Text

Monthly Operating Repts for Oct 1986
	ML20213G075
Person / Time
Site:	Quad Cities
Issue date:	10/31/1986
From:	Robey R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	RAR-86-37, NUDOCS 8611170313
	Download: ML20213G075 (23)
	v • d • e

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i QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT OCTOBER, 1986 COMMONHEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 0027H/0061Z 8611170313 861031 DR ADOCK 05000254 PDR

I 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 i

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.

Glossary 0027H/0061Z

I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed 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 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 i

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 Carol Kronich, telephone umber 309-654-2241, extensions 2240 and 2157.

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0027H/0061Z i

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II.

SUMMARY

OF OPERATING EXPERIENCE s

A.

Unit 1 7'

__ r October 1-16 Unit 1 began the month of October holding load at approximately 650 MWe due to the 1D Main Steam Line out of service. On October 2, at 0000 hours0 days 0 hours 0 weeks 0 months , load began a drop to 250 MWe.to repair the 1D MSIV. At 1240 load began a normal increase towards full power.

Eight hundred fifteen MWe was reached on October 4 at 1410.

On October 6, at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , load was dropped to 750 MWe to switch the Condensate pumps. At 0140 load was in-creased to full load. At 1415 load was dropped to 780 MWe to.' perform instrument maintenance on the EHC pressure regulator. At11520 load was increased to full power. On October 8, at 0133 hours0.00154 days 0.0369 hours 2.199074e-4 weeks 5.06065e-5 months , the, unit was placed on Economic Generation Control (EGC). At 0630 EGC was tripped' and load was increased to full power. The unit returned to EGC opera-tion on October 10 nt 0905.

The unit was taken off of EGC at 0805, and load was increased to iull power. On October 15, at 0040, the unit returned to EGC operatio'n.

At 1615 the unit was taken off of EGC at 810 MWe.

Load was dropped to 767 MWe for maintenance on the EHC pressure regulator on October 16, at 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months . At 1042 the Reactor a: rammed due to Instrument Mechanic testing on the EHC pressure regulator.

l' October 17-31 f

On October 17, at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months , unit startup commenced. At 0504 the Reactor went critical, and the unit was placed on line at 1230.

Full power was reached at 1835 on October 20 after a normal load increase. The unit.was placed on EGC at 1955.

EGC was tripped at 2327.

On October 22, at 0807, load was increased to full load. On October 23, load was dropped to 770 MWe for Condensate pump maintenance. At 1025 load was increase <J to full load. At 1400 the unit was placed on EGC.

On October 24, at 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months , the unit was taken off ECC at 79 $1We.

The unit returned to ECC at 0135 on October 25.

OnOctober27,at1628,glje unit was taken off of EGC.

The unit returned to EGC operation between 1935 and 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months . On October 28, at 0525, the load was increased from "

790 MWe to 815 MWe, Load was held until October 31, at 0043, when the unit was placed on EGC.

The unit remained on EGC for the remainder of October.

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Unit 2 t

October 1-10 Unit 2 began the montti of October holding load at full power. On October I

4, at3451, the cinit was placed in EGC operation.

ECC was tripped at 1340 hours0.0155 days 0.372 hours 0.00222 weeks 5.0987e-4 months on October.5.

Load was increased to 780 MWe at 1440. At 2320 load was dropped to 715 MWe for Turbine surveillances. On October 6, at 0215, load was increased towards full load. At 0315 load was held at 770

.s MWe dus to Condensate Demineralizer differential pressure. At 0400 load

' '.E was drepped to 400 MWe to perform maintenance on the Condensate L

Demineralizers. At 0600 load was increased to full power. Full load was reached at 0735. At 1646 the Reactor scrammed due to low level signal transient during instrument maintenance testing.

i On October 7, at 0050, unit startup commenced. The unit went critical at 0600, and was placed on line at 1250. Load reached 800 MWe at 1710 on October 8.

At 1805 load was dropped to 650 MWe for Xenon transients.

At 2045. load was increased towards full load.

Seven hundred eighty MWe was reached on October 9 at 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months .

On October-10, at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , load began a drop at 140 MWe/ hour in preparation for the refueling' outage. The Turbine was tripped at 0036 on October 11, and at 0131 the unit was manually scrammed. The unit

' remained shutdown for the remainder of October for the End of Cycle Eight Refueling and Maintenance Outage.

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

Amendments to Facility License or 'fechnical 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 1 and 2 during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Frevent Repetition.

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0027H/0061Z

t UNIT 1

MAINTENANCE SUhWARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUIEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION i

Q52574 1-1001-65A RHR The 1A RHR Service As all ECC Systems were The action to prevent re-Service Water Water Pump inboard operable & the other currence falls under Action Pump - Replaced seal was leaking containment cooling Item Record (AIR) 4-85-8.

i Inboard Seal &

while the pump was loop was available, This involves analysis of i

Bearing running which safety implications primary pump cavitation of l

caused an instan-were minimal.

the RHR Service Water Pumps.

l taneous over-l current tripping the pump.

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0027H/0061Z A

UNIT 2

MAINTENANCE SlANARY

'i CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NLAEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION There were no Safety Related Work Requests to be recorded for Unit 2 for the reporting period.

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I 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 l

to the reportable occurrence reporting requirements as. set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.

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Unit 1 l

I Licensee Event Report Number Date Title of Occurrence 86-28 10-3-86 RCIC Trip Throttle Valve Tripped 86-29 10-2-86 Control Room Vent Isolation From Toxic l

Gas (Invalid) 86-30 10-16-86 Unit 1 Reactor Scram Unit 2 Licensee Event Report Number Date Title of Occurrence 86-12 10-6-86 Reactor Scram Due to l

Level Transient I

l 86-13 10-11-86 MSIV Local Leak Rate i

Test Failure 86-14 10-12-86 Local Leak Rate Tests From All Valves and Penetrations Exceeding Technical Specification

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Limits 86-15 10-13-86 Failure of Unit 2 Integrated Leak Rate Test 86-16 10-25-86 Invalid Service Water Effluent Sample 0027H/0061Z

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i V.

DATA TABULATIONS

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The following data tabulations are presented in this report:

lf A.

Operating Data Report i

i B.

Average Daily Unit Power Level i

C.

Unit Shutdowns and Power Reductions l

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0027H/0061Z

OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATENOVEMBER 6 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 OPERATING STATUS 0000 100186 1.

Reporting period:2400 103106 Gross hours in reporting period:

745 2.

Currently authorized power 1cvel (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 726.6 4973 7 101635.1 2

6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 720.2 4083.8 98163.3 D.

Unit reserve shutdown hours.

0 0 0.0 909.2 2

9.

Gross thernal energy generated (MWH) 1670573 1i436287 206401444

10. Gross electrical energy generated (MWH) 552422 3752369 66871740

11. Net electrical energy generated (MWH)

__ 527475 3578031 62605361

12. Reactor service factor 97.5 68 2 00.1 1

13. Reactor availability factor 97.5 68.2 02.0

14. Unit service factor 96.7 66.9 77.4

15. Unit avo11ob111ty factor 96.7 66.9 78.1 16.-Unit capacity factor (Uning MDC) 92.1 63.0 64.2 l

17. Unit capacity factor (Using Des.MWe) 09.7 62.2 62.5

19. Unit forced outoge rate 3.3 1.9.

5.7 l

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

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20. If shutdown at end of report period,estincted date of startup NA

$0NOFFICIAL COMPANY NUMBERS ME USD IN THIS REPORT r

- - _ - -. ~. _ _., -

[._

OPERATING DATA REPORT DOCKET NO.

50-265 l

UNIT TWO

]

DATENOVEMBFR 6 1986 l

COMPLETED BYCAROL L KRONICH i-TELEPHONF(309) 654-2241 OPERATING STATUS 0000 i00186 1.-Reporting period 2400 103186 Gross hours in reporting period 745 l.

2.

Currently authorized power level (MWt): 2511 Max. Depend copocity (MWa-Net): -769* Design electrical rot ing (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 226.3 6440.0 97715.7 I

6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 l

7.

Hours generator on line 222.2 6401.5 94699.1 l

D.

Unit reserve shutdown hours.

0.0 O 0 702.9 t

9.

Gross thernal er rgy generated (MWH) 500249 15230676

_201339699

10. Gross electrical energy generated (MWH) _

161137 4942510 64359292

11. Net electrical energy generated (MWH) 151494 47a7963 60602222

12. Reactor service factor 30.4 80.4 77.6

13. Reactor avo11obility factor 30.4 88.4 79.9

14. Unit service factor 2228 87.7 75.2

15. Unit avo11obility factor 29.0 07.7 75.7

16. Unit capacity factor (Uning MDC) 26.4 04 3 62.6 u

17. Unit capacity factor (Uning Des.MWe) 25.0 82.1 61.0

18. Unit forced outage rote 7.6

.7 7. 7_

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

20. If shutdown at end of report period,estinated date o f s t ar t u p _ _ l_-3-8 7______

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$UN0FFICIAL COMPANY NUMERS ARE USED IN THIS REPORT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATENOVEMBER 6 1986 COMPLETED BYCAROL L KRONICH TELEPl10NE(309) 654-2241 l

MONTH October' 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

634 6 57.

151.0 1

2.

400.6 18, 503.2 3.

713.3 19.

733.0 4,

774.7 P0.

796.5 5,

775.3 P1.

846.9 6.

789.6 P2.

695.3 7.

785.6

?3.

769.6 8.

775.7 P4.

752.5 9.

790.6 25.

740.0 10.

767.5 P6.

761.9 ii. __

754.8 P7.

742.7

12. _

770.2 PB.

775.3

13. _

757.5__

P9.

775.5 14.

771 1 30.

780.2 15, 761.1 31, 740,9 16, 331,7 INGTRUCTIONS On this forn, list the overage daily snit power level in IWe-Net for each day in the reporting nenth Conpete to the nearest whole negewett.

These figures will be esed to plot a graph for each reporting nonth. Note that when noxinen dependable capacity is used for the net electrical rating of the snit,there ney be occasiens when the daily everage power level exceegs the 1983 line (or the restricted powr level line).In such cases,the everage daily snit power entpet sheet sheeld be festnoted to explain the opperent onenely l

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APPENDIX B AVERACE DnILY UNIT POWER LEVEL DOCKET NO.

50-265

)

UNIT TWO DATENOVEMBER 6 1986 l

COMPLETED BYCAROL L KRONICH l

i TELEPHONE (309) 654-2241 i

MONTH October-1906 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' (MWe-Net)

(MWe-Net)

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L 1.

769.3 37.

-9,3 i

2.

767.5

$8.

~-8.2 I

3.

781.8

$9.

~8.3 4.

750.7 P0.

-7.3 5.

720.3 P1.

-6.0 6.

498.?

PP.

-7.1 7.

146.9 P3.

-7.2 8.

615.5 P4.

-6.5 9.

708.2 PS.

-6.i 10.

624.7 P6.

-7.5 11.

-10.1 P7.

-6.5 12.

-9.0 P8.

-6.4 13.

-8.0 P9.

-6.3 14.

-8.0 30.

-6.5 15.

-8.0 31.

-6,2 0

L 16.

-9.2 INGTRUCTIONG On this fern, list the overage dolly unit power level in MWe

t for each day in the reporting nenth.Conpete to the nearest whole negewett.

These figures will be used to plot a graph for each reperting nonth. Note that when notinen dependable copecity is used for the net electrical rating of the snit,there nny be occasions when the daily eseroge power level exceeds the 1981 line (or the restricted power level line).In such cases,the average daily unit power eetpet sheet shield be festneted to explain the opperent onenely

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

050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C. Kronich DATE November 7, 1986 REPORT MONTil OCTOBER 1986 TELEPil0NE 309-654-2241 N

H et y$

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O LICENSEE o

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EVENT 8"

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DATE (110URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS oo 86-32 861002 S

0.0 A

5 CD VALVEX Reduced load to 250 MWe to repair 1D MSIV 86-33 861016 F

24.8 B

3 86-30 HA INSTRU Reactor scram due to EHC pressure regulator (Instrument Maintenance testing)

APPROVED AUG 1 G 1982 (final) ygg3g

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ID/SA 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 C. Kronich DATE November 7, 1986 REPORT MONTil OCTOBER 1986 TELEP110NE 309-654-2241 N

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DURATION d

EVENT

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u NO.

DATE (ll0URS) o REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

86-40 861005 S

0.0 B

5 HA TURBIN Reduced load to 715 MWe for Turbine surveillances 86-41 861006 F

0.0 B

5 HH DEMINX Reduced load to 400 MWe due to Condensate Demineralizers 86-42 861006 F

18.4 H

3 86-12 IA XXXXXX Reactor scram due to low level signal transient during Instrument Maintenance testing 86-43 861008 F

0.0 H

5 RC FUELXX Reduced load to 650 MWe for xenon transients 86-44 861011 S

203.8 C

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

)

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VI.

UNIQUE REPORTING REQUIREMENTS 1

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The following items are included in this report based on prior commitments to the commission:

I A.

MAIN STEAM RELIEF VALVE OPERATIONS l

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:

2 Date: October 6, 1986 Valves Actuated No. & Type of Actuation 2-203-3B 1 Automatic 2-203-3C 1 Automatic I

Plant Conditions: Reactor Pressure - 1100 Description of Events: Automatic actuation due to pressure spike following Group I Isolation 4

i.

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Unit:

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Date: October 11, 1986 Valves Actuated No. & Type of Actuation 4

2-203-3A 1 Manual j

2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual 1

Plant Conditions:

Reactor Pressure - 919 Description of Events:

Surveillance Technical Specification 4.5.D.l.a B.

CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS 1 & 2 i

The basis for reporting this data to the Nuclear Regulatory Commission are specified 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 l

and 2 Control Rod Drive Scram Timing for the reporting period. All scram j

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 R00 DRIVES, FROM 1-1-86 TO 12-31-86 AVERAGE TIE IN SECONDS AT %

MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION NIABER 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) 4-6-86 177 0.29 0.68 1.46 2.58 2.95 Unit 1 Ilot Scram Timing (J-10) 4-18-86 88 0.30 0.66 1.41 2.49 3.08 Unit 2 ilot Scram Timing - A Sequence

( 11 - 1 1 )

e 9-6-86 88 0.29 0.66 1.42 2.52 2.88 Unit 1 flot Scram Timing - A Sequence (K-7) 0027H/0061Z

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.

0027H/0061Z

QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST f

1.

Unit:

Q1 Reload:

8 Cycle:

9 2.

Scheduled date for next refueling shutdown:

9-14-87 3

Scheduled date for restart following refueling:

12-21-87 4.

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

i NOT AS YET DETERMINED.

4 5

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

AUGUST 21, 1987 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.

l l

a.

Number of assemblies in core:

724 l

b.

Number of assemblies in spent fuel pool:

1894 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 0

b.

Planned increase in licensed storage:

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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- - -, - - - - - + -,, - - -,,, _,.. -. -,

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t QTP 300-532 Revision i QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

3-5-88 3

Scheduled date for restart following refueling:

1-19-87 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: YES -

TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPLHGR CURVES),

MCPR OPERATING LIMIT, AND A LICENSE AMENDMENT TO MOVE SINGLE LOOP OPERATION INTO I5"$duNddaesWorsu'bmittingproposedlicensingactionandsupporting SP 5.

Information:

SUBMITTED SEPTEMBER 18, 1986.

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 AT PRESENT TIME.

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

987 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 l

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 APPROVED l APR 2 01978 C). C:. <>. si. Ft.

L

F

-s 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 Standcrds Institute APRM Average Power Range Monitor ATHS Anticipated Transient Without Scram BWR Boiling Nater Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System 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 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 i

MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve i

NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System j

RHRS Residual Heat Removal System j

RPS Reactor Protection System RWM Rod Worth Minimizer i

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 l

TIP Traversing Incore Probe TSC Technical Support Center 1

)

0027H/0061Z i

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i Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654-2241 RAR-86-37 October 29, 1986 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Document Control Desk 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 October, 1986.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION f

f C2<M6

.(w R.A.kbey Services Superintendent bb Enclosure A[ ?

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0027H/00612

ML20213G075

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