ML20214N419

Monthly Operating Repts for Aug 1986

ML20214N419
Person / Time
Site:	Quad Cities
Issue date:	08/31/1986
From:	Kronich C, Robey R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
RAR-86-30, NUDOCS 8609160283
Download: ML20214N419 (24)

Text

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f QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 I

MONTHLY PERFORMANCE REPORT AUGUST, 1986 COMMONHEALTH EDISON COMPANY AND IOHA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 8609160283 860831 PDR ADOCK 05000254 R

PDR fh 0027H/00612 j

r 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.

Glossary I

l 0027H/0061Z

i I.

INTRODUCTION t

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[

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

The Station is jointly owned by Commonwealth Edison I

l Company and Iowa-Illinois Gas & Electric Company.

The Nuclear Steam Supply i

Systems are General Electric Company Bolling 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 4

f numbers OPR-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 i

initial Reactor critica11 ties 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 number 309-654-2241, extensions 2240 and 2157.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One August 1-19 Unit One began the month of August on Economic Generation Control (EGC).

At 1505, on August 1, the unit was taken off of EGC at 800 MWe due to the Off Gas System. At 1625 the unit returned to EGC operation. On August 2, at 0010, the unit was taken off of EGC for Turbine surveillances, and returned to EGC at 0145. The unit remained in EGC operation on August 3, except for the hours between 0055 and 0155, when surveillances were being performed. The unit remained in EGC until August 5, at 0035, when load was dropped to 720 MWe to perform surveillances. At 0130 load began an increase to 750 MWe.

The unit returned to EGC at 0503.

On August 6 the unit remained on EGC except between 0030 and 0100, when surveillances were being performed.

On Augurc 7, at 1620, the unit was taken off of EGC to perform surveillances.

Fue unit was returned to EGC operation at 1713.

The unit remained in EGC operation until August 9, at 0020, while surveillances were being performed. The unit returned to EGC at 0228.

At 0340 the unit was taken off of EGC, and load was increased to full power. The unit remained at full power until August 10, at 0110, when the unit was placed in EGC. The unit was removed from EGC on August 11, at 1435.

Load was then increased to full power. At 1735 the unit was returned to EGC operation.

On August 12, at 0545, the unit was taken off of EGC and load was increased to full power. The unit remained at full power until August 13, at 1025, when the unit was placed on EGC.

The unit remained in EGC on August 14, except between 1612 and 1734, when the APRM's were being adjusted.

The unit remained in EGC operation until August 15, at 1255, when the unit was taken off of EGC and load was increased to full power. The unit returned to EGC at 1837. At 0110, on August 16, the unit was taken off of EGC to perform surveillances. The unit returned to EGC at 0205. On August 17, at 0245, the unit was taken off of EGC, and power was held at 745 MWe until 0822 when the unit returned to EGC.

At 1426 the unit was taken off of EGC until 1908, when it was returned to EGC.

The unit remained on ECC until August 18, when the unit was taken off of EGC at 1508, and later returned at 1620.

August 20-31 The unit remained in EGC operation until August 20 at 1000. Load was then increased to full power. The unit remained at full power until August 21, at 0857, when it was placed in EGC.

On August 22, at 0845, the unit was taken off of EGC until 0910 to perform control rod maneuvers.

At 1225 the unit was taken off of EGC, and load was increased to full power. At 0512, on August 23 load was decreased to within EGC limits and the unit was placed in EGC operation. At 05]2 the unit was taken off of ECC to perform Turbine surveillances.

Load was then held at 300 MWe until 1013, when the unit was placed in EGC operation.

0027H/0061Z

August 20-31 (cont.)

The unit remained in EGC until August 27, at 0640, while control rod maneuvers were being performed. The unit was. returned to EGC at 0930.

On August 28, at 0912, the unit was taken off of ECC and a unit shut-down commenced at 25 MWe/hr due to the 1A and 1D RHR Service Water Pumps being inoperable. The shutdown was terminated at 1630. Load began an increase towards full power. Load was held at approximately 800 MWe for the remainder of August.

l B.

Unit Two August 1-14 Unit Two began the month of August holding load near 800 MWe.

On August 2, at 0900, load began a drop to 750 MWe at the Load Dispatcher's request.

At 0926 the unit was placed on EGC. At 1400 the unit was taken off of EGC and load was increased to full power. On August 3, at 0330, the unit was placed in EGC operation. At 0500 the unit was taken off of EGC and load began a drop to 600 MWe at the Load Dispatcher's request. At 0755 load began an increase towards full power. On August 4, at 0110, the unit was placed in EGC.

EGC was tripped at 0800, and load was then increased to full load. The unit returned to EGC operation on August 5, at 0032. At 0825 the unit was taken off of EGC and load was increased to full power.

Load was held at full power until the unit was returned to EGC on August 6, at 1715.

On August 7, at 1820, the unit was taken off of ECC and load was dropped to 700 MWe to change the Reactor Feedwater Pump combination. At 1905 load began an increase towards full power. The unit was placed in EGC operation at 1945. The unit remained in EGC until August 9, at 0030.

The unit was taken out of EGC between 0030 and 0230 to perform Turbine surveillances. On August 10, at 0420, the unit was taken off of EGC, and load was dropped to 700 MWe to perform Condensate Demineralizer maintenance.

At 0920 load began an increase towards full power, and the unit was placed on EGC at 1630. On August 11, at 1435, the unit was taken off of EGC and load was increased to full power. Load remained at full power until August 14, at 0130, when load was dropped to 600 MWe to investigate EHC problems. At 1200 load began an increased to full power.

August 15-31 The unit remained at full power until August 23, at 0030, when load began a drop to 200 MWe at the Load Dispatcher's request. At 1105 load was being held at 280 MWe, At 1830 load began an increase to 400 MWe.

On August 24, at 1015,-load began an increase to 700 MWe. At 1551 load was decreased to 525 MWe to repair an oil leak on the 2C Reactor Feedwater Pump. At 1640 load began an increase to 700 MWe.

On August 25, at 0617, load was in-creased to full power. The unit remained at full power until August 30, at 0223, when the unit was placed in EGC operation. On August 31, at 0315, the unit was taken off of EGC and load was dropped to 740 MWe to change the Reactor Feedwater Pump combination. At 0345 the unit returned to EGC operation and remained on EGC for the remainder of August.

III.

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

Amendments to Facility License or Technical Specifications On August 11, 1986, the NRC issued Amendment numbers 95 and i

91 to Facility Operating License numbers DPR-29 and DPR-30, for Quad-Cities Nuclear Power Station, Units 1 and 2.

These Amendments incorporate surveillance requirements for a

the Residual Heat Removal (RHR) Vault Flood Protection Systems, which were recently installed for the RHR Service Water Sump g

j Pumps in the RHR Vault Rooms.

B.

Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

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C.

Tests and Experiments Requiring NRC Approval i

l There were no Tests or Experiments requiring NRC approval for the reporting period.

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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, j

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

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UNIT 1

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUhEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q42760 1-3903 Diesel The pump failed While testing the Unit The failed motor was Generator Cooling due to an 1 Diesel Generator, replaced with one not Water Pump electrical short the cooling pump exat:1y alike. An exact in the pump tripped immediately replacement motor will notor windings.

after the Diesel Genera-be installed within one This was a tor was started. The year.

result of cooling pump could not excessive wear be locally started. The in the front Unit 1 Diesel was tripped bearings but no off. All steps were taken cause for the to ensure operability of bearing failure the Unit 2 and Unit 1/2 could be found.

Diesel Generators. The 1/2 cooling water pump we.s lined up to supply cooling water to the ECCS room coolers.

Q50431 1-1601-32A No cause or While testing, the vacuum The valve and limit switches Vacuum Breaker problems could be breaker showed dual open/

were inspected and no found.

closed indication. This problems were found. The indicated the vacuum valve shaft was lubricated breaker had not fully and the vacuum breaker valve closed. However, further was stroked satisfactorily.

testing showed the required Drywell to Suppression Chamber differential pressure was maintained.

0027H/0061Z

UNIT 1

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QS0877 l-1201-2 Station personnel The heat shrink was Immediate action was to MO Valve failed to follow overlapped one inch in-install new heat ahrink manufacturer's stead of the required per the manufacturer's directions when two inches. However, instructions. Detailed installing Ray-analysis revealed that training for heat shrink chem heat shrink the valve operator would installation was given to on the valve still have performed its certain cognizant Station operator's power safety function.

personnel. An installation cables.

procedure is also being initiated.

1 Q50878 1-2419A Station personnel The overlaps were not done Immediate action was to j

Drywell High failed to follow per the manufacturer's in-install new heat shrink Radiation manufacturer's structions. This caused per the manufacturer's i

Detector directions when the heat shrink to not instructions. Detailed installing Ray-seal tightly to the leads training for heat shrink chem heat shrink of the Drywell Radiation installation was given to j

on the valve Monitors. Since the heat certain cognizant Station operator's power shrink would have per-personnel. An installation cables.

formed the necessary procedure is also being electrical insulating initiated.

function, the detectors were still operable.

Q50879 1-2419B See Work Request See Work Fequest Q50878 See Work Request Q50878 Q50878 Q50887 1-3706 M0 Station personnel The heat shrink was used Immediate action was to Valve failed to follow to cover splice components install new heat shrink manufacturer's that were larger than the per the manufacturer's directions when recommended maximum size instructions. Detailed installing Ray-component that could be training for heat shrink chem heat shrink heat shrink covered. How-

. installation was given to l

on the valve ever, the operator would certain cognizant Station operator's power still have performed its personnel. An installation cables.

safety function.

procedure is also being

]

initiated.

0027H/0061Z

UNIT 1

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUnBER NUhEER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q51384 1-1001-65C Cause of the failure The 1C RHR Service Water The immediate corrective RHR Service is stress induced Pump was declared in-action was to replace the Water Pump cracking of the seal operable. All redundant pipe nipple like-for-like.

Seal Water water line pipe safety systems were Long term corrective Line Nipple

nipple, verified operable.

action will replace the Failure rigid seal water line with a flexible-type line. This will lessen the affect of vibration induced stress on the seal water line components.

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0027H/0061Z

UNIT 2

MAINTENANCE

SUMMARY

~

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN T0 f

NURSER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION i

Q40936 85-05 2-1705-16A &

Noise induced The noise was causing A 50 microfarad, 50 VDC j

2-1705-16B Fuel by other an upscale spike and capacitor was installed Pool Radiation machinery was alarm of the Fuel Pool to dampen / filter out the Monitors affecting the Radiation Monitor, but noise in the signal j

monitor signal.

the monitor was still

cable, operable, j

Q50902 2-2419A Drywell Station personnel It was determined the New heat shrink material j

High Radiation failed to follow conductors were soundly was installed per manu-Detector manufacturer's insulated, and would facturer's instructions.

instructions for have been operable in Additional training was installing Ray-the radiation area given to Station personnel chem heat shrink.

harsh environment, and new installation procedures written.

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Q50903 2-2419B Drywell Station personnel It was determined the New heat shrink material High Radiation failed to follow conductors were soundly was installed per manu-Detector manufacturer's insulated, and would facturer's instructions.

instructions for have been operable in Additional training was installing Ray-the radiation area given to Station personnel chem heat shrink.

harsh environment.

and new installation l

procedures written.

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0027lI/0061Z

IV.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable cccurrence reporting requirements as set forth in sections 6.6.B.l. and 6.6.B.2. of the Technical Specifications.

I UNIT 1 Licensee Event Report Number Date Title of Occurrence 86-24 8-11-86 Unit 1 & Unit 2 RHR Service Water Piping Supports Exceed Code Stress Allowables 86-25 8-27-86 Torus Attached Piping Does Not Meet Code Stress Allowables UNIT 2 There were no Licensee Event Reports for Unit 2 for the reporting period.

0027H/00612

V.

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

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 0027H/00612

OPERATING DATA REPORT DOCKCT NO.

50-254 i

1 UNIT ONF DATESEPTEMBER 3 1906 i

COMPLETED BYCAROL L KRONICH_

TELEP HONE _(309 ) 654-2241 4

OPER ATING STATils 0000 080186

1. Reporting period 2400 083186 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 j

i

4. Reasons for restriction (if any):

1his Month Yr.to Date Cumulative 5.

Number of hours reactor was critical 744.0 360,,2.6 100264.0 i

6.

Reactor reserve shutdown hourc 0.0 0.0 3421.9

7. Hours generator on line 744,0 3544.5 96024.0 i

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Unit reserve shutdown hours.

0.0 0 _0 909.2 9.

Gross thernal energy generated (MWH) 1717321 0346547_

203311704

10. Gross electrical energy generated (MWH) 585150 2736505 65055876

11. Het electrical energy generated (MWH) 560043-2600395 61634920 i

12. Reactor service factor 100.0.

61.0 79.9

13. Reactor ovo11ob111ty factor 100.0 61.8 02,iZ

14. Unit service factor 100._0 60.0 77.2 l

15. Unit avo11obility factor 100.0 60.0 77.9 i

16. Unit capacity factor (Using MDC) 97.9-50.2 63.9 l

17. Unit capacity factor (using Des.MWe) 95.4 56 1 62.3 1

i

10. Unit forced outage rate 0.0 1.6

.5.7

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

20. If shutdown at end of report period,ectinated date o f s t a r t u p _ _ _ _!!A_ _ _ ___ __

3 UNOFFICIAL COMPANY HUMBERS ARE USED IN THIS REPORT j

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--+-+w--

7 m m

,s-,

y-w

-,_y--m.,--,-.--,,,p-,,,--y

-.,m,_,,-m,,--,,_,,..y,-,m,

,mwm,y,w. emmy,-,,-,%,,--,,,,,-

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT Ty0 DATESFPTEMBER 3 1916_

1 COMPLETFD BYCAROL t KRONICH i

TELFPHONE(309) 654-2241 OPERATING STATUS 0000 080186

1. Reporting period:g400 003186 Gross hours in reporting period 744

2. Currently authorized power Icvc1 (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 Cunulative

5. Nunber of hours reactor was critical 744,0 5501.7 96Zb9.4 I

6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 i

7. Hours generator on line 744,0 5459.3 93756.9 8.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thermal energy generated (MWH) 1776674 13011337

_199120360

10. Gross electrical energy generated (MWH) 57030ft 42P636?

636431.41 l

ii. Nct electrical energy gencroted(MWH) 546393 4015.303 59919642

12. Reactor service roctor 100.0 94.4 77.tZ l

13. Rcoctor ovo11obility factor 100.0 94.4 0 0_. t

14. Unit service factor 100.0 93.6 75 3 t

15. Unit availability factor 100.0_

93.6 75.9_

16. Unit capacity factor (Uning MDC) 95.5 90_tg

._62.6

17. Unit capacity factor (Uning Des.HWe) 93.1 87 2 61.0 3

l

10. Unit forced outage rate 01

.5 7.7

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

20. If shutdown at end of report period estinated dote of startup NA tVMEFICIAL COMPANY NUMERS ARE USED IN THIS REPORT i

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATESEPTEMBER 3 198b, COMPLETED BYC.A.RRL L KRONICH__

TELEPHONE (309) 654-224i MONTH Auaust 1986 DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

746.0 17, 742.0 2.

743.7

$8.

747.7 3,

755.9

$9.

735.0 4,

763.9 20, 764.4 5.

740.9 P1.

747.0 6.

764.4 P2.

757.2 7.

747.4 P3.

744.3 8.

756.8 24.

757.8 9.

708.6 25.

735.1 10.

745.4 26, 754.0 11, 750.6

?7.

756.5 12, 701.4

?B.

701.7 13, 774.3

?9.

727,9 14.

775.6 30, 764.5 15, 773.4 35.

760.8 16.

761.9 INSTRUCTIONG On this fored negewett. list the overage daily unit power level in Nie-Net for each day in the r nearest whol These figeres will be used te plot a oreph for each reperting senth, Netc that when noti 100% line (or the restricted power level line).In sich cases,the overage dolly unit powr setpet sheet should te fests ted to explain the apparent anopoly

APPENDIX B AV'2RAr;E DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATESEPTEMBER 3 1986 COMPLETFD BYCAROL L KRONICH TELEP HONEGO,9_) 654-2241 MONTH.

August 1906 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe -Ne t )

(MWe-Net) 1.

756.?

$7.

773.9 2,

755.4

18. __.

771.9 3.

693.3 19, 771.7 4,

754.9 P0.

705.9 5.

748.3 Pi, 762.0 6.

7(d.3 PP.

763.6 7.

725_._0 P3.

379.i 8.

7 43._R

?4.

547.9 9.

739,7 P5.

7P2 9 10.

720.0 P6.

74.8.9 ii. _

751.7 P7.

761.7 12, 770.0 P8.

777.0 13.

775.9 P9.

770 2 2

14, 695.3 30, 736.0 15.

769,5 31, 730.3 16.

77P.0 INSTRUCTIGHS On this fern, list the overage daily unit power level in lWe-Net for each day in the reporting ninth. Compete to the nearest whole necawatt.

These figsres will be vred to pir,t a graph for each reporting ninth. Note that when exinen dependable capacity is used for the net electrical rating of the init,there My be cccasions When the daily overage power level exceeds the ill% line (or the restricted power level line).In such cases,the average daily snit power evtput sheet sheild be feitnoted to explain the apparent anomaly

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ID/5A APPENDIX D QTP 300-S13 UNIT SifUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY C Kronich DATE September 2, 1986 REPORT MCaT11 AUGUST 1986 TELEPIIONE 309-654-2241 oOO w"

E

• W gw Wa a

h$

Q hM LICENSEE m@

w LURATION M

g EVENT

$u gu NO.

DATE (HOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS u

ao 86-30 860803 S

0.0 H

5 ZZ ZZZZZZ Reduced load to 600 MWe per Load Dispatcher 86-31 860807 S

0.0 B

5 CH PUMPXX Reduced load to 700 MWe to change Reactor Feedwater Pump combination 86-32 860809 S

0.0 B

5 HA TURBIN Reduced load to 700 MWe for Turbine surveillances 86-33 860810 S

0.0 B

5 HH DEMINX Reduced load to 700 MWe for Condensate Demineralizer maintenance 86-34 860814 S

0.0 A

5 HA XXXXXX Reduced load to 600 MWe to investigate EHC problems 86-35 860823 S

0.0 H

5 ZZ ZZZZZZ Reduced load to minimum load (200 MWe) as per Load Dispatcher 86-36 860824 S

0.0 B

5 CH PUMPXX Reduced load to 525 MWe to repair a Reactor Feedwater Pump oil leak APPROVED AUG 1 G 1982

, (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 There were no Main Steam Relief Valve Operations for the reporting period.

B.

CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TH0 There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

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/00612

.a

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

Unit:

01 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 re. fueling or resumption of operation thereafter require a technical specification change or other license amendment:

NOT AS YET DETERMINED.

i 5.

.,cheduled date(s) for submitting proposed licensing action and supporting Information:

AUGUST 21, 1987 6.

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

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

i NONE PLANNED AT PRESENT TIME.

t i

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 l

b.

Number of assemblies in spent fuel pool:

1896 8.

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

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

1 a.

t.icensed 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 XPPROVED

, APR 2 01978 Q.c.o.S.R.

--. m

.,r-,--

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

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

10-13-86 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:

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 TECHNICAL SPECUICATIONS'bmitting proposed licensing action and supporting 5.

Scheduled dateTs) Tor su information:

SEPTEMBER 19, 1986, IF 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.

7 The number of fuel assemblies.

a.

Number of assemblies in co-at 724 b.

Number of assemblies in sp 2nt fuel pool:

836 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 refue1Ing that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 XPPROVED APR 2 01978 Q.C.O.S.R.

~~-

,a-

.--,n,

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 Monttor ATHS Anticipated Transient Without Scram BWR Boiling Hater 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 MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RHM Rod 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 TBCCH Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center i

0027H/0061Z

s Commonwealth Edison Quad Cities Nuclear Power Station l

22710 206 Avenue North Cordova, lilinois 61242 M"

Telephone 309/654-2241 RAR-36-30 Septer:er 2, 1986 Director, Office cf Insoecticn $ Er fo :eme-!

Unite: 5tates Nuclear Reguli :ry C;mmt::!;n

.;a s n i ng ton, C. C.

20555 At anticn:

Cocument Contrai Den E n ' a s e :: far ycur info-3:ico i s :ne Mcn"'! y Pe -forman ;e Re;;cr:

- : <ering the coerition o','t;1-Cities '4;cieir P;aer Erdtion, Units

're 3nj inc. dJring the E nth of August 1936.

^

Re: ectfully, C wuCNnEALTH EDISON CCMPAN/

C R -CITIES NUCLEAR PCwER STATION

. d4dg R. A. Rcbey Services Sucerintendent 1

f bb Enclosure 1

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