ML20115H249

Monthly Operating Repts for Mar 1985

ML20115H249
Person / Time
Site:	Quad Cities
Issue date:	03/31/1985
From:	Kimler D, Tamlyn T COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
0027H, 0061Z, 27H, 61Z, TKT-85-07, TKT-85-7, NUDOCS 8504230033
Download: ML20115H249 (21)

Text

i QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 MONTHLY PERFORMANCE REPORT MARCH 1985 COMMONNEALTH EDISON COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 h 42 g g j4 v

,e 0027H

[/

0061Z

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 B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Evert 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 Valvr Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary i

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F I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

The Nuclear. Steam Supply Systems are General Electric. Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.

The Mississippi River is the condenser cooling water source.

The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively;-pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor critica11 ties 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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i II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One March 1-11: Unit One began the month holding load at full power.

On March 2, at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, load was dropped to 600 MWe for a Control

' Rod pattern adjustment.. On March 3, at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, the unit began a normal load increase to full power.

On March 9, at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, load was dropped to 700 MWe for weekly Turbine tests. At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> load was increased to 730 MWe, and the unit was placed on Economic Genera-tion Control (EGC). On March 11, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, load was dropped to 400 MW'e for the repair of the 1B Recirculation Pump Lower Bearing 011-Sight Glass.

On March 12, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the unit began a normal load increase to full power.

March 12-31: On March 15, at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />, load was dropped to 700 MWe for weekly Turbine tests. At 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> the unit began a normal load increase to full power.

On March 23, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, load was dropped to 700 MWe for weekly Turbine tests. At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, on March 24, the unit began a normal load increase to full power.

On March 31, at

-0015 hours, load was dropped to 700 MWe for weekly Turbine tests. At 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br /> the unit began a normal load increase to full power.

B.

Unit Two March 1-7: Unit Two began the month holding load at full power. On March 3, at 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />, load was dropped to 700 MWe for weekly Turbine tests. At 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> the unit began a normal load increase to full power. On March 4, at 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br />, load was dropped to 780 MWe for Barrier Fuel testing. At 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> the unit began a normal load increase to full power. On March 5, at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, load was dropped to 600 MWe for a Control Rod pattern adjustment. At 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> the unit began a normal load increase to full power.

On March 7, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, load was dropped to 700 MWe for weekly Turbine tests. On March 8, at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, the unit began a normal load increase to full power.

March 8-31: On March 11, at 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />, load was dropped to 730 MWe for a Control Rod pattern adjustment. At 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br /> the unit began a normal load increase to full power. On March 13, at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, load was dropped to 730 MWe for Control Rod testing and rod pattern adj ustments. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> the unit began a normal load increase to full power. On March 17, at 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the Turbine was tripped and at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, the Reactor was scrammed to begin the End of Cycle Seven Refueling and Maintenance Outage.

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III.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE l

A.

Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

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 Equipment The following represents a tabular summary of the major Safety Related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

0027H 0061Z

UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION THERE WERE NO SAFETY RELATED WORK REQUESTS FOR UNIT ONE FOR THE REPORTING PERIOD.

e

%4

1 UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT' REPETITION Q40044 Replaced Solenoid Failed 0-Ring or Caused the 2-1601-20A, Replaced solenoid Valve on 2-1601-seal.

Torus to' Reactor Bldg like-for-like and will 50A Valve Relief Valve, to stick later be replaced with open. The 20B valve EQ qualified material was operable'so safety implications were minimal.

Q40083 Troubleshoot No apparent The

'A' Channel was The instrument was problem with 'B' cause found.

operable and the 'B' checked per' procedure SJAE Off-Gas gave a downscale ST-36 and reinstalled.

Radiation reading.

Monitor A

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.l. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title-of Occurrence 85-05 3-7-85 1B Fuel Pool Radiation Monitor Tripped, also 1A Fuel Pool Radiation Monitor Tripped 85-12 3-26-85 1A Fuel Pool Radiation Monitor Spiked High 85-13 3-29-85 IB Standby Gas Treatment System Auto-Started UNIT TWO 85-06 3-18-85 A0 2-203-2B & D Failed Local Leak Rate Test 85-07 3-18-85 Valves and Penetrations Failed Local Leak Rate Test 85-09 3-20-85 2A Fuel Pool Radiation Monitor Tripped 0027H 0061Z

f 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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\\

r-OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEApril 3_.1985 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224ix192 OPERATING STATUS 0000 030105 1.

Reporting period:2400 033185 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):

1his Month Yr.to Date Cumulative 5.

Number of hours reactor was critical 744d 2160,0 90402.5 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 744.0 2134.7 87170.0

8. Unit reserve shutdown hours.

0,0 0.0 909.2 9.

Gross thermal energy generated (MWH) 1781799 4908900 180735290

10. Gross electrical energy generated (MWH) 509207 16531R9_

59430500

11. Net electrical energy generated (MWH) 564403 15040 M 54539763

12. Reactor service factor 100,0 100.0 00.1

13. Reactor availability factor 100.0 100.0 03.1

14. Unit service factor 100.0 90.0 77.1

15. Unit avo11ob111ty factor 100,0 90.0 77.9

16. Unit capacity factor (Using HDC) 98.7.

_95.4 62,8

17. Unit capacity factor (Using Der..MWe) 96.2 92.9 61 2

10. Unit forced outoge rate 0.0 1, 2.

6,0

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

20. If shutdown at end of report period,est1Noted date of startup NA SThe NDC nay be lower than 769 MWe dvring perleds of high onbient temperature due to the thernal perfernance of the spray canal.

$UN0FFICIAl. COMPANY HUMPERS ARE USED IN THIS REPORT

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEApril 3 1985 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224ix192 OPERATING STATUS 0000 030185

1. Reporting periodi2400 033185 Gross hours in reporting period 744

2. Currently authorized power level (MWt): 25i1 Max Depend capacity (MWe-Net): 769* Design electrical rating (HWe-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 304,7 1630,8 06536.0 6.

Reactor reserve shutdown hours 0,0 0,0 2985.0 7.

Hours generator on line 304,i 1600.7 83657,8 8.

Unit reserve shutdown hours.

0.0 0, 0.

7022 9.

Gross thernal energy generated (MWH) 922957 37P2622 175241/iq

10. Gross electrical energy generated (MWH) 302J122 1217401 55870U92

11. Het electrical energy generated (MWH) 209056 1166400 52484465

12. Reactor service factor 51,7 75,5 77,2

13. Reactor availability factor St.Z 75.5 79,9

14. Unit service factor 51,6 74,5 74,6

15. Unit availability factor 51,6 74,5 75,3

16. Unit capacity factor (Using MDC) 50.5 7 0, 2.

60,9

17. Unit capacity factor (dsing Des.MWe)

_47 2 60.4 59,4 10.-Unit forced outage rate 0, 0_

10,6 0.4 l

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

20. If shutdown at end of report period, estimated date o f s t ar t u p _ _6_3 _85 l

• The M C not tt lower than 769 MWe during perleds of high ambient temperatutt det to the thermal perfarnonce of the spray canal.

$UN0FFICIAL COMPANY NUMERS ARE USED IN THIS REPORT l

?

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO.

50-254 UNIT ONE DATEAnril 3 1985 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY-POWER LEVEL

.(MWe-Net)-

(MWe-Net) 1.

793.2 17, 772.5 2.

790.6 18, 787,0' 3,

588.9 19, 796.8 4.

694.6 20.

789.5 5,

783.7 21, 820.2 6.

796.2 22, 771.4 7.

786.5 23.

776.4 8.

794,8 24, 784.0 9.

732.1 25, 789.5 10.

724.3 26, 791.6 11, 563.3 27, 799.2 12.

658,2 28.

783.3 13, 785.5 29, 791.0 14, 789.4 30.

792.O 15. -

716.3 31, 775.5 16, 726.2 INSTRUCTIONS On this fern,Ilst the average daily unit power level in Ne-Net for each day in the reporting neith.Corpote to the neaPest while negawatt.

These figsres will be used to plot a graph for each reporting nonth. Note that when nailmen dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level entecas the 1861 line ter the restricted power level lir.e),In such cases,the avercqe daily snit power actput sheet should te festnoted to explain the apparent enemoly

3 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO D ATE A_p r il 3 1985 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224tx192 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-2,6 17.

-10.3 2.

-2,4 18.

-9,4 3.

777,0 19.

-6.6 4.

777.1 20.

-5,9 5,

759,2 21.

-5,1 6.

691,6 22.

-3,7 7.

709.2 23.

-3.8 8.

768,7 24.

-3,8 9.

781,7 25.

-3,8 10.

785,3 26.

-3,5 ii.

758.7 27.

-3,8 12, 786.4 28.

-3.3 13, 719.1 29.

-3,4 14, 777,3 30.

-3.5 15.

776,9 31.

-3,4 16, 655.6 INSTRUCTIONG l

On this forn, list the average daily snit power level in We-Net for each day in the reperting nonth, Compete to the nearest whole negawatt.

These flgeres will be used to plot a graph for each reporting nonth. Note that when meninen dependable capacitt is used for the met electrical rating of the Unit there may be attasiens when the daily average power level exceeds the 1001 line (or the restricted power level lint),In soth cases,the average daily snit power estpet sheet shavid be festnoted to explain the apparent onenaly

M M

M M

M M. ~ ~

M M

M M

M M

M Y!ES. M M

M

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ID/5A 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. Kimir DATE April 2, 1985 REPORT MONTil

!!ARCil 1985 TELEPl!ONE 309-654-2241 H

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LICENSEE go ga c

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EVENT o"

g DURATION E-s "g

NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

ca 85-17 850302 S

0.0 11 5

RB CONROD Reduced load to 600 MWe for Control Rod pattern adjustment 85-18 850309 S

0.0 B

5 IIA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85-19 850311 F

0.0 B

5 CB PUMPXX Reduced load to 400 MWe for repair of 1B Recirculation Pump Lower Bearing Oil Sight Glass 85-20 850315 S

0.0 B

5 IIA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85-21 850323 S

0.0 B

5 IIA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85'-22 850331 S

0.0 B

5 IIA TURBIN Reduced load to 700 MWe for weekly Turbine tests APPROVED AUG 1 G 1902 (final) yCO&H

O IS E

EEE E

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ClCi M

M M

M 313 - m

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ID/5A APPENDIX D QTP 300-S13 UNIT Sl!UTDOWNS AND POWER REDUCTIONS Revision 6-DOCKET NO.

050-265 August 1982 UNIT NAME Quad-Cities Unit 2 C0t!PLETED BY D. Kimler DATE April 2, 1985 REPORT MONT!!

MARCH 1985 TELEPl!ONE 309-654-2241 H

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EVENT M"

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DURATION M

NO.

DATE

(!!OURS)

REPORT NO.

CORRECTIVE ACTIONS /C0 tit!ENTS o

ca 85-14 850303 S

0.0 B

5 HA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85-15 850304 S

0.0 B

5 ZZ ZZZZZZ Reduced load 780 MWe for Barrier Fuel test 85-16 850305 S

0.0 H

5 RB CONROD Reduced load to 600 MWe for Contro.1 Rod pattern adjustment 85-17 850307 S

0.0 B

5 HA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85-18 850311 S

0.0 H

5 RB CONROD Reduced load to 730 MWe for Control Rod pattern adjustment 85-19 850313 S

0.0 H

5 RB CONROD Reduced load to 730 MWe for Control Rod testing and pattern adjustment 85-20 850317 S

359.87 C

2 ZZ ZZZZZZ Unit shutdown for End of Cycle Seven Refueling and Maintenance Outage APPROVED AUG 1 G 1982 (final).

y G.O b h

VI. 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.

B.

CONTROL R00 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.

4 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.

W 0027H 0061Z

QTP 300-S32 i

Ravision 1 I

QUAD-CITIES. REFUELING ilarch 1978

~,

INFORMATION REQUEST o

1.

Unit: _

Q1 Reload:

7 Cycle:

8 1-2-86 2.

Scheduled date for next refueling shutdown:

3 S heduled date for restart following refueling:

4-2-86 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:

DECDIBER 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.

l 7

The number of fuel assemblies.

P a.

Number of assemblies in core:

724

6. -

b.

Number of assemblies in spent fuel pool:

2340 3-8.

The present licensed spent fuel pool storage capacity and the size of any i

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 IIcensed 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 2.01978 Q. C. O. S. R.

e

b QTP 300-S32 l

Revision 1 t

QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

3-16-85 (Actual) 3 Scheduled date for restart following refueling:

5-28-85 4.

Will refueling or resumption of operation thereafter require a technical I

specification change or other license amendment:

T Yes. A routine MAPLHGR amendment has been submit'ted as a preparatory change j

to allow a 10 CFR 50.59 review.

5.

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

(-

Not Applicable.

I j

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:

I None planned at present time.

1^

i."

1-1 I

7 The number of fuel assemblies.

E a.

Number of assemblies in core:

0 1.

b.

Number of assemblies in spent fuel pool:

900 v

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 l

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 01978 Q. C. O. S. R.

VIII. GLOSSARY 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 ATHS Anticipated Transient Without Scram BHR Bolling Hater Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System Emergency Operations Facility EOF GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test 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 PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH 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 RHM Rod Horth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCH Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center I

l l

0027H 0061Z l

O Commonwealth Edison Qu:.d Citiis Nucir.r Power Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 TKT-85-07 April 1, 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 March 1985.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION J

f-W

?

l l

l T. K. Tamlyn l

Services Superintendent bb Enclosure a,

i 0027H 0061Z