ML20107D325

Monthly Operating Repts for Jan 1985

ML20107D325
Person / Time
Site:	Quad Cities
Issue date:	01/31/1985
From:	Kalivianakis N, Kimler D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
0027H, 0061Z, 274, 27H, 61Z, NJK-85-37, NUDOCS 8502220312
Download: ML20107D325 (22)

Text

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QUAD-CITIES NUCLEAR POWER STATION UNITS-1 AND 2 MONTHLY PERFORMANCE REPORT JANUARY 1985 C01440NWEALTH EDISON COMPANY AND 10WA-lLLIN0lS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 E

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TABLE OF CONTENTS

~

l.

Introduction II.

Summary of Operating Experience

.A.

Unit.One B.

Unit Two-111.

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 lC.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment

'lV.

. Licensee Event Reports V.

Data Tabulations A. ' Operating Data Report-B.

Average DailyfUnit 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 Vll.

Refueling Information

- Vill.

. Glossary w

)

A.

0027H 0061Z

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I.-

INTRODUCTION

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Quad-Cities Nuclear Power Station is composed of two Boiling Water Water Reactors, each with a M ximum Dependable Capacity of 789 MWe Net, a

. located in Cordova, Illinois. The Station is jointly owned by Commonwealtb Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The i

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

r 0027H 0061Z wun

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SUMMARY

OF OPERATING EXPERIENCE A.

Unit One January 1-19: Unit One began the month operating on Economic Generation Control (EGC). On January 4, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, load was dropped to 700 MWe for weekly Turbine tests.. At 0312_ hours load was increased to 720 MWe to place the unit in EGC operation. On January 13, at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />, load was dropped to perform weekly Turbine tests.

At 0140 tonrs load was increased to 730 MWe to place the unit in ECC operation. On January 18, at 0107 hours0.00124 days <br />0.0297 hours <br />1.76918e-4 weeks <br />4.07135e-5 months <br />, load was dropped to 750 MWe to place the unit on EGC operation. On January 19, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, load was dropped to 700 MWe for weekly Turbine tests. At 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br />

. load was increased to 740 MWe to place the unit in EGC operation.

January 20-31: ;0n January 24, at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, load was dropped to place the unit on EGC operation.- On January 25, at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br />, load was dropped to 400 !!We to take the 1C Reactor Feedwater Pump out of service. At 1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br /> the unit began a normal load increase to full power. On January 27, at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />, load was dropped to place the

-unit in EGC operation.

B.

Unit Two January 1-14: Unit Two began the month increasing load for fuel preconditioning.

On. January 5, at 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />, load was dropped to 700 MWe for a Reactor Feedwater Pump changeover. At 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br /> the unit began a normal load increase to full power. On January 8, at 2030. hours,. load was dropped to 70011Ne for weekly Turbine tests. At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> the unit began a normal increase to full power.- On January

-11, at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />, load was dropped to.700 MWe for Low Pressure Heater problems. At 1742 hour0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br />s-the unit began a normal increase to full p ower.-

On' January.14, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, load was dropped to 720 MWe to set the Feedwater Level Controller. At 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br /> the unit began a normal, load increase to full power.

~

January 15-31: On January 16, at 0622 hours0.0072 days <br />0.173 hours <br />0.00103 weeks <br />2.36671e-4 months <br />,- load was dropped due to low Condenser vacuum. At 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br /> the Reactor scrammed on low vacuum. On January 22, at 2314 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.80477e-4 months <br />, the Reactor was critical and at-1140 hours the unit was on line. (ht January 25, at 0128 hours0.00148 days <br />0.0356 hours <br />2.116402e-4 weeks <br />4.8704e-5 months <br />, the Reactor. scrammed due to #4 Control Valve fast closure during testing.

-At 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br /> the Reactor was critical and at 2208 hours0.0256 days <br />0.613 hours <br />0.00365 weeks <br />8.40144e-4 months <br /> the unit was on line..On January 30, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, load was dropped due to failure of the High Pressure Coolant Injection (HPCI) valve 2301-8 to open during tests. At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, the unit began a normal load increase to full power.

0027H 0061Z

t Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY:

RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications There were no Amendments to.the Facility License or i.

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.

Tes's 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 Humbers, LER Numbers, Components,.

Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCT10N SAFE OPERAT10N PREVENT REPETITION-Q39690 Repaired the

'B'

' Auxiliary Core Spray pump not Cleaned and inspected Core Spray Pump contacts for starting.

Only one entire breaker in Control Circuitry breaker were pump is needed and accordance with QIIS stuck open.

.the other one was 200-5.

operable.

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IV.

LICENSEE EVEhT 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 the reporting period.

1 UNIT TWO Licensee Event Report Number Date Title of Occurrence 85-01

'01-25-85 Reactor scram due to

1. 4 Control Valve Fast Closure.

85-02 01-29-85 HPCI inoperable.

85-03 01-16-85 Reactor scram due to loss of Condenser vacuum.

0027H 0061Z

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V.

DATA TABULATIONS

' The following data tabul'ations are presented in this report:

A.

Operat_ing Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions s

1 0027H~

0061Z

OPER ATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEFebruarv 5 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 010185

1. Reporting period:2400 013185 Gross hours in reporting period:

744

2. Currently authorized 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 Cunulative 5.

Number of hours reactor was critical 744.0 744,0 81066,5

6. Reactor reserve shutdown hours 0,0 0,0 3421.9

7. Hours generator on line 744,0 744.0 85779,3

8. Unit reserve shutdown hours.

0,0 0.0 909.2 9.

Gross thernal energy generated (MWH) 1722980 1722980 177469370

10. Gross electrical energy generated (MWH) 571074 571874 57349325 ii. Net electrical energy generated (MWH) 547864 547864 53503566

12. Reactor service factor 100.0 100,0 79.8

13. Reactor ovallobility factor 100.0 100.0 82.9

14. Unit service factor 100.0 100.0 76,9

15. Unit ovollobility factor 100.0 100.0 77,7

16. Unit copocity factor (Using MDC) 95,8 95.8 62,4

17. Unit copocity factor (Using Des.MWe) 93,3 93,3 60,8

18. Unit forced outage rate 0,0 0,0 6.0

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

20. If shutdown at end of report period,estincted date of stortup IThe MDC not be lower than 769 MWe dering periods of high onbient tepperatere due to the thermal perfernonce of the spray car,al.

$lpl0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

r OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEFebroorv 5 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241x192 OPERATING STATUS 0000 010185 1.

Reporting period:2400 013185 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):

Inis Month Yr.to Date Cumulative

5. Number of hours reactor was critical 591.0 591.0 85497.0

6. Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 574.1 574.1 82623.3

8. Unit-reserve shutdown hours.

O.0 0. 0.

702.9

9. Gross thernal energy generated (MWH) 1250036 1250036 172769103

10. Gross electrical energy generated (MWH) 409441 409441.

55062852

11. Net electrical energy generated (MWH) 392123 392123 51710108

12. Reactor service factor 79.4 79.4 77.3

13. Reactor avo11obility factor 79.4 79.4 80.0

14. Unit service factor 77.2 77.2 74.7

15. Unit avo11obility factor 77.2 77.2 75.3

'i6.

Unit capacity factor (Using MDC) 68.5 68.5 60.8

17. Unit capacity factor (Using Des.MWe) 66.8 66.8 59.2

18. Unit forced outoge rate 22.0 22.8 8.5

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

20. If shutdown at end of report period,estinated date of startup NA 1The MDC nay be lower than 769 MWe during periods of high onbient tenperatste due to the thernal perfernance of the sprop canal,

$ UNOFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

n-APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEFebruarv 5 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241x192 MONTH Januor v 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

689.0 17, 793.0 2.

712.1 18, 720.8 3.-

730.8 19, 714.7

.4.

717.2 20, 756.2 5.

726.8 21.

793.1 6.

714.4 22.

795.5 7.

722.8 23, 801.7 8.

713.5 24.

717.9 9.

724,9 25.

687,5 10.

720.0 26, 758.7 11.-

713.5 27.

764.1 12.

716,1

28..

736.4 13, 722.4 29.

727,9 14, 710.0 30.

741.0 15.

762.4 31, 766.0 16, 794.7 t

INSTRUCTIONS On this forn, list the overage daily snit power level in ik-Net for each day in the reporting month. Compete to the nearest whole nanwatt.

These figures utIl be witd to plot a graph for each reporting r.enth. Note that when notinen dependable capacity is esed for the net electrical rating of the unit,there may be ettasiens when the daily average power level exceeds the

_10l% line (or the restricted power level line).In seth cases,the average daily snit power estput sheet should be festnoted to explain the apparent onently e

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEFebruarv 5 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224ix192 MONTH Jonoorv 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

583.0 17.

-9.5 2.

682.0 18.

-0.6 3.

779.1 19.

-8.6 4,

768.4 20.

-8.6 5,

743.4 21.

-9.0 6.

771.2 22.

81.5 7.

794.1 23, 538,0 8.

770.6 24, 562.6 9.

750.9 25, 41.1 10, 785.0 26, 478.7 ii.

762.5 27, 561.6 12.

771.1 20.

692.1 13, 788.5 29.

772.5 14.

784.4 30.

440.3 15.

78( i 31, 644.1 16.

192.8 INSTRUCTIONS On this fern, list the average daily unit power level in NWe-Net for each day in the reporting nonth. Compete to the nearts: whole negawatt.

Thesefigureswillbeesedtoplotagraphforeachrepertingnonth.NotethatwhenParinendependablecapacitvis there may be 4ccasions when the daily overage power level exceeds the 1HI line (or the restricted power level line).esed for the net electrical rating of the unit,In sich cases,the average daily festnettd to explain the apparent onenaly I

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' 10?/5A APPENDIX U QTP 300-S13 UNIT SillTTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-254 August 1982 UNIT NAME Quad-C' ies Unit 1 COMPLETED BY D Kimler DATE

-February 6, 1085 REPORT MONTil JANUARY 1985 TELEPl!ONE 309-654-2241 g

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DURATION E.

EVENT o"

w NO.

DATE (il0URS)

"o REPORT NO.

CORRECTIVE ACTIONS /C0 tit!ENTS ct 85-1 850104 S

0.0 B

5 IIA

-TURBIN Reduced load for Turbine tests.

85-2 850113 S

0.0 B

5 HA TURBIN Reduced load for Turbine te6ts.

85-3 850118 S

0.0 F

5 ZZ ZZZZZZ Reduced load to place the unit in EGC operation.

85-4 850119 S

0.0 B

5 UA TURBIN Reduced load for Turbine tests.

85-6 850124 S

0.0 F

5 ZZ ZZZZZZ Reduced load to place the unit in EGC operation.

85-7 850125 F

0.0 A

5 Cll

-PUMPXX Reduced load to repair 1C Reactor Feed-water Pump.

85-8 850127 S

0.0 F.

5 ZZ ZZZZZZ Reduced load to place the unit in ECC operation.

APPROYED

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AUG 1 G 1982 (final) y c. o 3 g

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-APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-265 August. 1982 UNIT'NAME Quad-Cities Unit 2 COMPLETED BY D Kimler DATE February 6, 1985 REPORT MONTil JANUARY 1985 TELEPl!ONE 309-654-2241 g

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DATE

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REPORT NO.

CORRECTIVE ACTIONS / COMMENTS g

85-1 850105 S

0.0 11 5

Cll PUMPXX Reduced load for Reactor Feedwater Pump changeover.

85-2 850108 S

0.0 B

5 IIA TURBIN Reduced load for Turbine tests.

85-3 850111 F

0.0 H

5 Cll llTEXCll Reduced load for Low Pressure Heater problems.

85-4 850114 S

0.0 B

5 CH INSTRU Reduced load to set Feedwater Level Controller.

85-5 850116 F

149.2 A

3

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HC XXXXXX Reactor scram on low Condenser vacuum due to failed boot.

~

85-6 850125 F

20.7 A

3 CC VALVEX Reactor scram due to #4 Control Valve fast closure during test.

85-7 850130 F

0.0 A

5 SB VALVEX Reduced load due to failure of High Pressure Coolant Injection Valve 2301-8 to operate during test.

APPROVED AUG 1 G PJ02 (final) y c. o 3 g

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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

' Relief ' valve operations during the reporting period are summarized

-in.the following table.. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Unit: Two Date: January 16, 1985 Valves Actuated: 2-203-3B No. & Type of Actuations:

1 Automatic Plant Conditions: Reactor Pressure - 1065 lbs Description of Events: Automatic Actuation Due to Pressure Spike B.

Control Rod Drive Scram Timing Data for Units 'l and 2 The basis for reporting this : data to the Nuclear Regulatory Commission are.cpecified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units 1 and 2 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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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DKlVES, FROM 1-1-85 TO 12-31-85 AVERAGE TIME IN SECONDS AT %

Max. Time INSERTED FROM FULLY WITHDRAWN For 90% '

Insertion DESCRIPTION NUMBER 5

20 50 90 Technical Specification 3.3.C.1 &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.

3. 3.C.2 (Average Scram insertion Time) 1-22 89 0.30 0.68 1.46 2.58 2.95 Unit 2 Sequence B Ilot Scram (G-9)

Timing i

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VII. REFUELING INFORMAT10N 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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0027H 0061Z

QTP 300-S32

~ ' '

Revision 1 I

QUAD-CITIES REFUELING liarch 1978 INFORMATION REQUEST c

. 1.

. Unit:

U Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

1-2-86 3

Scheduled date for restart folicwing refueling:

4-2-86 4.

Will refueling or resumption of operation thereafter require a technical specification chan'ge 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.

d' 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 WPPROVED r

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QTP 300-532 Revision 1 QUAD-CITIES REFUELING ltarch 1978 g

INFORMATION REQUEST 1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

3-16-85

3. _ Scheduled date for restart following refueling:

5-28-85 l

4.

Will refueling or resumption of operation thereaf ter require a technical I

- 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 IIcensing action and supporting Information:

Janua ry 31, 1985 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 assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

0

.i

['

8.

The present Itcensed spent fuel pool storage capacity and the size of any increase in IIcensed storage capacity that has been requested or is planned (s

-in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present Ilcensed capccity: 2003 W P P R O V. E D

.. APR 2 019'iG Q. C. O. S. R.

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VilI. 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 ATWS Anticipated Transient Without. Scram BWR Boiiing Water Reactor CRD Control Rod Drive Electro-Hydraulic Control System EHC

-~

E0F

_ Emergency Operations Facility GSEP Generating Stations Emergency-Plan HEPA-High-Efficiency Particulate FiIter High Pressure Coolant injection System HPCI_

HRSS-High Radiation Sampling System i

ilPCLRT_

Integrated Primary Containment Leak Rate Test

,IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCl; Low Pressure Coolant injection Mode of RHRS Local Power Range Monitor LPRM MAPLHGR ' -

Maximum Average Planar Linear Heat Generation Rate

~y Minimum Critical Power Ratio MCPR MFLCPR Maximum Fraction Limiting Critical Power Ratio L

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Maximum Permissible Concentration 2

MSIV Main Steam isolation Valve NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCl~

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. Preconditioning Interim Operating Management Recommendations PCIOMR RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor i.

RCIC Reactor. Core Isolation Cooling System RHRS Residual Heai Removal System l

RPS Reactor Protection System RWM' Rod Worth Minimizer S8GTS~

Standby Gas Treatment System Standby Liquid Control i

S8LC Shutdown Cooling Mode of RHRS SDC SDV-Scram Discharge Volume

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SAM Source Range Monitor

-TBCCW Turbine Building Closed Cooling Water System TIP Traversing incore' Probe

' Technical Support Center TSC L

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l Commonwealth Edison Outd Citi:s Nuclair Power Stati n 22710 206 Avenue Nodh Cordova, Illinois 61242 Telephone 309/654-2241 NJK-85-37 February 1, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Centlemen:

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 January 1985.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION N. J. Kalivianakis I

Station Superintendent bb Enclosure h

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