Text

Monthly Operating Repts for Mar 1984
	ML20083P571
Person / Time
Site:	Quad Cities
Issue date:	03/31/1984
From:	Beth Brown, Kalivianakis N, Misak A; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NJK-84-118, NUDOCS 8404200069
	Download: ML20083P571 (19)
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t QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 l

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HONTilLY PERPORMANCE REPORT MARCll 1984 CCHMONWEALTil EDISON COMPANY AND j

IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 t

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TABLE Op MNTENTS

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, I f,' Summary of Opsr.it lng F.xp*ericacu p

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e Plant or Proceidure Cnango.1, Tests, R;periments, and Safety Ill.

.telated W.s inf t,)an.W '

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Amendencs to Fact)(?y 1.leense or I.cchnical Specifications l

B.

Fac t!1ty or Procedars thongos Roqutting NRC Approval C.. Tests and,Gpgrimont; Requirlur, NRC lipproval l

D, correct (vi Maht;nanco of Safety Related Equipment IV.

Licinsee LN.t Reports

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D.,.ta Tabulstions i

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Operatiot.h.&f a Report,

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1 Average Ally,11 nit i' owr level

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Unit Shutdovne and Power Redi-'Gttons V t,' Unique Reporting Pt'quirementa -

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Msin Stes: Mellet Valve OparatJ/.nr

-... -tontrol kod Drive Scran Tfulny 0.ita '

B VII.

Refueling infonnation VIII. Glossary w.

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INTRODUCTION l

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l Quad-Citles Nuclear Power Station is camposed of two Bolling Water Reactors, each with a Max 1 mum Dependable Capacity of 769 MWe i

i Net, located in Cordova, Illinois. The Station is jointly owned by Canmonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

i The Nuclear Steam Supply Systems are Cencral Electric Company l

Bolling Water Reactors. The Architect / Engineer was Sargent &

Landy. Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling wa ter source. The plant is subject to license l

numbers DPR-29 and DPR-30, issued October 1,1971, and Morch 21, 1972, respectively; pursuant to Docko t Numbers 50-254 and 50-265.

The date of inttial Reactor critica11tles for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Comme rclal i

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

This report was complied by Becky Brown and Alex Hisak, telephone number 309-654-2241, extensions 127 and 194.

A II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Unit One began the month derated to 710 MWe due to End of Cycle fuel depletion. These deratings continued until 0113 hours0.00131 days 0.0314 hours 1.868386e-4 weeks 4.29965e-5 months on March 6 when the unit was shutdown for End of Cycle Seven Refueling and maintenance.

In addition, the unit dropped load to 700 MWe at 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months on March 4 for weekly Turbine tests. At 0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months , the testing was completed, and a nornal load increase was initiated.

B.

Unit Two March 1-5:

Unit Two began the month increasing load 5 MWe/ hour to full power following a unit shutdown to replace the motor on the 2B Recirculation Pump Discharge Valve. This load incrcase was terminated at 790 MWe on March 2 because of high Turbine vibration.

The unit maintained this load until 0340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months on March 3 when the unit dropped load to 650 MWe due to Condensate Demineralizer problems. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months , a normal load increase was Initiated. This load increase was terminated at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months on March 4 due to high Turbine vibration.

The unit maintained a load of 790 MWe until 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months on March 5 when the unit dropped load to 650 MWe due to Condensate Demineralizer p roblems. At 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months the unit began increasing load, and the increase continued until 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months when the unit held load at 790 MWe due to high Turbine vibration.

March 6-11: At 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months on March 6, the unit dropped load to 650 MWe due to Condensate Demineralizer problems.

At 0550 hours0.00637 days 0.153 hours 9.093915e-4 weeks 2.09275e-4 months the unit began a normal load increase to full power.

At 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months on March 7 the unit dropped load to 750 MWe for Main steam isolation valve testing. At 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months the testing was completed, and the unit increased load until 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months when the increase was terminated because of high Turbine vibration.

At 0508 hours0.00588 days 0.141 hours 8.399471e-4 weeks 1.93294e-4 months , the unit dropped load to 600 MWe due to high Turbine vibration.

At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months the unit began increasing load to full power. At 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months , on March 10, the unit dropped load to 700 MWe for weekly Turbine tests and Control Rod Pattern adjustments. At 0220 hours0.00255 days 0.0611 hours 3.637566e-4 weeks 8.371e-5 months the unit began a normal load increase.

B.

Unit Two (Continued)

March 12-23: At 0655 hours0.00758 days 0.182 hours 0.00108 weeks 2.492275e-4 months on March 17, the unit dropped load to 660 MWe due to a failed Feedwater Regulating Valve. At 0000 hours0 days 0 hours 0 weeks 0 months on March 18, the valve was repaired and a nornal load increase to full power was initiated.

March 24-31: At 2110 hours0.0244 days 0.586 hours 0.00349 weeks 8.02855e-4 months on March 24, the unit dropped load to 300 MWe as part of testing to collect data on single Recirculation pump. operation and to define the flow control line. At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months on March 25, the testing was completed and the unit began a nornal load increase to full power.

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

Amendments to Facility License or Technical Specifications On February 14, 1984, the NRC issued Amendment 81 to License DPR-30. This Amendment establishes limiting conditions for operation, setpoints for overvoltage, undervoltage, and underfrequency protective instrumenta-tion, and surveillance requirements for the Reactor Protection Bus Power Monitoring System.

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 Mainter.ance of Safety Related Equiprent The following represents a tabulo summary of the major r

safety related nalntenance performed on Unit One and Unit Two during the reporting period.

This summary includes the following headings; Werk Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT _0WE MAINTE;tANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN T0 t

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q33089 RHR Supprest. ion Leads were broken The valve would not All of the lugs on Pool Cooling at the limit operate; the unit the limit contact Valve 1-1041-36B contact block, was shutdown.

block connected to field wirino were replaced.

Q33386 84-2 A0 1-1601-23 Wear.

Contributed total The packing was LLRT failure.

adjusted.

Q33387 84-2 A0 1-Is01-24 Wear.

Contributed total The plate opposite LLRT failure.

the operator had a gasket installed.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q29139 2A RHR Service Cavitation.

The pump makes a The problem is being Water Pump lot of noise and the studied.

Meanwhile, casing is erroded.

the casing was replaced.

-Q32602 IRM Channel 15 lhe dual trip The IRM gave a The 216 Dual trip module 216 Dual Trip nodule was bad.

constant inope rable was replaced with a Module signal.

spare.

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IV, LICENSEE EVENT REPORTS 4

The following is a tabular summary of all licensee event reports i

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 Licensee Event Report Number Date Title of Occurrence 84-1 3-5-84 Electromatic Failed to Open 84-2 3-7-84 Leak Rate From all Valves and Penetrations 293 75

- SCFH 84-3

'3-6-84 Spurious Water -Level Scram

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84-4 3-16-84 MSIV Failed Local Leak Rate Test UhlT TWO There were no Licensee Event Reports, for Unit Two, for the' reporting period.

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V, DATA TABUIATIONS 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 v

OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEApril 6 COMPLETED BYAlex L.

Misak TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 030184 1.

Reporting period:2400 033184 Gross hours in reporting period:

744 2.

Currently authorized power level (MWt): 2511 Max. Depend copocity_

(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):

This Month Yr.to Date Cunulative 5.

Number of hours reactor was critical 122.1 1562.1 85i17.7 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 121.2_

1561.2, 81909.1

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8. Unit reserve shutdown hours.

O'0 0.0 9 0'/. 2

9. Gross thermal energy generated (MWH) 252848 3659732 168766438

10. Gross electrical energy generated (MWH) 83636 1213148 54471764

11. Net electrical energy generated (MWH) 79579 1152950 50758917

12. Reactor service factor 16.4 71.5 81.7

13. Reactor avo11obility factor 16.4 71.5 84.9

14. Unit service factor 16.3

'71.5 78.6

15. Unit avo11obility factor 16.3 71.5 79.5

16. Unit capacity factor (Using MDC) 13.9 68'6 63.3

17. Unit capacity factor (Using Des.HWe) 13.6 66.9 61.7

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18. Unit forced outage rate 0.0 0.0 6.1 j

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

20. If shutdown at end of report period, estimated date o f s t or

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8The NBC ney be lower then 769 mit dering perleds of high onblent tenperatore dee-to the thernal perfernance of the sprey canal.

$1BIIFFICIAL COWAIN MpOERS ARE USED 111 THIS REPORT

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I OPERATING DATA REPORT DOCKET NO.

50-265 l

UNIT TWO DATEAnril 6 COMPLETED BYAlex L.

Hisak TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 030184

1. Reporting period:2400 033184 Gross hours in reporting period 744

2. Currently authorized power level (MWt): 2511 Max. 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):

This Month Yr.to Date Cunulative

5. Nuober of hours reactor was critical 744,0

__989.5 78907.0 0.l 2985_.fL j

6. Geoctor reserve shutdown hours 0.0 7.

Hours generutor on line 744.0_

904.3 76114.1 B.

Unit reserve shutdown hours.

0.0 0.0 702.9 i

9.

Gross thermal energy generated (MWH) 1783500 197?283

~157359371

10. Gross electrical energy generated (MWH) 583515 641733 50077513 ii. Net electrical energy generated (MWH) 554974 608312 46942372

12. Reactor service factor 100.0 45.3 76.4

13. Reactor avo11ob111ty factor 100.0 45.3 79.3

14. Unit service factor' 100.0

~41.4 73.7

' i5. Unit avo11ob111ty factor 100.0' 41.4 74.4

16. Unit capacity factor (Using MDC) 97.0 36.2 59.i

17. Unit capacity fact'or (Using Des.MWe) 94.5-35.3 57.6

18. Unit forced outage rate 0.0 10.6 8.7-

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

20. If shutdown at end of report period,e st imated date - of star t up ___NA 8The HOC not be lower then 769 Hlle dering periods of high enblent tenperature dee to the thernel perfernance of the sprer canal.

8tMOFFICIM. ColFAlff IUSERS ARE UED Ill THIS REPORT

i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEApril 6 COMPLETED BYAlex L.

Misak TELEPHONE 309-654-2241xi94 HONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

654.3 17.

-5.8 2.

697.3 18.

-5.4 3.

692.0 19.

-5.3 4.

709.6 2 0 '.

-5 J 5.

559.8 21.

-5 7 6.

-6.6 22.

-5.6 7.

-10.7 23.

-5_,3 8.

-9.8 24.

-5.2 b

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-10.2 25.

-4,1 10.

-9,8 26.

-4,2 11.

-9,8 27.

-4,2 L2.

-10.2 28.

-4.0 13.

-8.2 29.

-4,2 14.

-7,9 30.

-3,3 15.-

-6,5 31.

-3,2 16.-

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INSTRUCTIONS' On this forn, list the eserege daily snit power level in ille-Met for each dar in the reporting nenth. Compete to the nearest uhele negemott.

'These figeres will be used to plot a graph for each reporting nenth. Note that when no:inen dependable capacite is.

used for the set electrical reting of the sait there ney be eccesiens when the delly eserege power level exceels the

-illI line (or the restricted power level line).,In suh cases,the eserege dell enit power setpet sheet should be t

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEApril 6 COMPLETED BYAlex L.

Misak TELEPHONE 309-654-2241x194 HONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

L.

689.8 17, 679.4 2.

745.7 18, 697.1 3.

708.8 19, 781.9 4.

738.3 20.

786.3 5.

720 9 21.

773.0 6.

757.6 22, 780.9 7.

677.0 23.

783;7 8.

744.4 24.

733.3 9.

780.8 25.

600.7 10, 763.2 26, 748,1 ii.

745.3 27.

783.5 12, 769.i 28.

778.3 L3.

775.7 29.

781.4 14, 785.5 30.

781.6 15, 770.8

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779.0

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780.8 INSTRUCTIONS On this forn, list the estrege delly enit power laul in ltie-kt for each day in the reporting senth Compete to the neerest uhele negemett.

These figeres will be used te plot a graph for each reporting nenth liete that when noninen dependeble cepecite is used for the net electrical reting of the enit there ney be occasions when the delly eserege peuer level exeeds th '

1991 line (or the restricted power level line).'In sKh Cases,the estrege daily enit peger setpet sheet should be feetnoted to esplein the apparent enenely

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

050-254 August 1982 UNIT NAtlE Quad-Citles Unit One CutlPl.ETED BY Alex Misak DATE April 9, 1984 REPORT P10:!rt! MARCH 1984 TEl.EPil0NE 309-654-2241 N

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NO.

DATE (ll0URS)

REPORT NO.

CORRECTIVE ACTIONS /CotitlENTS v

oo 84-12 840304 S

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine tests I

86-13 840305 F

0.0 B

5 84-1 SF VALVEX Reduced load for Drywell entry to inspect o

'IE' Electromatic Relief Valve 84-14 840306 5

622.8 C

1 84-1 RC FUELXX Unit One Shutdown for End of Cycle Seven Refueling and Maintenance APPROVED AUG 1 G 1982 (rinal) ygg3g

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ID/5A APPENDIX D QTP 300-S13 IINIT SilllTDOWNS AND POWElt HEDilCTIONS Revision 6 DOCKET NO.

050-265 August 1982 UN1T NAME _ quad-Citles Unit Two C0ilPLETED BY Alex Misak DATE April 9. 1984 HEPORT HodTil MARCH 1984 TEI.EPl10NE 309-654-2241 N

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DATE (Il0URS)

HEPORT NO.

CORHECTIVE ACTIONS /COHilENTS oo 84-5 840303 F

0.0 B

5 HG DEMINX Reduced load due to Condensate Demineralizer problems 84-6 840305 F

0.0 B

5 HG DEMINX Reduced load due to Condensate Demineralizer problems 84-7 840306 F

0.0 B

5 HG DEMINX Reduced load due to Condensate Demineralizer problems 84-8 840307 S

0.0 B

5 CD VALVEX Reduced load for weekly MSIV testing 84-9 840307 F

0.0 B

5 HA TURBIN Reduced load due to high Turbine vibration 84-10 840310 S

0.0 B

5 RB CONROD Reduced load for Control Rod Pattern adjustments 84-11 860317 F

0.0 B

5 CH VALVEX

. Reduced load due to failed Feedwater Regulating Valve i

84-12 840324 S

0.0 B

5 CB ZZZZZZ Reduced load for Flow Control Line determination and single Recirculation l

Loop operation data collection.

APPROVED AUa 1 G 1982 1 (final) gg3g j

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

A.

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

I B.

Control Rod Drive Scram Timing Data For ' Units One and Two There was no Control Rod Drive Scram Timing Data for Units i

One ani! Two for the reporting period.

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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-S32 Rsvision 1 QUAD-CITIES REFUELING March 1978 d

INFORMATION REQUEST 1.

Unit:

QI Reload:

7 Cycle:

8 Refueling Outage 2.

Scheduled date for next refueling shutdown:

Currently in Progress 3

Scheduled date for restart following refueling:

5-21-84 4.

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

Preparatory Technical j

Specification changes have been submitted to include MAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.

5.

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

Technical Specification change has been submitted February 21, 1984.

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:

1) All new fuel assemblies will be GE78-type (barrier clad, extended exposure design).

2) A generic methodology wcs used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

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3)

Four Barrier Lead Test Assemblies will be re-inserted to gather

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information on the effects of extended exposures.

7 The numter of fuel assemblies.

a.

Number of assemblies in core:

0 b.

Number of assemblies in spent fuel pool:

2454 y

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

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in number of fuel assemblies:

1 a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in IIcensed storage:

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The projected date of the last refueling that can be discharged to the

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spent fuel pool assuming the present licensed capacity: 2003 L(

XPPROVED I

L APR 2 01978 Q.C.O.S.R.

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QTP 300-S32 l

Revision 1

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QUAD-CITIES REFUELING March 1978 h,

INFORMATION REQUEST r

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1.

Unit:

- Q2 Reload:

7 Cycle:

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2.

Scheduled date for next refueling shutdown:

3-18-85 4

3 Scheduled date for restart following refueling:

5-26-85 r

4.

Will refuellng or resumption of operation thereaf ter require a technical specification change or other license amendment:

f Not as yet determined.

L 5.

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

January 18, 1985, i f licensing action requi red.

6.

Important IIcensing 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 cperating procedures:

I)

All new fuel assenblies will be GE78-type (barrier clad, extended exposure design).

2) A generic methodclogy was used-for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

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The number of fuel assembites.

Number of assemblies in core:

724 a.

o b.

Number of assemblies in spent fuel pool:

412 1;,

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 i

in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 1

b.

Planned increase in IIcensed storage:

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9.

The projected date of the last refueling that can be discharged to the F

spent fuel pool assuming the present Ilcensed capacity: 2003

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XPPROVED APR 2 01978 m

Q. c. O. S. R.

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VIII, C LDSSARY The following abbreviations which may have been used in the Monthly Report, are defined beloa:

ACAD/ CAM Atmospheric Containment Atmospheric Dilution /Contalmient Atmospheric Monitoring American National Standards Institute ANSI Average Power Range Monitor APRM ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor C RD Control Rod Drive EHC Electro-Hydraulic Control System Emergency Operations Facility EOF CSEP Generating Stations Emergency Plan H EPA High-Ef ficiency Particulate Filter High Pressure Coolant Injection System HPCI HRSS High Radiation Sampling System IPC LRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Evant Report LIRT Incal Leak Rate Test LPCI Low Fressure Coolant Injection Mode of RHRS L!'RM local Power Range Monitor MAP LHCR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximon Fraction llmiting Critical Power Ratio MPC Maximum fe rmissible Concentration MS IV Ma in S team Isola tion Val ve National Institute for Occupational Safety and Health NIOSH Primary Containment Isolation PCI Precenditioning Interim Operating Management Recommendations PCIOMR RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RHRS RPS Reactor Protection Sys tem Rod Worth Minimizer RWM SBGTS Standby Cas Treatment System Standby Liquid Control i

SBIC SDC Shutdown Cooling Mode of RHRS l

SDV Scram Discharge Volume SRM Source Range Monitor Turbine Building Closed Cooling Water System TBCCW TIP Traversing Incore Probe Technical Support Center TSC

c.

CommonwIalth Edison J*

C Quid Citiss Nucitar Powar Station tW 22710 206 Avenue North Corcova, filinois 61242; Telephone 309/654-2241 NJK-84-118 April 9,1984 Director, Effice of Inspection & Enforcenent United States Nuclear Regulatory Commission Washlagtor., D, C, 20555 Attention: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Perf ormance Report covering the operation of Quad-Cities Nuclear Power Station, Unica One and Two, during the month of March 1984, i

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER -STATION s.#f&

N. J. Kalivianakis

-Station Superintendent bb Enclosu re jh

\\

ML20083P571

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