLETED'BYDAVE KIMLER' TELEPHONE 309-6h4--2241Xi92 L

- DMONTH- October 1984 D'AY? AVERAGE ~ DAILY POWER 1 LEVEL' DAY-AVERAGE 1DAILYiPOWER; LEVEL- ;

( MWe-Ne t ) ;- -(MWe-Net)

i. 792.5 'i7.- 778.O' 2.- 789.5 -

18 . -: 789'.i' 3.. 794.0~ 19. -717-6 .

24 . 781.1 20 . . -

709.9--

5. - 7 9 2 '. 8 21. .. -

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U 6. 792.O' - 22'. 708.5

7. 768.6 - 23. . 711.3

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8. 790.6 24. 711,9

9. 787.0 .25. -

766.'i

10. 746.2 26. 786.8-

'ii. 730.0 27, 784.9

, 12. 715.6 28. 798.7 13, 727.7 29. 794.8

14. 734.0 30. 785.8

15. 715.9 ' 31. 794.6

16. 712.8 INSTRUC(IONS On this fern, list the average daily snit power level in Mlle-Met for each day in the reporting nenth.Conpste to the t nearest whole neaevatt.

l These figures will be esed to plot a graph for each reporting nenth. Note that when nominen dependable capacite is

.nsed for the net electrical rating ef the unit there may be occasions when the daily average power level exceeds the

< ' ill! line (or the restricted power level line).,In such cases,the overage daily enit power estput sheet shield be festnoted to explain the apparent anenely

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATENovember 5 COMPLETED BYDAVE KIMLER TELEP40NE309-654-2241Xi92 MONTH October 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 775.0 17. 773.3

2. 787.2 18, 768.4

3. 783.6 19, 772.8 4, 769.8 20. 781.0 5, 786.0 21. 767.7

6. 781.9 22, 776.1

7. 719.9 23, 780.4

8. 818.3 24. 760.0

9. 769.8 25, 15.3

10. 731.9 26. -11.5 ii. 707.1 27, 75.5

12. 697.4 28, 421.0 13, 712.8 29. 630.9 14, 686.0 30, 725.4

15. 708.0 31. 752.2

16. 729,5 INSTRUCTIONS On this fern, list the average daily snit power level in MWe-Net for each day in the reporting nonth.Campste to the nearest whole negawatt.

These figures will be used to plot a graph for each reporting nonth. Note that when noxinen dependable capccity is used for the net electrical rating of the unit there nay be occasiens when the daily average power level exceeds the illIline (or the restricted pswer level line),In sich cases,the average daily snit power evtput sheet shtold be footnoted to explain the apparent anencly

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ID/5A APPENDIX D- QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY D. Kimler DATE November 5, 1984 OCTOBER 1984 REPORT HONTil TELEPlIONE 309-654-2241 m $ g w" $ m EE gw Ww g$ Q M LICENSEE m@ @

NO. DATE w DURATION M EVENT REPORT NO.

$" o" (IIOURS) CORRECTIVE ACTIONS / COMMENTS o

84-25 841007 S 0.0 B 5 IIA TURBIN Reduced load to perform weekly Turbine tests 84-26 841010 S 0.0 F 5 XX ZZZZZZ Reduced load to place the unit in EGC operation 84-27 841012 S 0.0 F 5 XX ZZZZZZ Reduced load to change ECC load limit setpoint 84-28 841013 S 0.0 B 5 IIA TURBIN Reduced load to perform weekly Turbine tests 84-29 841019 S 0.0 F 5 XX ZZZZZZ Reduced load to place the unit in EGC operation 84-30 841021 S 0.0 F 5 XX ZZZZZZ Reduced load to place the unit in ECC operation

84-31 841028 S 0.0 B 5 IIA TURBIN Reduced load to perform weekly Turbine tests APPROVED AUG 1 G 1982

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ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED By D. Kimler DATE N vember 5, 1984 OCTOBER 1984 REPORT HONTil TELEP110NE 309-654-2241 N $ g m" 5 SE gm Wm

@ Q M LICEN?EE m@ g@

NO. DATE w DURATION d EVENT REPORT NO.

$ o" U

(IIOURS) CORRECTIVE ACTIONS / COMMENTS a

84-46 841007 S 0.0 B 5 HA TURBIN Reduced load to perform weekly Turbine tests 84-47 841010 S 0.0 F 5 XX ZZZZZZ Reduced load to place the unit in EGC operation 84-48 841021 S 0.0 B 5 HA TURBIN Reduced load to perform weekly Turbine tests 84-49 841024 F 0.0 A 5 HB VALVEX Reduced load due to leaking Servo Valve on EHC System 84-50 841025 F 49.13 H 3 ZZ ZZZZZZ Reactor scram due to high Reactor pressure 84.-51 841025 F 0.0 H 5 HA TURBIN Reduced load due to high Turbine vibration 84-52 841031 S 0.0 B 5 IIB VALVEX Reduced load to perform MSIV testing APPROVED AUG 1 G 1982 (final) yGUbH

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VI.- UNIQUE REPORTING REQUIREMENTS s

The following items iare included in ~ this report based on prior .

'h Jcommitments to'the commission:

O A..'llain' Steam Relief Valve Operations

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.There were no Main' Steam Relief Valve. Operations-for'..the. '

' reporting period..

B. -Control Rod Drive' Scram Timing Data for Units'-One and Tuo' ,

- The basis'for reporting this= data to'the Nuclear Regu'latory:

Commission are.specified in the surveillance requirements of:-

Technical Specifications 4.3.C.1 an'd 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'.

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a RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM l-1 TO 12-31-84 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION NUMBER S 20 50 90 Technical Specification 3.3.C.I s DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Time) 10-27 1 0.29 0.69 1.58 2.34 2.34 Unit 2 K-13 Ilot Scram Timing After Replacement l

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. VII. REFUELING _INF_0RMATI.0N._

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- The .following. information about future reloads at. Quad-Cities :.

' Station was requested-in a January .26,1978, licensing memorandum.

.'(78-24) from .D., E. O'Brien to- C; . Reed, et al . . . titled "Dresden,

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_ Quad-Cities, and Zion Station--NRC~ Request' for. Refueling Information",

dated January 18, 1978.

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'A I QUAD-CITIES REFUEll!!G March'1978 p INFORMATION REQUEST.

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1. Uniti Q1 Reload: 7 Cycle: 8 l

2. ' Scheduled date for next refueling shutdown: 11-11-85

'3 Scheduled date for restart following refueling: 1-20-86..

4.- Will refueling or resumption of operation thereaf ter require a technical k- specification change or other IIcense amendment:

> NOT AS YET DETERMINED.

m ~

5 Scheduled date(s) -for submitting proposed licensing action and supporting Y- . Information:

' SEPTEMBER 13, 1985, IF LICENSING ACTION REQUIRED.

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 PLANNED AT PRESENT TIME.

W L

b 7 The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 2340

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. 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: 2003

[ XPPROVED APR 2 01973 Q.C.C.S.R.

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y~ . a' g .

. . QTP 300-S32 Reviston 1 Y-,.* ' ~

QUAD-CITIES REFUELING HIrch 1978 es

~

INFORMATION REQUEST

~

U~ 1. Unit: 2 Reload: 7 Cycle: 8

2. Scheduled date for next. refueling shutdown: 4-2-85 i

3 Scheduled date for restart following refueling:

6-22-85 *

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other IIcense amendment:

] Ilot as yet determined.

1 5 Scheduled date(s) for submitting proposed IIcensing action and supporting 7

1

.-- Information:

3 . January 18, 1985',. If IIcensing' action required.

f'

6. Important IIcensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis q methods, significant changes in fuel design, new operating proced,ures:

d . -- tione planned at present time.

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b 7 The number of fuel assemblies. .

I' a. Number of assemblies in core: '724 L1 b' . Number of assemblies in spent fuel pool: 0 m

Ij 8. The present Ilcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned r, in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 3897 r,

I, b. Planned increase in licensed storage: 0 L

9 The projected date of the last refueling that can be discharged to the spent fuel p,ool assuming the present IIcensed capacity: 2003 f}

4PPROVED

.U APR 2.01978

, Q.C.O.S.R. ;

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(m - _ _ -

F .A .

-VIII. GLOSSAR)

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The following' abbreviations which may have Ibeen used 'in .the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric' Containment Atmospheric Dilution / Containment

- Atmospheric Monitoring ANSI -- American National Standards Institute ^

APRM - Average ~ Power Range. Monitor ATWS :- Anticipated Transient Without Scram

-BWR - . Boiling Water Reactor

.CR0 .- Control Rod Drive Electro-Hydraulic Control System

-EHC -

E0F - Emergency Operations Facility GSEP. -

Generating Stations Erergency Plan HEPA - - High-Efficiency Particulate Filter HPCI -

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

Integrated Primary Containment Leak Rate Test IRM - Intennediate 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 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 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 RPS -

Reactor Protection System RWM -

Rod Worth Minimizer 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

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/ ) ' Quad Cities Nucleir Power Stiti:n j -

N 22710 206 Avenue North

\ / Cordova, Illinois 61242.-

- (M :. Telephone 309/654-2241 I

NJK-84-344 i l

4 November 1, 1984 Directior, Office-of Inspection & Enforcement l United' States Nuclear Regulatory Comunission Washington, D. C. 20555 Attention: Document Control Desk.

, ' Gentlemen:

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 October 1984.

l J

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION I

f/

N. J. Kalivianakis Station Superintendent l

bb Enclosure f

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ML20099E635

Text

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SUMMARY

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