ML20097F480

Monthly Operating Rept for Aug 1984

ML20097F480
Person / Time
Site:	Quad Cities
Issue date:	08/31/1984
From:	Kalivianakis N, Kimler D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-84-260, NUDOCS 8409190012
Download: ML20097F480 (28)

Text

_ _ - _. _ _ _ _ _ _ _. _ _

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1984 C(NM0 WEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 ko!M254 PDR

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r, TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.. Un i t 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 Infonnation VIII. Glossary

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I.

INTRODUCTION

. 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 Company and Iowa-Illinois Gas & Electric Company.

The Nuclear Stean Supply Systens 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 fo r Uni t Two.

This report was canpiled by Becky Brown and Dave Kimler, telephone number 309-654-2241, extensions 127 and 192.

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One August 1-17: Unit One began the month shutdown for End of Cycle Seven Refueling and Maintenance.

On August 16, at 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />, the unit was critical and on August 17, at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, the unit was on line.

August 18-31: On August 25, at 0726 hours0.0084 days <br />0.202 hours <br />0.0012 weeks <br />2.76243e-4 months <br />, the unit scrammed on high APRM flux caused by a pressure spike that was generated by the rapid opening and closing of a Turbine Bypass Valve. On August 26, at 1914 hours0.0222 days <br />0.532 hours <br />0.00316 weeks <br />7.28277e-4 months <br />, the unit was critical and on August 27, at 0503 hours0.00582 days <br />0.14 hours <br />8.316799e-4 weeks <br />1.913915e-4 months <br />, the unit was on line. On August 28, at 1352 hours0.0156 days <br />0.376 hours <br />0.00224 weeks <br />5.14436e-4 months <br />, the unit scrammed on Main Steam Line High Flow caused by an Instrunent Mechanic's failure to fill the reference leg of the transmitter. At 2139 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.138895e-4 months <br /> the unit was critical and on August 29, at 0314 hours0.00363 days <br />0.0872 hours <br />5.191799e-4 weeks <br />1.19477e-4 months <br />, the unit was on line.

B.

Unit Two August 1-6: Unit Two began the month operating at full power. On August 4, at 2105 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.009525e-4 months <br />, load was dropped to 400 MWe to perform MSIV quarterly testing. On August 5, at 1044 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.97242e-4 months <br />, the unit scrammed due to a one-half scram from loss of the 2B RPS MG Set coupled with a one-half scram from the partial closure of two MSlV's.

On August 6, at 0204 hours0.00236 days <br />0.0567 hours <br />3.373016e-4 weeks <br />7.7622e-5 months <br />, the unit was critical and at 0852 hours0.00986 days <br />0.237 hours <br />0.00141 weeks <br />3.24186e-4 months <br />, the unit was on line.

August 7-19: On August 12, 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 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br /> the unit began a normal load increase to full power. On August 19, at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />, load was dropped to 700 MWe for weekly Turbine tests. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> the unit began a normal load increase to full power.

August 20-31: On August 24, at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, load was dropped to 700 MWe for Reactor Feed Pump changeover. At 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, the unit began a normal load increase to full power.

On August 26, at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br />, load was dropped to 700 MWe to perform weekly Turbine tests. At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, the unit began a normal load increase to full power.

s III.

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

Amendments to Facility License or Technical Specifications On June 6, 1984, the NRC issued Amendment 88 to License DPR-29 and Amendment 83 to License DPR-30. These Amendments establish time delays on Trip Level Settings for initiation of Primary Containment isolation by means of High RCIC Steamline Flow and High HPCI Steamline Flow.

A time delay of greater than or equal to 3 seconds, but less than or equal to 10 seconds was implemented. These Amendments also establish changes to the Minimum Test and Calibration Frequency Tables pertinent to these Core Cooling Systems including a verification of the time delay setting.

On August 8, 1984, the NRC issued Amendment 90 to License DPR-29 This Amendment establishes the implementation of Analog Trip Systems in the Reactor Low Water Level, Reactor Water Level, HPCI High Steam Flow and HPCI Steam-line Low Pressure Instrumentation.

It also establishes the installation of level switches and related instrumenta-tion in the Scram Discharge Volumes. This includes changes to the pertinent Reactor Protection System Instrumentation Requirements, Logic Systems Functional Tests, and Minimum Calibration Frequencies Tables.

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 Unit One and Unit Two 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.

I UNIT ONE MAICTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION l

Q35034 84-2 Outboard

'B' Valve leaks; not Reference LER 84-2.

Cleaned'the seat and Feedwater Check seating properly.

tested satisfactorily.'

Valve Q35135 84-7 RHR Service Leak; pipe The leakage encountered The penetrations were Water Vault vibration.

was small enough that repai red for startup.

Penetrations the vault sump pump could easily handle the flow in the unlikely event of condensate pit flooding.

Q36392 84-2 Valve A0 l-Leak; improperly The in-line valve, A0 Adjusted stroke.

2001-4 adjusted stroke.

1-2001-3, would have performed PCI function.

Reference LER 84-2.

Q36585 1/2 Diesel Terminal The results of this The terminals were Gene ra tor connection on the deviation were minimized relocated to a larger Voltage Pegged

'A' phase of the because two off-site box to prevent over-High powe r _ t rans fo rme r lines and the Unit I heating on all three burned. See DVR and Unit 2 Diesel Diesel Generators.

84-43.

Generators were available.

Q28421 RHR Service improper seating if backflow through the The Check Valve was Water Pump of the valve disc.

pump was detected, the replaced.

Discharge Check pump could have been Valve

'A' isolated with the I-1001-3A valve.

O

UNIT ONE MAINTENANCE'

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION.TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION w28423 RHR Service improper seating if backflow through The Check Valve was Vater Pump of the valve disc.

the pump was detected, replaced.

Discharge the pump could have Check Valve been isolated with the

'C' l-1001-3C valve.

I Q31467 HPCI Testable Disc would " hang-This line could be Rebuilt valve, lapped l

Check Valve up" during testing, isolated remotely seats and relocated (Disassemble using valves M0 1-hinge pin bearing

& Rebuild) 2301-9 or M0 1-2301-8.

Inserts.

l Q3196 Replace Cables Cracked insulation Both Squib Valves Replaced cables with to Standby on cables to SBLC maintained continuity, cracked insulation.

Liquid Control Squib Valves.

therefore, the safety Squib Valves consequences of this occurrence were mininel.

Q32927 84-2 Valve M0 l-Leaks; improper Reference LER 84-2.

Valve was cleaned and 220-1 seating of valve leakage was reduced to disc.

an acceptable value f.pr startup.

Q33174 34-2 2D MSIV Leaks; improper The other in-line MSIV Valve was rebuilt and seating of the would have limited the leakage through this valve plug.

leakage to an acceptable valve was reduced to value. Reference LER an acceptable value for 84-2.

startup.

Q33176 84-2 IC MSIV Leaks; improper Reference LER 84-2.

Valve was rebuilt and seating of the leakage was reduced to valve plug, an acceptable value for startup.

O

UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q33178 84-2 IB MSIV Leaks; improper Reference LER 84-2.

Valve was rebuilt and seating of the leakage was reduced to valve plug.

an acceptable value for startup.

Q33183 84-2.

M0 1-220-2 Leaks; improper Reference LER 84-2.

Valve was rebuilt and seating of leakage was reduced to valve disc.

an acceptable value for startup.

Q36594 84-2 2C MSIV Leaks; improper Reference LER 84-2.

Valve leakage was seating of reduced to an acceptable valve plug.

value for startup.

Q36674 Unit 1/2 Battery charger The consequences of installed new silicone 250 Volt would not give this occurrence were controlled rectifiers Battery Charger correct output.

minimized because Unit and diodes; adjusted (trips when I was shutdown. The charger for correct turned on; Unit 2 battery charger output.

install new was cross-tied to Unit Silicone I. The 1/2 battery Controlled charger was returned to l

Rectifiers and service within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

l Diodes)

I Q36690 84-12 1/2 'B' Standby Incorrectly placed Reference LER 84-12.

Rewired and replaced Gas Treatment jumpers caused control transformer.

Heater - replace secondary side of Performed a Drawing cont rol t rans-control transformer Change Request so former & rewire.

to be grounded.

drawings would reflect more accurately what existed at the heater.

UNIT ONE.

' MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

.W.R.

LER OF ON ACTIGN'TAKEN TO 1

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q36767 1-1601-33C Leaks; dirt and No effects on safe Seat was cleaned. Test Vacuum Breaker sand in seating ope ra t ion. Leak was was performed again on surface.

.found during testing.

the following day.

Test (Q05 1600-5) was successfully conducted the next day.

Q36833 Relay 590-102D An out of adjust-Defect was found during Adjusted lever arm on of MSIV IC -

ment lever arm on testing. No effect on 28 switch and MStV Does not " pick-2B switch.

safe operation. Test was scram functional was up" During successfully performed performed.

Testing later on the same day.

Unit I was shutdown.

Q29142 IB RHR Service Cavitation.

Pump still performed its Replaced pump casing.

Water Pump intended function.

Casing - Replace Q32777 HPCI Oil Sump -

Water infiltra-The unit was shutdown Replaced gasket.

Investigate &

tion from gasket for refuel and HPCI was repair--over-between tube and not required.to be flowing and is shell of heat

operable, white & milky.

exchanger.

Q32815 84-13 1-203-3E Coil failure from The other Elec*.romatic Rebuilt actuator.

Electromatic excessive Relief Valves would have Relief Valve vibration.

provided an adequate Failed to Open flowpath.

During tianual Actuation e

UNIT ONE MA10TENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF-ON ACTION TAKEN TO I

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION q33365 84-21 Perform IHSI Believed to be Welds treated with All welds, except three, on Specified IGSCC induced lHSI were not 100%

had lHSI performed on Welds on Reactor indications.

through-wall.

them, as per NUTECH, Recirculation Reference LER 84-21.

Inc. Engineers.

and RHR Piping i

Q36130 84-2 A0 1-2001-16 Stroke was out Reference LER 84-2.

The leakage was brought of adjustment to an acceptable value causing valve prior to startup.

l to fail LLRT.

I q36629 84-1 A0 1-203-2B Improper seating Reference LER 84-2.

Leakage was reduced to l

(MSIV).

of valve disc an acceptable value caused valve to prior to startup.

fail LLRT.

Q36892 1A RHR Pump Leaks; seal faces Unit was shutdown &

Replaced mechanical Seal worn.

leakage was minimal.

seal.

Q36982 Valve M0 1-Motor mount for Unit I was coming up Installed new motor.

2301 valve M0 1-2301-48 from refueling and Motor Mount was found to be HPCI was not needed, is Broken broken.

1 i

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q36691 84-12 1/2

'A' Standby Poor drawings caused The SBGT Trains were Replaced control Gas Treatment improper placement repaired within the transformer and changed Train Heater of a temporary required 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, prints to' reflect what jumper.

Reference LER 84-12.

actually exists.

Q36743 84-9 DC Solenoids on Air solenoid valves The coils failed in a The faulty coils were the Outboard

'A' had failed DC coils, safe direction. When replaced and all MSIV

& 'B' MSIV's the 'B' RPS bus failed, DC solenoids were (2-203-2A & 2B) these valves went shut tested.

causing a Reactor scram. Reference LER 84-9 Q36870 Valve M0 2-An undetected The valve did not fail, The valve was rewired 1001-29A mistake was found in it just had the potential correctly.

(rewire) the anti-hammer for hammering.

circuit when a new Reference Unit I LER EQ operator (without 84-14.

brakes) was installed.

Q36871 Valve MO 2-An undetected The valve did not fail, The valve was rewired 1001-298 mistake was found in it just had the correct y.

l (rewi re) the anti-hammer potential for circuit when a new hammering. Reference EQ operator (without Unit 1 LER 84-14.

brakes) was installed.

Q36981 M0 2-2301-10 Motor pinion gear on Unusual Event (GSEP)

Shaft and keyway were Will Not Limitorque operator was declared due to drilled with an in-Close had loose set screw RCIC being inoperable dentation to lock key which allowed key to and there was a delay on shaft.

fall out.

in testing & PCI due to this valve.

Reference DVR 4-2-84-46.

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1 UNIT WO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON

' ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT nEPETITION Q30933 595-112B (PCI Relay was stuck in Relay failed in the~

Replaced the relay.

Group i Relay) de-energized safe direction by position.

giving a 1/2-isolation signal.

Relay for the other channel prevented a full isolation.

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IV. 1.'ICENSEE 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 occurrence reporting svequirements

_ as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technicall Specifications.

UNIT ONE A

Licensee Event Report Number Date Title of Occurrbnce.,

Standby Gas Treatrent ~

84-12 8-2-84 System 'A' and 'B!

Trains,_ inoperable, 84-13 8-8-84 ECCS Signal From improper Backfilling ofwinstrument Lines

\\

84-14 8-8-84 MO l-1001-29A and 298 s,

!Fallure 84-15 8-25-84

Reactor scram -- APRH

'di' Flux Due to. Pressure 4

Spike s,

s 84-16 8-28-84 Reactor scram - 'Hain_

Steamline Hi Flow x

84-17 8-17-84 South SJAE Velves incorrectlyinstaQ{d s

UNIT TWO

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5 84 8-5-84' Reactor scra., -- 2B Reactor Protection System MG Set Trip i

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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

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OPER ATINC DATA REPORT DOCKET NO.

50-254__ _

UNIT ONE D ATESgn.t, i2 COMPLETED BYDAVE KIHLER TELEPHONE 309-654-2241X192 OPERATING STATUS 0090. TW)4 L.

Reporting period:2400 Ob3 84 Gross hours in reporting period:

744 2.

Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 7694 Design electrical roting (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 reacior was critical 530.8 1892.9 d5448.5 6.

Reactor reserve shutdown hours 0,0 0.0 3421.9 7.

Hours generator on line 282.0 1843.2 H2191.1 8.

Unit reserve shutdown hours.

0,0 0,0 909,2 9.

Gross ther mol energy generated (MWH) 436851 4096583 169203289

10. Gross electrical energy generated (MWH) 147522 1360670 54619286

11. Net electrical energy generated (MWH) 136965 1281172 50887139

12. Reactor service factor 44.5 32.3 79.2

13. Reactor ovollobility factor 44,5 32.3 B2.4

14. Unit service factor 37.9; 31,5 76,2

15. Unit ovallobility factor 37,9 31,5 77.0 16, Unit capacity factor (Using MDC) 23;9 28,5 61.3

17. Unit copocity factor (Using Des.MWe) 23,3 27,7-59,8

18. Unit forced outage rote 13.4 2.3 5,2

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

20. If shutdown at end of report period, estimated date o f s t ar t u p _ _ _N_A________,

8The MDC not be lever than 769 MWe daring periods of high ambient temperatsre due to the thernal perfernonce of the spray canal.

$ UNOFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

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OPERATING DATA REPORT L

DOCKET NO.

50-265 UNIT TWO a.

9 DATESgot. 12 m

COMPLETED BYDAVE KIMLER TELEPHONE 309 >54-2241Xi92 OPERATING STATUS 0000 080184

1. Reporting period:2400 083184 Gross hours in reporting period:

744

2. Currently authorized. power level (MWt): 2511 Max. Depend capacity

. MWe-Net): 769* Design electrical-rating (MWe-Net): 789

)

(

-3.

Power level to which' restricted (if any)(MWe-Net): NA

4. Reasons for restriction-(if any):

This Month Yr.to Date Cunulative

'5.

Number of hours reactor was critical 728.7 4293.8 82211.3 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8

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~

on-line 721.9 4176.9 79306.6~

7. Hours generator 0.. Unit reserve shutdown hours.

0. 0_

0.0 702.9

9. Grossuthernal energy generated (MWH) 1749867_

9849890 165231978

~

.10.

Gross electrical energy generated (MWH) 554982 3174072 52609852

.11.

Net electrical energy generated (MWH) 528825 3023454 49357514 c[ 'i2.

Reactor service factor 9-7. 9 73.3 76.8

'i3. Reactor availability factor 97.9_

73.3 79.6

14. Unit service' factor 97.0 71.3 74.2

15. Unit avo11ob111ty'foctor.

97.0 71.3 74.9 m

'16. Unit capacity factor (Using MDC) 92.4 67.2 60.0

17. Unit copacity factor-(Using Des.MWe) 90.1 65.4 58.5 18.1 Unit' forced outage rate 2.1 3.8 8.4

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

20. If shutdown-at end of report period,estinated date of star tup ___NA 8The MBC not be lwer then 769 MWe dering perleds of high anbient tenperatere due to the thernal perfernece of the sprey canel.

St31 OFFICIAL COWAllY NUMBERS ARE USED IN THIS REPORT

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATESept. 12 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 MONTH Aunust 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-7.4 17.

-18.8 2.

-0.0 18, 74.7 3.

-0.3 19, 274.3 4.

-7.7 20.

413.3 5.

-8.7 21, 533.0 6.

-10.0 22.

-617.5 7.

-11.7 23, 695.1 8.

-11.6 24.

608.3 9.

-11.0 25, 170.7 10.

-10.0 26.

-$2.8 11.

-10.1 27, 279.5 12.

-10.2 28.

260.7 13.

-10.0 29, 432.3 14.

-9.5 30, 647.2 15.

-9.3 31.

726.8 16.

-13.1 INSTRUCTIONS On this fern, list the overage daily snit power level in Me-Net for each day in the reporting nonth Compete to the nearest whole negawatt.

These figsres will be ssed to plot a graph for each reporting nonth. Note that when narinen dependable conocity is ssed for the net electrical rating of the snit there nay be occasions when the daily overage power level ' xceeds the e

186% line (or the restricted power level line),In such cases,the average daily snit power evtput sheet should be footnoted to explain the apparent anonaly

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO l

DATESept. 12 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92

' MONTH-

'Avaust 1984 DAY' AVERAGE DAILY POWER. LEVEL DAY AVERAGE DAILY POWER LEVEL

'(MWe-Net)

(HWe-Net) 1.

761.3 17.

756.8

'2.

759,8 18, 766.3 3.

756.7 19.

730.9 4.

738.0 20.

751.9

-5.-

158.1 21.

762.5 6.-

256.1 22.

756.2 7.

594.8 23, 768.6 8.

716.5 24.

755.6 9.

746.5 25, 762.3 10.

752.1 26, 736.0 1i.

752,3 27.

767.9 12.

724.8 28, 780.0 13.

746.3 29.

755.0 14.-

755.5 30.

760.0 15. -

758.7 31.

768.4 11 6.-

759.5

' INSTRUCTIONS'

.On this forn, list the overage daily snit power level in Mlle-Net for each day in the reporting nonth. Compute to the nearest whole negewett.

.These figeres will be esed to plot a graph for enth reporting nenth. He'e that when noxinen dependable capacity is used for the net electrical reting of the snit,In such cases,the average daily snit power evtput sheet sheeld b

19g1 line (sr the restricted power level line).

feetnoted to explain the apparent onenely

M M

M M

M M

M M

M M

M M

M M

M M

M y

ID/SA APPENDIX I)

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

050-254 August 1982 UNIT NAME quad-Cities Unit One COMPLETED BY D. Kimler DATE September 4, 1984 REPORT HONTil AUGUST 1984 TELEPIIONE 309-654-2241 9

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5 gm Gm LICENSEE m@

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Q hM DURATION EVENT o"

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NO.

DATE (110URS)

REPORT NO.

CORRECTIVE ACTIONS /COHHENTS a

ca 84-15 840824 S

0.0 B

5 Cli VALVEX Reduced load to 600 MWe for Heater Control Valve Adjustment.

84-16 840825 F

35.2 A

3 84-15 HE VALVEX Reactor scram - Turbine Bypass Valve opened and shut rapidly causing pressure spike and Hi APRM Flux.

84-17 840828 F

7.8 H

3 84-16 CC INSTRU Reactor scram - Instrument Mechanic

' failed to fill reference leg of flow transmitter on Main Steam Line.

APPROVED AUG 1 G 1982 (final)

~

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M M

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ID/5A APPENDIX D QTP 300-S13 UNIT SilVTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. _05D-265 August 1982 UNIT NAME _ quad-Cities Unit Two COMPLETED BY D. Kimler DATE September 4. 1984 REPORT HONTil AUGUST 1184 TELEPit0NE 309-654-2241 N

g w"

B

$59 gm Ww g$

Q M

LICENSEE m@

w DURATION d

EVENT gu v

0 NO.

D, ATE (Il0URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS ct 84-29 840804 5

0.0 B

5 CD VALVEX Reduced load to 400 MWe to perform Main Steam Isolation Valve Quarterly Tests.

84-30 840805 F

15.3 A

3 84-9 CD VALVEX Reactor scram due to 28 Reactor Protection System MG Set trip and tiSIV closure.

84-31 840812 S

0.0 B

5 liA TURBIN Reduced load to perform weekly Turbine tests.

84-32 840819 S

0.0 0

5 HA TURBIN Reduced load to perform weekly Turbine tests.

84 840824 S

0.0 H

5 CH PUtiPXX Reduced load to changeover Reactor Feed Pump 84-34 8h0826 S

0.0 B

5 HA TURBIN Reduced load to perform weekly Turbine tests.

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 dellef 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.

-Valves No. & Type Plant Unit Date Actuated Actuations Conditions Description of Events 1 17-84 1-203-3A I Manual Rx Press Surveillance Technical 1-203-3B-1 Manual 940 Specification 4.5.D.I.b 1-203-3C 1 Manual (Post Maintenance) 1-203-3D

.i Manual (Rep, laced Pilot Valves) 1-203-3E I Manual 4

T c.

e 3

s.

VI.

UNIQUE REPORTING REQUIREMENTS (continued)

B.

Control Rod Drive Scram Timing Data for Units One and Two The basis for reporting this data to the Nuclear Regulatory

-Commission are specified in the surveillance requirements,f Technical Specifications 4.3.C.I and 4.3.C.2.

The following table is a complete summary of Units One and Two

~

Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with Reactor pressure greater than

'800 psig.

M

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1&2 CONTROL R0D DRIVES, FROM I-I TO 12-31-84 i

' 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.I &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.

3. 3.C.2 (Average Scram insertion Time) 8-19 177 0.28 0.67 1.45 2.55 3 39 Unit 1 Hot Scram Timing -

I (P-5)

A & B Sequence 3

s A

k I

]

VII.

REFUELING INFORMATION 1

The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandtsn

- (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Infomation",

dated January 18, 1978.

4

~d

i QTP 300-S32 l

Rsvision 1 I

QUAD-CITIES" REFUELING March 1978

~

INFORMATION REQUEST I

c 1.

Unit:

Q1 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

11-11-85 3

Scheduled date for restart following refueling:

1-20-86 4.

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

NOT AS YET DETERMINED.

5.~

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

SEPTEMBER 13, 1985, IF LICENSING ACTION REQUIRED.

6.

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

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

NONE PLANNED AT PRESENT TIME.

s d

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2062 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3657 b.

Planned increase in licensed storage:

0 9

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

-spent fuel pool assuming the present licensed capccity:

2003

T P P R C) V E C)

. APR 2 019'l3 C).c:.<>.Ei.Ft.

g*

QTP 300-S32 Rsvision 1 k

~

March 1978 QUAD-CITIES REFUELING i --

4 INFORMAT10N. REQUEST

]

e IJ 1.

Unit:

Q2 Reload:

7 Cycle:

8 J

2.

Scheduled date for next refueling shutdown:

3-18-85

]

3 Scheduled date for restart following refueling:

5-26-85 4.

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

Not as yet determined.

5.

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

P January 18, 1985, if licensing action required.

6.

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

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

y

'l)

All new fuel assemblies will be GE78-type (barrier clad, extended exposure design).

p 2)

A generic methodology was used for the analysis.of the Control Rod Drop Accident and Rod Withdrawal Error events.

p l

H A

7 The number'of fuel assemblies, a.

Number of assemblies in core:

724 e

b.

Number of assemblies in spent. fuel pool:

278 8.

The present licensed spent fuel pool storage capacity and the size of any increase in IIcensed storage capacity that has been requested or is planned in number of fuel assemblies:

l-a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

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

spent fuel pool assuming the present licensed capacity: 2003 XPPROVED y APR 2 01978 P

Q.C.O.S.R.

Pw. _. _ _

._.m._..

VI II.

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

Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Monitoring Anerican National Standards Institute ANSI Average Power Range Monitor APRM Anticipated Transient Without Scram ATWS Boiling Water Reactor BWR Control Rod Drive CRD Electro-Hydraulic Control System EHC Onen.jency Operations Facility E0F Generating Stations Emergency Plan GSEP High-Efficiency Particulate Filter HEPA High Pressure Coolant Injection System ilPCI High Radiation Sampling Systen HRSS Integrated Primary Containment Leak Rate Test IPCLRT Intennediate Range Monitor IRM Inservice Inspection ISI Licensee Event Report LER Local Leak Rate Test LLRT Low Pressure Coolant Injection Mode of RHRS LPCI Local Power Range Monitor LPRM Maximum Average Planar Linear Heat Generation Rate MAPLHGR Minimum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratio MFLCPR Maximum Pennissible Concentration MPC.

Main Steam Isolation Valve MSIV National Institute for Occupational Safety and Health NIOSH Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Water Systen RBCCW Rod Block Monitor RBM f -

RCIC Reactor Core Isolation Cooling Systen Residual Heat Removal Systen RHRS Reactor Protection Systen RPS Red Worth Minimizer RWM Standby Gas Treatment Systen SBGTS Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SDV Source Range Monitor SRM Turbine Building Closed Cooling Water Systen TBCCW Traversing Incore Probe TIP.

Technical Support Center TSC

\\

Commonwealth Edison Quad Citts Nucl:cr P:wer St:ti:n 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 NJ K-84-260 September 4,1984 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Canission Washington, D. C.

20555 Attention:

Document Control Desk Gentlemen:

Enclosed for your infomation is the Monthly Perfomance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of August 1984.

Very truly yours, COMMONWEALTH EDIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION

/

f

/

)Y N. J. Kalivianakis Station Superintendent bb Enclosu re 1824 ljt