ML20112J344

Monthly Operating Repts for Dec 1984

ML20112J344
Person / Time
Site:	Quad Cities
Issue date:	12/31/1984
From:	Kalivianakis N, Kimler D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
0027H, 0061Z, 27H, 61Z, NJK-85-05, NJK-85-5, NUDOCS 8501180251
Download: ML20112J344 (22)

Text

1 t

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER 1984 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8501180251 841231 PDR ADOCK 05000254 R

PDR

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i TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.

Amendments to Facility License or Technical Specifications 4

B.

Facility or Procedure Changes Requiring NRC Approval i -

C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Clossary i

0027H 0061Z

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1.

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 POmpany 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 criticalitiec for Units One and Two, respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.

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

0027H 0061Z

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11.

SUMMARY

OF OPERATING EXPERIENCE A.

Un i t One :

December 'l-13: Unit One began the-month on Economic Generation Cont rol: (EGC). At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> load was dropped to 455 MWe to repair the Recirculation MG-Set Tach Coupling.

On December 2, at 0457 hours0.00529 days <br />0.127 hours <br />7.556217e-4 weeks <br />1.738885e-4 months <br />, the Turbine was tripped and at 0511 hours0.00591 days <br />0.142 hours <br />8.449074e-4 weeks <br />1.944355e-4 months <br /> the Reactor was scrammed to repair the 1-202-4A Recirculation Suction Valve.

On December 4, at 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br />, the Reactor was critical and on December 5,.at 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br />,'the unit was.on line, and starting a normal load increase to full power. On December 10, at 1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br />, load was dropped to.740 MWe to place the unit in EGC." On December 13, at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, the. unit dropped loed 'to 250 MWe. to repai r. Traversing in-Core Probe ' tubing.

At 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br />,' on December 14, the' unit began a normal load increase to full power.

December '14-31 : On December 17, at 1333 hou'r's, load was dropped to I

760 MWe to place the unit in EGC.

On December 22, at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, load was -dropped to 700 MWe due to 181 Heater problems..At 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br /> the unit was.placed in EGC. On December 23, load was dropped to 700 MWe to perform Turbine weekly tests.

At 0522 hours0.00604 days <br />0.145 hours <br />8.630952e-4 weeks <br />1.98621e-4 months <br /> load was increased to 720 MWe and the unit was placed on EGC.

On December 24, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, load was dropped to 500 MWe per a Load Dispatcher.

B.

Unit Two December-1-12:. Unit Two began the month at full power.

On Decenber 2, at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, load was dropped to 700 MWe for Turbine' weekly tests.

At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> the. unit began a normal load increase to full powe r.

Dn December 9, at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, load was dropped to 700 MWe for

. Turbine weekly tests. At 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> the unit began a nornal load increase to full power.

On December 10, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, load was dropped to 725 MWe per a Load Dispatcher request.. At 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> the unit began'a normal load increase to full power.

On December 12, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, load was dropped to 623 MWe per a Load Dispatcher. request.

t

~ At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> the unit began a normal load increase to full power.

3 December 13-31:

On December 15, at. 2240 ' hours, load was dropped to 700 MWe for. a Control Rod pattern adj ustment.

On December 16, at' 1655 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.297275e-4 months <br />, the unit began a normal load increase to full. power.- On December 18, at 1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />,. load was dropped to 700 MWe for a Condensate 1 Pump ~ changeove r.. At :1200 hours, the ~ unit began increasing load to full power.,0n December 21,^at 2353 hours0.0272 days <br />0.654 hours <br />0.00389 weeks <br />8.953165e-4 months <br />, the Turbine was tripped and at 0022 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> the Reactor was scrammed to repair the-Phin Transforner. - On-December 29, at 1728 hours0.02 days <br />0.48 hours <br />0.00286 weeks <br />6.57504e-4 months <br />, the Reactor was1 critical. On December 30, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />,~the unit was <s L.ne beginning a normal. load increase

'to full powe'.

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i III.

PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications On June 19, 1984, the NRC issued Amendment 89 to License DPR-29 and Amendment 84 to License DPR-30.

These Amendments establish specifications for the monitoring of Radiological Effluents at Quad-Cities Station.

B.

Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety Related Equipnent The following represents a tabular summary of the major safety related maintenance perforned on Unit One and Unit Two during the reporting period. This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

0027H 00612

UNIT 1

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q38988 Replace Torque Excessive torque Valve failed to close.

Lcosened packing, Switch on the MO-during closure due Remaining open is the upped torque swi tch 1-202-4A Valve to overtight packing.

position the valve is current trip setpoint in during a LOCA.

from 3 2 to 4.0 amps, and next outage will repack valve and inspect.

Q38994 Adjusted Limit Weight of actuating improper indication.

Readjusted limit Switches on I-arm moved switches Unit shutdown and switches.

1601-33B out of adjustment.

valve did actually work.

Q39021 Repaired Closure incorrect wiring of Without shunt field Corrected wiring.

Problem With 1-shunt field coil.

coil there is a loss Since past history 2301-14 Valve of valve movement shows this to be an speed control. HPCI isolated case so no remained operable at further action is all times. Valve is necessa ry.

just a minimum flow test valve.

Q39058 Adjusted Packing See Notes on Work Request Q38988 Listed Above.

and Lubricated Stem on 202-4A Valve Q36831 Replaced Diesel Unknown.

Tripped Diesel Replace switch like-Generator Low Generator #1; was for-like.

Water Pressure locally reset and ran Siwtch 1-6641-502 0.K. Would have been bypassed on an autostart.

e a

UNIT 1

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETIT10N Q38186 Repaired Limit Valve not functioning Motor operator power Replaced limit Switch Block on properly. First supply breaker switch block, cleaned Valve 1-1001-23B thought limit switch tripped on thermal spring pack and was the problem,-then overload. 'A' loop installed grease tube determined spring was available and (Work Request Q38304).

pack of motor valve could have operator was the cause been operated manually.

(Work Request Q38304).

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i UNIT 2

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS-W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q28248 Remove Mechanical See Deviation SNED evaluation Like-for-like Snubbers for Repo rt 4-2-83-66.

results said 12 of replacement. Personnel Functional Testing Side loading, 14 were operable told not to stand rust, corrosion, and the other two did on snubbers and and misaligned not impart signifi-improvement of Drywell inertia mass.

cant effects on the envi ronnent.

piping.

Q38347 Repaired Valve 2-Unknown.

Dual indication Unknown.

1601-33A originally, then (lubricated got to cycle and valve stem restored Delta-P packing) between Drywell and Torus in ten minutes.

Q38986 Adj usted High Instrument set-Failure caused Calibrated and Trip Point on point drift.

Standby Gas to perforned a functional 2B Fuel Pool Auto-Start and test.

Monitor Reactor vent system to isolate which is in the safe direction.

Q39412 Repai red ' D' Failed resistor

'B' Channel 1/2 scram Replaced resistor and Main Steamline in high voltage and 1/2 Group I functionally tested.

Radiation Monitor power supply.

Isolation. Failed in safe direction.

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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 ONE There were no Licensee Event Reports for Unit One for the reporting period endino December 31, 1984.

UNIT TWO Licensee Event Report Number Date Title of Occurrence 84-12 12-01-84

'B' Fuel Pool Monitor Tripped 0027H 0061Z

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V.

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

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions i

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OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ~

ONE DATEJanuarv 9 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241x192

- 0PER AT1.NG. STATUS

~

0000-120184 L

Li.-Reporting period:2400 123184 Gross hours in reporting period:

744 2.: Currently authorized power level.(MWt): 2511'Hux. Depend capacity (MWe-Net)':-769* Design electrical. rating (MWe-Net): 789

-3 Power level to which restricted (if any)(MWe-Net): NA 4.-Reasons for restriction (if any):

1his Month Yr,to Date-Cumulative 25.

Number.of hours reactor was critical 689.0 4766.9-88322.5 6.

Reactor reserve shutdown hours 0.0 i0.0 3421.9 7.

Hours generator on line 659.2-4687.5 85035.3 8.

Unit reserve shutdown hours.

0.0 0.0 909.2-

~9.. Gross thermal energy generated (MWH) 1464510 10639684' 175746390 LO. Gross electrical' energy generated (MWH) 483038 3519835 56777451 ii. Net-electrical energy generated (MWH)-

461658 3349735 52955702

12. Reactor service factor 92.6 54.3 79.7 13.-Reactor ovallability factor' 92;6 54.3 82.8 c14.. Unit service factor.

88.6 53.4~

-76 '7

.15.

Unit-availability. factor 88.6 53.4 77.5

'16. Unit capacity factor (Using MDC) 80.7 49.6 62.i' 17.-Unit capacity f. actor:(Using Des.MWe) 78.6 48.3 60.6 18.. Unit forced outage rate ~

11 4

'2-7

'6.1

~

.. Shutdowns scheduled'over next:6 months.(Type,Date,and DurationMof_each):

20.t-If shutdo'wn at end o# report p e r i o d, e si A ma t e d. d at e o f. s t ar t u p

____N_A________

- 8The IIOC ney'be ' lever then 769 Inle during periods of high onbient tenparatere det to the thernal perferne ce of the sprey canal.

IWilFFICIAL CIIIPAltf NIIERS ARE USED 111 THIS REPORT

1 j

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEJanuarv 9 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241x192 OPERATING STATUS 0000 120184 1.

Reporting period 2400 123184 Gross hours in reporting period:

744 2.

Currently outhorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 3.

Power level to which restricted (if any)(MWe-Net): NA 4.

Reasons for restriction (if any):

lhis Month Yr.to Date Cumulative 5.

Number of hours reactor was critical 558.9 6988.5 84906.0 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 538.4 6839.4 82049.2 8.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Cross thermal energy generated (MWH) 1279234 16136979 171519067

10. Gross electrical energy generated (MWH) 420415 5217631 54653411

11. Net electrical energy generated (MWH) 402015 4983925 51317985

12. Reactor service factor 75.1 79.6 77.2

13. Reactor availability factor 75.1 79.6 80.0

14. Unit service factor 72.4 77.9 74.6

15. Unit availability factor 72.4 77.9 75.3

16. Unit copocity factor (Using hDC) 70.3 73.8 60.7

17. Unit capacity factor (Using Des.MWe) 68.5 71.9 59.2

10. Unit forced outage rote 27.6 5.8 8.4

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

20. If shutdown at end of report period,estiMoted date of startup __@__________

• The NDC nay be leur than 769 MWe daring perleds of high onbicnt tenperature due to the thernal perfornance of the spray canal.

$UN0FFICIAL COMPANY NtNERS ARE USED IN THIS REPORT

r :.

APPENDIX B AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT _

ONE DATEJanuarv 9 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92 MONTH December 1984 DAY AVERAGE. DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

359.6 17, 753.7 2.

42.0 18.

718.2 3.

-10.5 19.

776.7 4.

-11.7 20.

784.8 5.

82.3 21, 799.0 6.

604.7 22.

730,7 7.

746.7 23.

723.5 O.

78$.0 24, 678.9 9.

788.7

25..

701.1 10.

770.6 26.

715.5 ii.

698.2 27.

774.8 12.

690.6 28.

683.2 13, 658.3 29, 700.3 14.

576.9 30.'

-694.1 15. -

764.6 31.

702.3

'16, 782.4 INSTRUCTIONS On this forn, list the overage daily enit power level in Mlle-Net for each day in the reporting nenth.Conpete to the nearest whole negowatt.

These figures will be used to plot a graph for each reperting nenth. Note that when moninen dependable capacity is used for the net electrital rating of the unit there may be occasions when the daily average power level exceeds the-

- 1991 line (or the restricted power level line).,In seth cases,the average daily enit power outpet sheet should be footnoted to explain the apparent onenely e

' APPENDIX B.

. AVERAGE DAILY. UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEJanuorv 9 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224ix192 MONTH December 1984

' DAY AVERAGE DAILY POW'ER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

799.0 17.

772.8 2.

758'.9 18, 767.0 3.

797.5 19, 788.2 4.

771.3 20, 786.5' 5.

785.8 21.

663 i 6,

790.9 22.

-8.9 7.-

789.5 23.

-10.4 8.

786.2 24.

-10.4 9.

765.2 25.

-10.5 10.

773.7 26.

-9.7 11, 778.4 27.

-9.6 12.

735.4 28.

-9.5 13.

816.0 29.

-9.9 14, 756.8 30.

128.8 15.

785.8 31, 533.3 16..

677.8 INSTRUCTIONS--

' nearest whole, list the overage daily enit power level in Mlle-Net for each day in the reporting nenth.Conpete to the On this forn negewett.

.These figures will be used to plot a graph for each reporting nenth. Note that when notinen dependable capacity is esed for he net electrical rating of the enit there nay be occasions when the daily overage power level exceeds th ill! line (or the restricted power level line),In such cases,the average daily enit power estput sheet sheeld be

- festnoted to explain the apparent onomaly

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ID/SA APPENDIX D QTP 300-S13 UNIT Sl!UTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY D. Kimler DATE January 7, 1985 REPORT MONTil DECEMBER 1984 TELEPil0NE 309-654-2241 N

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B

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DURATION M

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ou NO.

DATE (110URS)

"o REPORT NO.

CORRECTIVE ACTIONS / COMMENTS ca 84-38 841201 S

0.0 B

5 CB XXXXXX Load was reduced to repair MG Set Tach Coupling 84-39 841202 F

84.75 B

2 CB VALVEX Reactor scram to repair the 1-202-4A Recirculation Suction Valve 84-40 841210 S

0.0 F

5 XX ZZZZZZ Load was reduced to place the unit on Economic Generation Control 84-41 841213 S

0.0 B

5 IF INSTRU Load was reduced to repair Traversing In-Core Probe tubing 84-42 841217 S

0.0 F

5 XX ZZZZZZ Reduced load to place the unit on Economic Generation Control 84-43 841222 F

0.0 B

5 HH HTEXCH Reduced load for 1B1 Low Pressure Heater problems 84-44 841223 S

0.0 B

5 HB TURBIN Reduced load to perform Turbine weekly tests 84-45 841224 S

0.0 F

5 ZZ ZZZZZZ

' Reduced load to system minimum per a request by the Load APPROVED Dispatcher AUG 101982 (final) ygg3g e

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M M

M M

M M

M M

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p ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-265 August 1982 UNIT NAME Quad-Citles Unit 2 COMPLETED BY D. Kimler DATE January 7, 1985 REPORT HONTil DECEMBER 1984 TELEPIIONE 309-654-2241 g

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LICENSEE go ga mo DURATION Ei EVENT m

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NO.

DATE (IIOURS)

REPORT No.

CORRECTIVE ACTIONS / COMMENTS o

~84-58 841202 S

0.0 B

5 HB TURBIN Reduced load to perform Turbine weekly tests 84-59 841209 S

0.0 B

5 HB TURBIN Reduced load to perform Turbine weekly tests 84-60 841210 S

0.0 F

5 ZZ ZZZZZZ Reduced load per Load Dispatcher 84-61 841212 S

0.0 F

5 ZZ ZZZZZZ Reduced load per Load Dispatcher 84-62 841215 S

0.0 H

5 RB CONROD Reduced load for Control Rod Pattern adjustment 84-63 841218 S

0.0 H

5 HH PUMPXX Reduced load for Condensate Pump change-over 84-64 841221 F

205.6 B

2 HA TRANSF Reactor scram for repai r of Main Trans fo rme r APPROVED AUG 1 G 1982

. (final) ygg3g

VI.

UNIQUE REPORTING REQUIREMENTS j

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

l A.

MAIN' STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B.

CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

i 9

0027H 00612

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.

0027H 0061Z L--

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1 QTP 300-532 Revision 1 QUAD-CITIES REFUELING tiarch 1978 INFORMATION REQUEST 1.

Unit:

01 Reload:

7 Cycle:

8 1

2.

Scheduled date for next refueling shutdown:

1-2-86

)

3 Scheduled date for restart following refueling:

4-2-86 i

4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:

NOT AS YET DETERMINED.

5.

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

DECCIBER 19, 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.

7 The number of fuel assemb11es.

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 capccity: 2003 XPPRoVED APR 2 019'l3 C). c:. <>. S. R.

P

~

QTP 300-S32 Revision 1 QUAD-CITIES REFUEll!;G tiarch 1978

.,=

INFORMATION-REQUEST 1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

3-18-85 3

Scheduled date for restart following refueling:

5-28-85 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:

Yes. A routine MAPLHGR amendment will be submitted as a preparatory change to allow a 10 CFR 50 59 review.

5 scheduled date(s) for submitting proposed Itcensing action and supporting Information:

banua ry 31, 1985 6.

Important licensing considerations associated with refueling, e.g., new or

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

None planned at present time.

~

7 The number of fuel assembites.

l a.

Number of essemblies in core:

724 1

b.

Number of assemblies in spent fuel pool:

0 ij

- 8.

The present licensed spent fuel pool storage capacity and the size of any Increase in IIcensed storage capacity that has been requested or is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 l

b.

Planned increase in licensed storage:

0 9

The pro,iected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capccity: 2003 NPPROVED APR 2 019'l3 CD. CL <>. S. R.

w_

VIII. CLOSSARY The following abbreviations which may have been 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 CRD Control Rod Drive Electro-Hydraulic Control System EHC EOF Emergency Operations Facility GSEP Cenerating 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 IRM 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 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 PCIONR 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 Traversing Incore Probe TIP TSC Technical Support Center 0027H 00612

CN Commonwealth Edison

) 22710 206 Avenue North

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Quad Citits Nuclsar Powsr Station O

c~f Cordova, Illinois 61242 Telephone 309/654-2241 NJK-85-05 January 3, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission 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 December 1984.

i Respectfully, COletONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

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N. J. Kalivianakis Station Superintendent bb Enclosure 0027H 0061Z

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