ML20100A005

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Monthly Operating Repts for Feb 1985
ML20100A005
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/28/1985
From: Kalivianakis N, Kimler D
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
NJK-85-69, NUDOCS 8503250273
Download: ML20100A005 (22)
v • d • e


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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1985 COMMONWEALTH EDISON COMPAN" AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 I

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TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Chanties, 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 Fower Level C. Unit Shutdowns and Fower Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary 0027H 0061Z

I. INTRODUCTION Quad-Cities Nuclear Power Station is c(mposed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 K4e Net, located in Cordova, Illinois. The Station is jointly owned by Consonwealth 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 criticalities 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.

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'II. SUI 9tARY OF OPERATING EXPERIENCE A. Unit One

. February 1-10: -Unit One began the month holding load. On February

'2, at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, load was dropped to 700 MWe for weekly Turbine

' tests..'At 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> the unit began a normal load increase to place the unit on Economic Generation Control (EGC). On February 5, at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, load was dropped due to inoperability of the High Pressure Coolant Injection System (HPCI). At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> the unit began increasing load to- full power. On February 9, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, load was dropped to'700 MWe for weekly Turbine tests. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on February 10, the unit began a normal load increase to full power. i February 11-28: On February 11, at 2255 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.580275e-4 months <br />, load was dropped to place the unit on EGC. On February 15, at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, load was dropped and the unit was placed in HOT STANDBY to repair an EHC oil leak. At.0411 hours0.00476 days <br />0.114 hours <br />6.795635e-4 weeks <br />1.563855e-4 months <br />, on February 16, the Turbine was tripped. On February 17, at 0532 hours0.00616 days <br />0.148 hours <br />8.796296e-4 weeks <br />2.02426e-4 months <br />, the unit was. on-line. and increasing load

. to full power. - On February 23, at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />, load was dropped to place the unit on' EGC. ' On February 25, at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />, load was dropped to 700 MWe for a Reactor Feedwater Pump changeover. At 0910 hour0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />siload was increased to 740 MWe and the unit was placed on EGC.

B. Unit Two February 1-13: Unit Two. began the month increasing load at 5 MWe/

hour for fuel preconditioning following a load reduction to repair

' the~HPCI 2301-8 valve. On February 3, at.0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, load was dropped

. to 700 MWe for . weekly Turbine tests. At 0215' hours the unit began a normal load increase to full power. On February.8, at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />, 1

- - load was Ldropped to 700 MWe for a Condensate Pump changeover. At

1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> the unit began a normal load increase to full power. On L February -9, atn2200 hours. load was dropped to 600 MWe for a Control Rod Pattern adjustment.' 'At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, on February 10, the unit began a normal load increase to full power. On February 13, at 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />, load was dropped to repair a seal leak in the 2C Reactor Feedwater

. Pump. At 0835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br /> the unit began a normal load increase to full

'n power; February 14-28: On February 16, at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br />, load was dropped to -

600 MWe. for a Control Rod Pattern adjustment. At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, on February 17, the unit. began a normal load increase to full power.

- On February 19, at 0024 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the Reactor scrammed due to full closure of the 2B Outboard MSIV during bi-weekly testing. At 1712 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.51416e-4 months <br />, the Reactor.was critical and at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> the unit was on-line and increasing load to full power.

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III. 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

, Technical Specifications for the reporting period.

B. Facility or Procedure Changes Requiring NRC Approval g 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. porrective 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' 00612

tl UNIT - ONE MAINTENANCE

SUMMARY

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, CAUSE. -RESULTS & EFFECTS '

W. R - LER. ..

OF - ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION' PREVENT REPETITION ,

, .Q40205 Repaired . IIPCI Valve motor end ' Valve would not open Replaced end bell.

3 Cooling Return bell broken.. or close. HPCI Investigation by Valve 1-2301 - . remained operable. Technical Staff is 48 in progress to alleviate recurring problems.

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UNIT TWO- MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT 'MALFUNCT10N SAFE OPERATION PREVENT REPETIT10N Q37619 84-14 Adjusted Limit Closed side- Valve failed to open Adjusted limit Switches on HPCI limits of switch; completely. HPCI switches; stroked Steam Isolation set too close. declared inoperable successfully.three Valve 2-2301-4 for 25 minutes; timea.

minimal impact on sa fe ty.

Q40141 85-002 Repair HPCI Failed capacitor Drove MGU to its low Replaced capacitor.

. Motor Gear Unit in power supply speed stop. HPCI to signal declared inoperable convertor- for 115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br />.

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r-i IV. LICENSEE EVENT REPORTS The following is a tabular summaey 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 85-01 2-5-85 HPCI System Inoperable UNIT TIM 85-04 2-8-85 HPCI Room Cooler Motor Failure 85-05 2-19-85 Reactor Scram due to 2B MSIV Full Closure t 0027H 0061Z

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

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdcwns and Power Reductions 0027H 0061Z-

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OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATEMorch 5 1985 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92 OPERATING STATUS ~

0000 020185

1. Reporting period:2400 022885 Gross hours in reporting perlud 672
2. Currently authorized power level (MWt): 2511 Max. Depend copocity (MWe-Net): 769* Design electrical roting (HWe-Net): 789
3. Power level to which restricted (if any)(HWe-Net): NA
4. Reasons for restriction (if any):

This Month Yr.to Date Cunulative

5. Nunber of hours rendtor was critical 672.0 1416.0 89738.5
6. Reactor reserve shutdown hours 0.0 0.0 3421.9
7. Hours generator on line 646.7 1390.7 86426.0
8. Unit reserve shutdown hours. 0 . 0, 0.0 _

909.2

9. Gross thernal energy generated (MWH) 1484121 3207101 178953491
10. Gross electrical energy generated (MWH) 492048 1063922 57841373
11. Het electrical energy generated (MWH) 471714 1019578 53975280
12. Reactor service factor 100.0 100.0 79.9
13. Reactor ovallobility factor 100.0 100.0_ 03.0
14. Unit service factor 96.2 98.2 77.0
15. Unit ovalle.bility factor 96.2 98.2 77.8
16. Unit l capacity factor (Using MDC) _ 91_.3 93.6_ 62.5
17. Unit capacity factor (Using Des.MWe) G 9_._0_ _. 91_.] 602 9
18. Unit forced outage rate 3.8 i 8 _ 6. 0
19. Shutdowns scheduled over next 6 Months (Type, Dote,ond Duration of each ):
20. If' shutdown at end of report period,estincted date of startup ____

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8the MDC rey be luer then 769 MWe daring periods of high anbient temperatore due to the thernal perforne ce of the spray canal.

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OPER ATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATEMarch 5 1985 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 020185

1. Reporting period:2400 022885 Gross hours in reporting period: 672

-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):

lhis Month Yr,to Date Cumulotive

5. Number of hours reactor was critical 655.2 1246.2 86152.2 l
6. Reactor reserve shutdown hours 0.0 0.0 2985.8
7. Hours generator on line 650.4 1224.5 83273.7 8._ Unit reserve shutdown hours. 0.0 0.0 702.9
9. Gross thermol' energy generated (MWH) 1549629 2799665 174318732
10. Gross electrical energy generated (MWH) 505818 915259 55568670
11. Net electrical energy generated (MWH) 485301 877424 52195409
12. Reactor service factor 97.5 88.0 77.4
13. Reactor ovallobility factor 97.5 88.0 80.1
14. Unit service factor 96.8 86.5 74.8
15. Unit avo11cbility factor 96.8 86.5 75.4

~i6. Unit capacity factor (Using MDC) 93.9 80.6 61 . _0_

17. Unit capacity factor (Using Des.MWe) 91.5 78.5 59.4 10 '. Unit forced outage rate 3.2 13.5 8.5
19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):
20. If shutdown at end of report period, estimated dote of startup NA
' $The MDC nay be lower than 769 MWe during periods of high ambient temperatore due to the thernal perfernance of the spray canal, u

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATEMarch 5 1985 L COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224ix192 MONTH Februarv 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 783.9 17, 275.3 2.. 785.5 18, 578.5 3, 792.6 19 -762.8
4. 783.4 20, 781.9
5. 406.1 21. 728 i

'6. 676.6 22. 735,3 7.- 786.9 23. 734.7 G. 788'.3 24, 731.8

9. __ _ _ _ 794.8 _ 25, 729.5 10, 779.4 26. 735.2
11. 798.5 27. 780.5 12, 731.8 28, 867.8
13. 791.3

.14. 788.4 15 . . 778.2 16, 30.9 INSTRUCTIONS On this forn, list the overage daily snit power level in We-Net for each day.in the reporting nonth Compute to the nearest uhele necawatt.

These figures will be ssed to plot a graph for each reparting nonth. Note that when notinen dependable capacity is there may be occasions when the daily average power level exceeds the

~1981 used line for(orthe theret electrical restricted power rating levelof line). the snit,In such cases,the overage daily snit power evtput sheet should be footnoted to explain the apparent anonaly i

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APPENDIX B

~ AVERAGE DAILY UNIT POWER LEVEL.

h. , DOCKET NO. 50-265 UNIT TWO DATEMarch 5 1985=

COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224ix192

-MONTH 'Februarv 1985 DAY: AVERAGE-DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

-(MWe-Net)- (MWe-Net)-

Li. ; 779.7 17. 640.6

2. _ 790.0 18. 709.7 3.. 768.8 19. 10.0

.4 . 787.9 20. 493.5 5.. -790.8 21. 621.2 6.. -791.6- 22. 735.3

7. 790.0 23. 772.5 8.- -

774.4 24. 790.1

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-9. . 783.7 25, 784.4 10 .; 607.5 26. 776.0

11. = 730.0 27.- 793.9 t i2. - 787.1 28. 776.6 t

-13. -790.O V'

~' 14 . 771.1

15, 786.7 16.

783.4

-INSTRUCTIONS On this forn, list the average daily _enit power level in mie-Net for enth day in the reporting nonth. Compete to the nearest uhele neocuatt. -

These fitsres will be used to plot a graph for each reporting nenth. Note that when narinen dependable capacity is :

there nay be occasions when the daily everage pour level exceecs the

--esed ilgt line for (or the net electrical the restricted powerrating of the unit,In such cases,the overage daily snit pour satpet sheet should te level line).

festnoted to expl:ln the apperent onently

M M M m M M M M M M M R M M ID/5A APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME _ Quad-Cities Unit 1 COMPLETED BY Dave Kimler DATE March 5, 1985 REPORT HONTil FEBRUARY 1985 TELEPil0NE 309-654-2241 N $ g m" 5 E9 "m W.m

@ @ LICENSEE @ @

u w DURATION g"g EVENT $" o o

NO. DATE (IIOURS) o REPORT NO. CORRECTIVE ACTIONS / COMMENTS

, a 85-9 850202 S 0.0 B 5 HA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85-10 850204 S 0.0 F 5 XX ZZZZZZ Reduced load to place Unit on Economic Generation Control (EGC) i 85-11 850205 P 0.0 D 5 85-01 SF VALVEX Reduced load due to llPCI System inoper-ability 85-12 850209 S 0.0 B 5 HA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85-13 850211 S 0.0 F 5 XX ZZZZZZ Reduced load to place Unit on ECC 85-14 850215 S 25.4 B 9 llB XXXXXX Reduced load and placed Unit in 110T STAND-BY to repair EHC oil leak 85-15 850223 S 0.0 F 5 XX ZZZZZZ Reduced '_oad to place Unit in EGC 85-16 850225 S 0.0 11 5 CH PUMPXX Reduced load for Reactor Feedwater Pump changeover APPROVED AUG 1 G 1982 (final) ygg3g

M M M M M M M M M M M M ,

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ID/5A APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY Dave Kimler DATE March 5, 1985 REPORT MONTH FEBRUARY 1985 TELEPil0NE 309-654-2241 N $ g w" 5 $$U gw Ww

@ Q h LICENSEE m@ @

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% DURATION @ "

EVENT @v o NO. DATE (IIOURS) REPORT NO. CORRECTIVE ACTIONS / COMMENTS ca 85-8 850203 S 0.0 B 5 HA TURBIN Reduced lead to 700 MWe for weekly Turbine tests 85-9 850208 S 0.0 H 5 HC PUMPXX Reduced load to 700 MWe for Condensate Pump changeover 85-10 850209 S 0.0 H 5 RB CONROD Reduced load for Control Rod Pattern Adjustment 85-11 850213 F 0.0 A 5 CH PUMPXX Reduced load to repair seal leak on 2C Reactor Feedwater Pump 85-12 850216 S 0.0 H 5 RB CONROD Reduced load for Control Rod Pattern Adj us tment 85-13 850219 F 21.6 A 3 85-05 HB VALVEX Reactor scram due to 2B Outboard MSIV full closure during test APPROVED

AUG 161982 (final) ygg3g

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: One Date: February 16, 1985

. Valves Actuated No. & Type of Actuations 1-203-3A 1 Manual 1-203-3B 1 Manual 1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E l~ Manual-Plant' Conditions: Reactor Pressure - 940 lbs

. Description of Events: Surveillance Technical Specification 4.5.D.1.b

.B. ' Control Rod Drive Scram Timing Data for Units 1 and 2 The basis for reporting this data to the Nuclear Regulatory Commission are specified'in the surveillan;e requirements of Technical Specifica- -

tions.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 L

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 DRIVES, FROM 1-1 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.l &

DATE OF RODS 0.375 0.900 2.00 3. 5 7 sec. 3.3.C.2 (Average Scram insertion Time) 2-17 89 0.28 0.66 1.42 2.51 2.90 Unit 1 Sequence B Hot Scram Timing (D-2)

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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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.t QTP 300-S32

-  ! Revision 1

. QUAD-CITIES REFUELING liarch 1978 '

N,, INFORMATION REQUEST 1._ Unit: Q1 Reload: 7 Cycle: 8

2. Scheduled date for next refueling shutdown: 1-2-86 3 scheduled date for restart following refueling: 4-2-86
4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

m NOT AS YET DETERMINED.

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'5 scheduled date(s) for submitting proposed licensing action and supporting I P . Information:

da DECDIBER 19, 1985; IF LICENSING ACTION REQUIRED.

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6. _Important licensing considerations associated with refueling, e.g., new or

' different fuel design or supplier, unreviewed design or performance analysis y methods, significant changes in fuel desl 5n, new operating procedures:

8- NONE PLANNED AT PRESENT TIME.

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' 7 The number of fuel assemblies.

p- a. Number of assemblies in core: 724 li.

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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

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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.

, ; QTo 300-S32

,.  ! Revision 1 I

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QUAD-CITIES REFUELING March 1978 x, ,

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 I
4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

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Yes. A routine MAPLHGR amendm.ac has been submit'ted as a preparatory change

!j to allow a 10 CFR 50.59 review.

5 Scheduled date(s) for submitting proposed licensing action and supporting 8

. Information:

~'- Not Applicable.

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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:

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None planned at present time.

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1 l-i- 7 The number of fuel assemblies.

a. Number of assemblies in core: 724 o

-b. Number of assemblies in spent fuel pool: 0

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. 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
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.

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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 ATWS - Anticipated Transient Without Scram BWR -

Boiling Water Reactor CRD -

Control Rod Drive EHC - Electro-Hydraulic Control System i

EOF - Emergency Operations Facility

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 IRN - Inte_w diate 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 Main Steam Isolation Valve

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MSIV -

NIOSH - National Institute for Occupational Safety and Health

j. PCI - Primary Containment Isolation PCIOMR - Preconditioning Interist Operating Management Recommendations RBCCW - Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection System RWM -

Rod Worth Minimizer SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV -

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

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Quad Cities Nucle:r Power Stati:n O Commonwealth Edison 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 IlJ K-85-69 March 1, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Kashington, D. C. 20555 Attention: Document Control Desk Gentlemen:

Enclosed for your infomation is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of February 1985.

Very truly yours, COMM0islEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 6'

//- p- ,

fl. J. Kalivianakis Station Superintendent bb Enclosu re fhY

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