ML20083A129

Monthly Operating Repts for Nov 1983

ML20083A129
Person / Time
Site:	Quad Cities
Issue date:	11/30/1983
From:	Kalivianakis N, Misak A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-83-446, NUDOCS 8312200176
Download: ML20083A129 (22)

Text

p-QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1983 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 8312200176 831130 gDRADOCK 05000254 PDR

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 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, INTRODUCTION Quad-Cities Nuclear Power Station is camposed of two Bolling 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 Cas & 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 condenser cooling method is a closed cycle spray canal, and 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 a

March 21,1972, respectively, pursuant to Docket Numbers 50-254 and 50-265. The date of initial reactor critica11 ties for Units 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit I and March 10, 1973 for Unit 2.

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

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_ __ ~.. _ _,

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Novembe r 1 -4 : Unit One began the month operating at full power and maintained this load until 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br /> on November 1, when the unit was manually scrammed due to the loss of the Turbine Building Closed Cooling Water System caused by a valving error.

At 0440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br /> on November 2, the Reactor became critical and remained critical until 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> when the Reactor scrammed due to a loss of pressure in the Scram Air Header caused by a valving error. The Reactor again became critical at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, and the unit was placed on line at 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />, at which time a normal load increase to full power was initiated.

November 5-10: At 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> on November 5, the unit dropped load from 800 MWe to 600 MWe due to low Off Gas flow caused by Off Gas combustion in the Steam Jet Air Ejector. At 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, the combustion was stopped by closing the primary jet suction to the 'A' Steam Jet Air Ejector, and a normal load increase was initiated. At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, the unit was again forced to drop load to 600 MWe due to high Main Condenser backpressure caused by operation with the ' A' Steam Jet Air Ejector primary Jet suction closed to prevent Off Gas combustion.

The unit held load at 600 MWe until 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br /> when a normal load increase was initiated. At 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />, on November 7, the unit dropped load from 810 MWe to 650 MWe to backwash a Condensate Demine ra l ize r.

At 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, backwashing was completed, and a normal load increase was initiated.

November 11-19: At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on November 11, the unit dropped load f rom 815 MWe to 550 MWe to change the Control Rod Pattern.

The Control Rod moves were completed by 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on November 12, and a normal load increase was initiated. At 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> on November 18, the unit dropped load from 815 MWe to 580 MWe due to Main Condenser vacuum problems caused by a Steam Jet Air Ejector Relief Valve lif ting.

At 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />, the valve was repaired and the unit began a normal load increase.

November 20-30: At 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on November 20, the unit dropped load f rom 810 MWe to 700 MWe to perform weekly Turbine tests.

At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the tests were completed, and a normal load increase was initiated.

l At 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> on November 27, the unit dropped load from 810 MWe to 700 MWe to perform weekly Turbine tests. The tests were completed at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, and a normal load increase was initiated. At 2l00 hours on November 29, the unit dropped load from 820 MWe to 700 MWe to switch

~

Condensate pumps.

At 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, the pump switch was completed, and the unit began a normal load increase.

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B.

Unit Two Unit Two remained shutdown throughout the month for End of Cycle Six Refueling and Maintenance.

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

Amendnents 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 Maintanance of Safety Related Equipaent The following represents a tabular summary of the major safety related maintenance performed on Unit 1 and 2 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.

l 1

I

UNIT OllE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q28222 1/2 Diesel The commutator was The fuel prime pump The commutator was Generator -

dirty.

motor would not run.

cleaned and the Fuel Prime Pump This did not make coupling was adjusted.

iiotor the Diesel Generator Pump operation was inoperable.

then verified.

Q29782 Shock Suppressor 10 CFR 21 Both SBGTs were The snubber was -replaced.

PSA#3 Hanger No.

notification of inoperable during M986-D97, on possible capstan snubber replacement.

SBGTS line 7509-

-spring degrada-24" (Sri 25170) tion.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTIGN TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q28849 250 Volt Bittery The cell failed the The whole 250 Volt The cell was replaced.

Cell #76 discharge test.

Battery still passed the discharge test even with Cell

1. 76 failure.

Q29128 2-599-24A ACAD Valve internals Valve leak 15.1 scfh Valve internals were Torus injection were fouled, at 48 psig pressure.

cleaned and its flex Check Valve preventing good Af ter repai rs it gasket was replaced.

seating.

leaked 0.0 scfh.

The valve was then successfully leak rate tested.

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Q29170 Sensor Removed input transistors The sensor had been Transistors Q1 & Q2 From 'B' Fuel Q1 & Q2 n the removed f rom the ARM were' replaced & the Pool ARM main amplifier and replaced with a sensor was source board were failed.

Red Tagged Spare on calibrated, and replaced Work Request Q29149 in the ARM.

Q29788 Reactor Bldg The sensor failed.

The moni tor read The sensor was replaced Fuel Pool 105 mr/hr. Radiation with a new: calibrated Channel

'B' Protection readings sensor. The monitor i

Monitor indicated normal was functionally tested, levels.

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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,.r trsuant 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 83-45/0lT 11-21-83 Generic Problem with Namco Limit Switches 83-46/03L 11-28-83 1C RHR Service Water Pump Out of Service UNIT TWO 83-19/03L 11-07-83 2A 24/48 Volt Battery Failed Discharge Test 83-22/0lT 11-15-83 Both MSIV Room Doors Open; Loss of Secondary Containment 83-23/03L 11-28-83 Main Steamline Hi-Flow Switch Setpoint Drift f

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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 I

0FERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEDecember i COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 110183 1.

Reporting period:2400 113083 Gross hours in reporting period:

720 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 Cumulative 5.

Number of hours reactor was critical 705.2 7640.4 82811.6 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 696.8 7517.2 79603.9 G.

Unit reserve shutdown hours.

0.0 0.0 909.2 9.-Gross thernal energy gencruted(MWH)

__ 1644743 17087388 163300379

10. Gross electrical energy generated (MWH) 538517 5539670 52661551

11. Net electrical energy generated (MWH) 508793 5210811 49039719

12. Reactor service factor 97.9 95.3 81.7

13. Reactor avu11obility factor 97.9 95.3 85.1

14. Unit service factor 96.8 93.8 78.6

15. Unit avullability factor 96.G 93.8 79.5

16. Unit capacity factor (Using MDC) 91.4_

04.4 62.9

17. Unit copucity factor (Using Des.MWe) 89.1 02.2 61.3

10. Unit forced outuge rate 3.2 2.2 6.3

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

20. If shutdown at end of report period,estincted d a t e o f s t a r t u p _ _ _ _N_A_ _ _ _ _ _ _ _

• The MDC ear be lower then 769 MWe during periods of high unbient tenperature due to the thernal perfernance of the spray canal.

$UNDFFICIAL COMPANY HUMBEFS ARE USE1) IN THIS REPORT

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEDecember i COMPLETED BYAlex Misak P

TELEPHONE 309-654-2241x194 OPERATING STATUS 0000 110183 1.

Reporting period:2400 113083 Gross hours in reporting period:

720 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 Cumulative S.

Nunber of hours reactor was critical 0.0 5654.1 77V17.5 6.

Reactor reserve shutdown hourc 0.0 0.0 2985.8 7.

Hours generator on line 0.0 5621.7 75209.8 0.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thernal energy generated (MWH) 0 10790594 155382088

10. Gross electrical energy generated (MWH) 0 3338245_

49135780

11. Net electrical energy generated (MWH)

-2494 31q 1_32J__

46334896

12. Reactor service factor 0.0 70.5 77.6

13. Reactor availability factor n.0 70.5 80.6

14. Unit service Factor 0.0 70.i 74.9

15. Unit avullability Factor 0.0 7n.1 75.6

16. Unit capacity Factor (Using MDC) 5 51.2 60.0 17, Unit capucity Fuctor (Using Des.MWe)

.5 49.9 58.5

10. Unit Forced outuge rate 0.0 10 8.6

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

20. If shutdown ut end of report period, estimated date o f s t ar t u p _. J.13-J_4_____

• The HDC ocy be Imr thcn 767 M'.'e dwing periods of high unblent temperature he to the therul performnce of the spny cuol.

$1NOFFICIAL 00FIANY N'MERS ARE USED IN Tills FEFORT

1 APPENDIX D AVERAGE DAILY UNIT POWER LEVEL POCKET No.

50-254 UNIT ONE DATEDecember i COMPLETED BYAlex Misak TELEPHONE 309-654-2241xi94 HONTH November 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

594.1 17.

763.1 2.

54.3 18.

712.4 3.

549.9 19.

755.7 4,

699.7 20.

752.9 5.

633 i 21.

749.7 6.

734.2 22.

778.3 7.

736.0 23.

765.2 8.

752,1 24, 769.5' 9.

763.1 25.

764.2 10, 762.9 26.

764.6 ii.

751,0 27, 750.2 12.

572.4 28 765.1 13.

661.7 29.

765.2 14.

601.1 30, 763.0 15.

602.6 16.

043.3 INSTRUCTIONS On this forn, list the average daily crit power level in HWe-Net for each day in the reporting nonth. Compete to the r.ecrest whole neamit.

These figures will be used to plot a graph for each reporting nonth. Note that when noninen dependable cepecite is tsed for the att electrical rating of the unit there noy be secosions when the daily overage power level exceeds the 1998 line (or the restricted power level line),.In soth cases,the overage daily snit power outpet sheet should be footnoted to explain the apparent cnonaly

APPENDIX B AVERAGE DAYLY UNIT POWER LEVEL DOCFET NO, 50-265 UNIT TWO DATEDecember i COMPLETED BYA_1_ex Mi.sak TELEPHONE 309-654-2241x194 MONTH Novanber 1933 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mue-Net)

(MWe-Net) 1.

-3.5 17.

-4.8 2.

-3.4 18.

-3,0 3.

3.4 19.

-4.9 4.

'3 20.

-4,9 5,

q,3 21.

-5.0 6.

-'.9 22.

-4,5 7.

-7.9 23.

-4.3 C.

--'.3 24,

-4.5 9,

-7.2 25.

-4.2 10.

-1.7 26.

-4.3 11.

-47 27

-4.4 4 5 12.

31. 0 20, 13.

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'9.

4,7 14.

E O 33

- 2,5 15.

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INSTRUCTIONS l

- En this forn, list the curage daily enit power level in We-Net for each day in the reporting month,Conpute to the r.earest whole nea witt, These figures will be used to plot c grcph for each repseting nonth, Note that when noximon d;cndable ccp2 cite is used for the net electrical rating cf the unit,In such cases,the overage daily unit pcwer output sheet shavi idZ line (:r the restricted pour level line).

foetnoted to explain t!.e cpprent anualy

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

050-254 August 1982 UNIT NAME Quad-Cities Unit One COMPLETED BY A. Misak DATE December 5, 1983 REPORT MONTil NGVEl1BER 1983 TELEPil0NE 309-654-2241 w

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DATE (IlOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

83-76 831101 F

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WG HTEXCH Reduced load due to Turbine Building Closed Cooling Water System Low Pressure 83-77 831101 F

13.8 G

2 WG HTEXCH Reactor scrammed due to loss of Turbine Building Closed Cooling Water System 83-78 831102 F

9.4 G

3 RB ZZZZZZ Reactor scrammed due to low scram air header pressure 83-79 831105 F

0.0 B

5 HC ZZZZZZ Reduced load due to low Off Gas Flow 83-80 831105 F

0.0 H

5 HC liTEXCH Reduced load due to high Condenser backpressure 83-81 831107 F

0.0 B

5 HG DEMINX Reduced load to backwash Condensate Demineralizers 83-82 831111 S

0.0 B

5 RB CONROD Reduced load to change Control Rod Pattern 83-83 831118 F

0.0 H

5 HC HTEXCH Reduced load due to Main Condenser Vacuum problems APPROVED 83-84 831120 S

0.0 B

5 HA XXXXXX Reduced load to pe'rform weekly Turbine tests AUG 1 G 1982

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

050-265 August 1982 UNIT NAME Quad-Cities Unit Two COMPLETED BY A. Misak DATE December 5, 1983 REPORT HONfil NOVEMBER 1983 TELEP110NE 309-654-2241 l

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CORRECTIVE ACTIONS / COMMENTS Q

83-66 830904 S

720.0 C

4 RC FUELXX Unit Two reamins shutdown for End of Cycle Six Refueling and Maintenance APPROVED AUG 1 G 1982 (final) y C.o d H

VI, UNIQUE REPORTING REI)UIRIMENTS

'Ihe following items are included in this report based on prior conmitments to the conmf ssion:

A.

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

B.

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

4 VII, REFUELING INFORMATION The following information about future reloads at Quai-Cities Station was requested in a January 26, 1978, licensing memorandtrn (78-24) from D. E, O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",

j dated January 18, 1978.

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QTP 300-S32 f.

Revision 1 QUAD-CITIES REFUELING March 1978

(

INFORMATION REQUEST 1.

Unit: _

Q1 Reload:

6 Cycle:

7 2.

Scheduled date for next refueling shutdown:

9-6-82

[

3 Scheduled date for restart following refueling:

12-18-82

i. Will refueling or resumption of operation thereaf ter require a technical i

specification change or other license amendment:

Yes 5

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

8-19-82: Tech. Spec. changes submitted to the NRC.

U 6.

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

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

a) All Tx7 fuel assemblies vill be removed from the core.

b) MAPLEGR curves for fuel types in the core are being extended to h0,000 MWD /ST.

c) MCPR limits vill be determined by GE's ODYN computer code.

d) The vessel pressure safety limit is being modified to acco==odate the

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potential for higher reactor pressures as c' alculated by ODYN.

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7 The number of fuel assemblies, a.

Number of assemblies la core:

724 b.

Number of assemblies in spent fuel pool:

1730 m

8.

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

increase in licensed storage capacity that has been requested or is planned in number of fuel assembiles:

d a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in licensed storage:

o (I'

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003

.ay' WPPROVED l APR 2.01978 Q.C.O.S.R.

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I QTP 300-S32 i

Rnvision 1 l --

I QUAD-CITIES REFUELING Harch 1978 f

INFORMATION REQUEST 1.

Unit:

Q2 Reload:

6 Cycle:

7 2.

Scheduled date for next refueling shutdown:

9-5-83 3

Scheduled date for restart following refueling:

11-12-83 4.

dIII refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment:

No, however, a change to the Technical Specifications is being submitted (see below).

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

~

June 14, 1983 (Scheduled) 6.

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

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

a) All new fuel assemblies will be of barrier design; MAPLHGR curves will be re-labeled to include the barrier designation.

b)

The use of 1.mproved assumptions in the load reject wi thout bypass analysis resulted in a much improved MCPR operating limit. Technical Specifications are being changed to provide this additional operating margin.

7 The number of fuel assemblies.

I a.

Number of assemblies in core:

0 b.

Number of assemblies in spent fuel pool:

1136 t'

8.

i '

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:

1 a.

Licensed storage capacity for spent fuel:

3897 0

b.

Planned increase in IIcensed storage:

The projected date of the last refueling that can be discharged to the 9

spent fuel pool assuming the present licensed capacity: 2003 XPPROVED r APR 2 01978 Q.C.O.S.R.

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VIII, CLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Monitoring American National Standards Institute ANSI Average Power Range Monitor APRM ATWS Anticipa ted Transient Without Scram BWR Boiling Water Reactor CBD Control Rod Drive EHC Electro-Hydraulic Control System EOF Ene rgency Operations Facility Generating Stations Emergency Plan CSEP High-Ef ficiency Particulate Filter H EPA HPCI High Pressure Coolant Injection System High Radiation Sampling System HRSS Integrated Primary Containment Leak Rate Test IPCLRT IRM Inteomediate Range Monitor ISI Inservice Inspection LER Liccasee 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 MS IV Main Steam Isolation Valve National Institute for Occupational Safety and Health NIOSH PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RB CCW 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 KRM Rod Worth Minimizer SBUIS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center

O - Commonwe:lth Edison s

) 22710 206 Avenus North xf-C Quad Citi:s Nucl ar Pcwer Station e2 Cordova, Illinois 61242

\\

Telephone 309/654-2241 NJ K-83-446 December 1, 1983 Director, Of fice of Inspection & Enforcenent 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 November 1983.

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

/d N, J. Ka11vlanakis Station Superintendent bb Enclosu re I

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