Text

Monthly Operating Repts for Sept 1984
	ML20093L501
Person / Time
Site:	Quad Cities
Issue date:	09/30/1984
From:	Kalivianakis N, Kimler D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NJK-84-298, NUDOCS 8410190030
	Download: ML20093L501 (27)
	v • d • e

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l QUAD-CITIES NUCLEAR POWER STATION l

UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1984 CMM0 WEALTH EDISON COMPANY l

AND IWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

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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 Stean Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Infonnation VIII. Glossary 4

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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 Steam Supply Systens are General Electric Company.

Boiling Water Reactors. The Architect / Engineer was Sargent &

l. undy 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 campiled by Becky Brown and Dave Kimler, telephone number 309-654-2241, extensions 127 and 192.

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SUMMARY

OF OPERATING EXPERIENCE A.

UNIT'ONE 1 September 1-30: Unit One began the month reducing load as requested by the Load Dispatcher.- At 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months the unit was holding load at i.

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500 MWe. On September.7, at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months , the unit began a normal load increase to full power. On September 8, at 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months , load was reduced.to 700'MWe for Turbine weekly tests. At 0225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months the unit began a normal increase to full power.. On September 13, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , load was dropped to 700 MWe for a condensate pump changeover.

At 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months the unit began a normal load increase to full power.

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On September 14, at 1610 hours0.0186 days 0.447 hours 0.00266 weeks 6.12605e-4 months , load was dropped to 300 MWe due to Recombiner fires. At 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months , the unit began a normal load increase to full power.

On September 18, at 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months , load was dropped to 650 MWe per the Load Dispatcher. At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months 1oad was t

j' increased to full power. On September 21, at 0930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months , load was l

l dropped per the Nuclear Engineer for a special control rod maneuver.

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- At 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months the unit began a aormal load increase to full power.

On September 30, at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months , load was dropped to 700 MWe for l

weekly Turbine tests. At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months the unit began a normal load-Increase to full power.

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UNIT TWO September 1-8: Unit Two began the month at full power. On September 2, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , load was dropped to 700 MWe for weekly Turbine tests.

At 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months the unit began a normal load increase to full power. On September 3, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , load was dropped to 700 MWe per the Load Dispatcher. At 1950 hours0.0226 days 0.542 hours 0.00322 weeks 7.41975e-4 months load was ' Increased to 750 MWe. At 2220 hours0.0257 days 0.617 hours 0.00367 weeks 8.4471e-4 months , load was dropped to 650 MWe to perform Turbine nightly and-MSIV 81-Weekly ' tests. On September 4, at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months , the init began a normal load increase to full power. On September 6, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , load was dropped to 600 MWe per the Load Dispatcher. At 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months .

l load was increased to 730 MWe. At 1045 hours0.0121 days 0.29 hours 0.00173 weeks 3.976225e-4 months tests were performed on l

the Economic Generation Control System. At 1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months the' unit began a normal increase to full power. On September 7, at 1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months , load was dropped to 730 MWe.for EGC testing. At 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months the unit began a normal increase to full power. On September 8, at 2230 hours0.0258 days 0.619 hours 0.00369 weeks 8.48515e-4 months , load was dropped for weekly Turbine tests.

September 9-30: On September 9, at 0930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months , the unit began a normal load increase to full power. On September 13, at 1352 hours0.0156 days 0.376 hours 0.00224 weeks 5.14436e-4 months , l

load was dropped to 759 MWe to turn off the 28 Circulating Pump.

On September 14, at 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months , load was dropped to minimum load, the i

l Generator was turned off, and Turbine Overspeed Tests were performed.

At 1909 hours0.0221 days 0.53 hours 0.00316 weeks 7.263745e-4 months the Generator was synchronized and at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months , the unit was at 200 MWe. At 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months , on September 17, the unit began a normal load increase to full power. On September 19, at 1205 hours0.0139 days 0.335 hours 0.00199 weeks 4.585025e-4 months ,

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.4 B.

UNIT TWO September 9-30: -(Continued) load was dropped 10 HWe for a problem with the HPCI 2J01-4 valve.

The problem was resolved and at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months load was increased to full power. On September 23, at 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months , load was dropped to 700 MWe for Turbine weekly tests. At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months the unit began a normal load increase to full power. On September 30, at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months , load was dropped to 700 We for weekly Turbine testa. At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months the unit began a normal load increase to full power.

III.

P. ANT OR PROCEDlRE CHANGES. TESTS EXPERIMENTS AND SAFETY R ELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

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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 App" oval r

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 molntenance 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.

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LI'dENSEE EVENT REPORTS

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The following is.a tabular summary of all licensee event reports for Quad-Cities Units One and:Two occurring during the reporting gy

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period,- pursuant to the-reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.

k UNIT ONE Licensee Event Report Number Date Title of Occurrence 84-18 9-22-84 standby Gas Treatment 84-18A 9-24-84 Auto-Start UNIT TWO There were no Licensee Event Reports for Unit Two for the reporting period.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON

' ACTION TAKEN T0-NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION 034506 84-5 Weld Overlay

'J' Unknown. Suspect Leak would have been

-The cracks were Jet Pump Riser IGSCC induced detected prior to repaired and a weld' (02J-S3) indications.

pipe break.

overlay was performed as designed by Nutech Engineers, Inc.

Q34582 84-5 Weld Overlay 'M' Unknown. Suspect Indications were not The indications were Jet Pump Riser IGSCC induced 100% through-wall, weld overlayed as (02M-S3) axial Indications, designed by Nutech Engineers, Inc.

Q34645 84-5 Weld Overlay

'C' Unknown. Suspect Indications were not The indications were Jet Pump Riser IGSCC Induced 100% through-wall.

weld overlayed as (02C-S4) indications, designed by Nutech.,

Engineers,-Inc.

Q34646 84-5 Weld Overlay

'J' Unknown. Suspect Indications were not A weld overlay was Jet Pump Riser IGSCC induced' 100% through wall.

performed as designed (02F-S4) axial indications.

by Nutech Engineers, Inc.

Q34722 84-5 Weld Overlay 'D' Unknown. Suspect Indications were not A weld overlay was Jet Pump Riser IGSCC induced 100% through wall.

performed as designed (02D-S4) axial indications.

by Nutech Engineers, Inc.

Q34723

~84-5' Weld Overlay 'G' Unknown. Suspect.

Indications were not A weld overlay was Jet Pump Riser IGSCC induced 100% through wall.

performed _as designed (02G-S4) indications.

by Nutech Engineers, Inc.

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. i UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q34889 84-5 Weld Overlay

'E' Unknown. Suspect Leakage would have A weld overlay was. _

Jet Pump Riser IGSCC induced been detected and the perforned as designed (02E-S4) indications.

Unit. shutdown prior to by Nutech Engineers, 4

pipe break.

Inc.

Q349to 84-5 Weld Overlay 'B' Unknown. Suspect Leakage would have A weld overlay was Jet Pump Riser IGSCC induced been detected and the perforced as designed (02B-S10) indications.

Unit shutdown prior to.

by Nutech Engineers, pipe break.

Inc.

Q34947 84-5 Weld. overlay 'G' Unknown. Suspect Leakage would have A weld overlay was Jet Pump Riser IGSCC induced been detected and the performed as designed (02G-S3) indications.

Unit shutdown prior to by Nutech Engineers, pipe break.

inc.

Q34948 84-5 Weld overlay

'J' Unknown. Suspect Leakage would have A weld overlay was Jet Pump Riser IGSCC induced been detected and the perforned as designed (02J-S4) indications.

Unit shutdown prior to by Nutech Engineers, pipe break.

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Q34949 84-5 Weld overlay

'J' Unknown. Suspdct Leakage would have A weld overlay was Jet Pump Riser IGSCC induced been detected and the performed as designed i

(02J-F6) axial indications.

Unit shutdown prior to by Nutech Engineers,

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pipe break.

Inc.

Q34950 84-5 Weld Overlay 'H' Unknown. Suspect Leakage would haveL A weld overlay was Jet ? ump Riser IGSCC induced been detected and the performed as. designed (02H-S3) indications.

Unit shutdown prior to by.Nutech Engineers, pipe break.

Inc.

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t UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

.W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT-MALFUNCTION SAFE OPERATION PREVENT REPETITION 434951' 84-5 Weld Overlay. 'H' Unknown.' Suspect Leakage wauld have A weld overlay was Jet Pump Riser IGSCC induced been detected and the performed as designed (02H-S4) axial indications.- Unit shutdown prior to by Nutech Engineers,-

pipe break.

Inc.

Q35048 84-5 Weld Overlay 'K' Unknown. Suspect Leakage would have A weld overlay was Jet Pump Riser IGSCC induced been detected and the performed as designed-(02K-S3) indications.

Unit shutdown prior to by Nutech Engineers, pipe break.

Inc.

Q35049 84-5 Weld Overlay ' K' Unknown. Suspect Leakage would have A weld overlay was-Jet Pump Riser IGSCC induced-been detected and the performed as designed (02K-S4) axial indications. Unit shutdown prior to

. tar Nutech Engineers, pipe break.

Inc.

Q35050 84-5 Weld Overlay on Unknown. Suspect Leakage would.have A weld overlay was

'B' Recircula-IGSCC induced been detected-and the performed as designed.

tion Header

. axial indications.

Unit shutdown prior to by Nutech. Engineers, (02B-S7) pipe break.

Inc.

Q36085 IRM-14 Spikes Not apparent.

Half scrams were The chassis and pre-High Possibly dirty received when IRM-14

. amp connectors were connectors.-

spikes high.'The cleaned. Inputs were.

conservative direction ' swapped and cable 3

of this system was not insulation resistance compromised.

was checked. No problem

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was found.

Q36152 2B ltSIV-Failed Failure of one Unit was shutdown and Replaced pilot valves.

to ShutL of the pilot Primary Containment,

valves, capability.was not needed.

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I-UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.H.

LER OF ON ACTION TAKEN TO.

HUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q36679 Repair Welds on Slag in old welds.

None. This line has The slag'was removed Reactor Vessel been hydrostatic and welds were Bottom Drain tested repeatedly repaired.

(W-1,W-12,W-13) with no leakage.

Q36841 84-14 Mo 1-1001-29A; No brakes and no None. Unit was shut-Stem was replaced; Replace Stem functioning anti-down.

anti-hammer circuitry hammer circuitry, was re-wired correctly..

so valve hannered shut repeatedly.

Q36845 84-14 M0 1-1001-29B; No brakes and no -

None. Unit was shut-Stem was replaced;.

Replace Stem functioning anti-

down, anti-hammer circuitry hamme r c i rcui t ry, was re-wired correctly, so valve hammered shut repeatedly.

Q36989-84-17 Valves 1-5401A improper installa-The consequences of Re-installed valves

& B Operate tion.

this event were correctly.

Backwards Reference LER minimized by.the low 84-17 power condition of the core, less than 1% and the-short time period, 90 minutes, that the vacuum pump could not be isolated.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

.W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNC't10N SAFE OPERATION PREVENT REPETITION 4

Q36153 MO 2-1402-24A High ambient Due to the large

" Provided fans for Local Station temperature.

capacity of the charger and rooms.

OPEN Indication batteries, ample. time Light Does Not would be available to Work charge the batteries, if the batteries still are not charged, a half screm would occur, thereby maintaining the conservative direction of the system.

Q36997 2B2 24-48 Velt High ambient Due to the large Provided fans for DC Charger Will temperature.

capacity of the charger and room.

Not Stay On batteries, ample time Equalize would be available_to.

charge the batteries.

If the batteries still did not get charged, a half scram would occur, thereby maintaining the conservative direction of the system.

V.

DATA TABlitATIONS-The following data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit P 2r Level C.

Unit Shutdowns.and Power Reductions 1'

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OPERATING: DATA REPORT

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DOCKET NO -

50-254

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, UNIT-ONE DATE0ctober 3-

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COMPLETED BYDAVE KIMLER

-TELEPHONE 309-654-2241Xi92

. OPERATING STATUS.

0000~090184 Li. Reporting period:2400 093084 Gross hours in reporting' period:

720

2. Currently authorized power level (MWt): 2511'Hox. 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 720.0 2612.9 86168.5 6', Reactor reserve shutdown h'ours 0.0 0.0 3421.9 7.-Hours generator on line 720.0 2563.2 82911.1

8. Unit reserve shutdown hours.

0.0 0.0 909.2

9. Gross thermal energy generated (MWH) 1630543 5727126-170833832

10. Gross electrical eneroy generated (MWH) 536126 1896796-55155412

11. Net electrical energy generated (MWH) 513251 1794423 51400390

12. Reactor service factor-100.0 39.7.

79.3

13. Reactor ovo11ob111ty factor 100.0 39.7 82.5~

14. Unit service factor 100.0 39.0 76.3

15. Unit ovallobility factor

'i00.0 39.0 77.2

16. Unit capacity factor (Using MDC) 92.7-35.5 61.5

.17.

Unit capacity factor (Using Des.MWe) 90.3 34.6 60.0 1.8. Unit forced outage rate 0.0 1.7 6.1

19. Shutdowns. scheduled over next 6 months (Type, Dote,and Duration of'ecch):

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

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The MDC ney be lower then.769 ice during periods of high unbient tenperature doe

- to the thersel perfernance of the sprey canal.

WOFFICIAL CWPANY NUMBERS ARE USED IN THIS REPORT

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. DOCKET?NO.-

50-265-J 4

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-UNIT'

'TWO'

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'DATE0ctober 3~

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' COMPLETED BYDAVE KIMLER e -

TELEPHONE 309-654-224iXi92

~ -OPERATING' STATUS.

0000 090184 i.sReporting period:2400 093084 Gross-h'ours in repor. ting period':

720

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r2'.ECurrently authorized' power level;(MWt): 2511. Max. Depend capacity

-(MWe -Net) if 769* Design electrical rating (MWe-Net) : 759-

3. Power level to'which restricted (if any)'(MWe-Net): NA E4. Reasons for restriction (if.ony):

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Thir. Month Y'r.to Date Cumulative

'5.

Number. of hours reactor was critical 720.0 5013.8

'82931.3-6.

Reactor reserve 1 shutdown hours 0.0

-0.0 2985.8

-7.

Hours generator on line-720.0 4896.9 80106.6-8.

Unit reserve shutdown hours.

0.0 0.0 702.9

' 1531787 166913875 9.

Gross' thermal energy generated (MWH) 1681897 i

10. Gross electrical energy generated (MWH) 542770

'3716842 53152622' 11.. Net electrical energy generated (MWH) 520037 3543491 4987755i

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12. Reactor service factor iro.O

-76.3 77.0

-13. Reactor avo11ob111ty factor' 100.0 76.3

'79;8.

- 14. Unit' service factor 100.0

-74.5 7 4. 4 --

115.1 Unit ovo11ob111ty' factor 100.0 74.5

-75.0-16.. Unit capacity factor. (Using MDC) 93.9 70.1 60.2 17. a Unit capacity factor. (Using Des.MWe) 91.5 68.3 58.7-

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' 18. Unit forced outage. rote 0.0 3.2 8.3 f

19.; Shutdowns scheduled over next 6 months:(Type,Date',ond Duration.of each):. -

20~.fIf shutdown at end of report per i od,e st inat ed dat e o f' s t ar t up

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_8The IEC not be lever then 769 IRle dering periods of high onblent temperatore due tothethernal'perfornanceef;thespretcanal..

8WINFICIAL'C9tPAllY IRISERS ARE UBES Ill THIS REPORT

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. APPENDIX-B J AVERAGE DAILY ~ UNIT POWER LEVEL

-DOCKET NO.

50-254 UNIT ONE-DATE0ctober 3 COMPLET'ED BYDAVE'KIMLER TELEPHONE 309-654-2241Xi92 MONTH September 1984 DAY ~ AVERAGE DAILY POWER LEVEL DAY AVERAGE DA'ILY POWER LEVEL (MWe-Net)

' '(MWe-Ne t )

1.

-499.9 17, 777.9

.2.

478.5 i8.

732.9 3.

485.4 19..

-786.0 4.

500.5 i

20.

779.i 5.

559.0 21, 645.4 6.

658.1 22.

'I20.i 7.

688.3 23.

781.3 8.

726.8 24.

776.6 9.

777.1 25.

781.8 10.

790.1 26, 869.8 it.

784.0 27.

716.8 12, 859,6 28, 788.0 13.

651.3 29, 794.6-14.

714.0

-30, 739.8_.

115. _.

736,6.

16.

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. INSTRUCTIONS On this fornilist the average daily snit power level in l#le-NeI for each day in the reporting nenth.Cenpete to the

-nearest uhelt negewett.

These figures will be used to plot a grcph for each reporting nenth. Note that when noxinen dependable capacity is used for the net electrical rating of the snit,there nay be occasions when the daily average power level exceeds the 1991 line (or the restricted power level line).In such cases,the average daily unit pewer evtput sheet should be.

4 festnoted to explain the apparent ansnaly U

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' APPENDIX B

' AVERAGE DAILY UNIT POWER. LEVEL DOCKET'N0'.

50-265

. UNIT

TWO DATE0ctober 3 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241X192

MONTH September 1984 DAY' AVERAGE DAILY POWER LEVEL DAY AVERAGE-DAILY POWER LEVEL (MWe-Net)-

(MWe-Net) i '.-

774.2 17, 639.6-2.-

727~7 18..

757.4 3.

-686.8 19.,

773.i

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4.

713.0

20..

775.1 5.

767.8 21, 761.1 6.

709.0 22, 769.5 7.

737.6 23.

745.3 8.

770.0 24.

768.5 9.

'670.5 25.

766.3 10.

'772.2 26.

773.0 ii.

761.5 27, 782.8 i

l 12.,

764.0 28.

773.0 i.

l 13.

733.5 29.

780.3 l

14. -

509.0 30, 726.6' 15.

478.5 16.

524.1 INSTRUCTIONS l-On this fern, list the overage daily unit power level in IWe-Met for toch day in the reporting nenth Conpete to the nearest uhele negouett.~

These figures will be esed to plot a graph for each reporting nenth. Note that when notinen dependable copecity is -

t used for.the net electrical rating of the snit there ney be occasions when the daily overage power level exceees the

100% line (or the restricted power level line).,In such cases,the average daily unit power setput sheet sheeld be -

festnoted to explain the apparent onenely f 1.

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

050-254 August 1982 UNIT NAME Quad-Cities Unit One COMPLETED BY D. Kimler DATE October 4, 1984 REPORT MONTil SEPTEMBER 1984 TELEPil0NE 309-654-2241 g

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LICENSEE

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DURATION EVENT o

NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS /CONNENTS ca 84-18 840901 S

0.0 F

5 ZZ ZZZZZZ Reduced load to 500 Mwe per Load Dispatcher 84-19 840908 S

0.0 B

5 HA TURBlN Reduced load to perform weekly Turbine tests 84-20 840913 S

0.0 H

5 HH PUtiPXX Reduced load for Condensate Pump changeover 84-21 840914 F

0.0 H

5 MB RECOMB Reduced load due to Recombiner problems 84-22 840918 5

0.0 F

5 ZZ ZZZZZZ Reduced load per Load Dispatcher 84-23 840921 S

0.0 B

5 RB CONROD Reduced load for Nuclear Engineer Test and Special Rod Maneuver 84-24 840930 S

0.0 B

5 HA TURBIN Reduced load to perform weekly Turbine tests i

APPROVED AUG 1 G 1982 l

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M M

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

050-265 August 1982 UNIT NAME Quad-Cities Unit Two COMPLETED BY D. Kimler DATE October 4, 1984 HEPORT MONTil SEPTEMBER 1984 TELEPil0NE 309-6S4-2241 g

g N 20 g

m x

n h

I,ICENSEE m

DURATION M

EVENT o

u NO.

DATE (110URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS ca 84-35 840902 S

0.0 B

5 HA TURBIN Reduced load to perform weekly Turbine tests 84-36 840903 5

0.0 F

5 ZZ ZZZZZZ Reduced load per Load Dispatcher 84-37 840903 S

0.0 B

5 HA TURBIN Reduced load to perform Turbine nightly test and MSIV bi-weekly test 84-38 840906 S

0.0 F

5 ZZ ZZZZZZ Reduced load per Load Dispatcher and EGC Testing 84-39 840907 S

0.0 B

5 ZZ ZZZZZZ.

Reduced load for Economic Generation Control System test 84-40 840908 5

0.0 B

5 HA TURBIN Reduced load to perform weekly Turbine tests 84-41 840913 S

0.0 11 5

HF PUMPXX Reduced load to place 2B Circulating Water Pump out of service 84-42 840314 S

1.0 B

9 HA TURBIN Reduced load to 31 ace Reactor in HOT STANDBY, turn off Generator, and perform Turbine Overspeed APPROVED

~

Tests AUG 1 G 1982 (final) ygg3g

M M

M n

M M

p a

ID/SA APPENDIX D QTP 300-S13 UNIT SliUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET No. 050-265 August 1982 UNIT NAME Quad-Cities Unit Two COMPLETED BY D. Kimler DATE October 4, 1984 REPORT HONTil SEPTEMBER 1984 TEl.EPIIONE 309-654-2241 H

m w"

B gw

$m M

LICENSEE m@

DURATION EVENT g

u NO.

DATE (Il0URS)

REPORT No.

CORRECTIVE ACTIONS /CONNENTS ca 84-43 840919 F

0.0 H

5 SF VALVEX Reduced load due to problems with HPCI 2301-4 Valve 84-44 840923 S

0.0 B

5 HA TURBIN Reduced load to perform weekly Turbine tests 84-45 840930 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 -I'tems are included in this ' report based on prior commitments to the commission:

(

A.

Main Steam ReliefsValve 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. S. Type Plant' Description

. Unit Date Actuated Actuations Conditions of Events 2

9-14-84 2-203-3A 1 Manual Rx Press Surveillance 2-203-38 1 Manual 920 Technical 2-203-3C 1 Hanual Specification 2-203-3D 1 Manual 4.5.0.1.b 2-203-3E 1 Manual 4

2 1

J B.

Control Rod Drive Scr'am Timing Data For Units One and Two 4

The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifica-tions 4.3.C.1 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.

)

2 4

l

\\

h[

g.--

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM l-1 TO 12-31-84 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-0F RODS 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 (Average Scram insertion Time) 9-15 88 0.29 0.66 1.42 2.51 2.95 Unit 2 Hot Scram Timing (m-7)

A Sequence 4

.. +

VII.

REFUELING INFORMATION The following infonnation 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 Infonnation",

dated January-18,1978.-

t K

4 4

l i

I

\\

L i

e' QTP 300-S32 Revision 1 k

QUAD-CITIES REFUELING liarch 1978 INFORMATION REQUEST 1.

Unit:

QI Reload:

7 Cycle:

8 2.

Scheduled d' ate 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 IIcensing action and supporting Information:

SEPTEMBER 13, 1985, IF LICENSING ACTION REQUIRED.

6.

Important IIcensing 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.

4 d

7.-

The number of fuel assemblies.

a.

Number of assemblies in core:

724 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 l

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 WPPROVED s APR 2 01913 CD.c:.c).55.Ft.

['. +

QTP 300-S32

.=

,J

~

Rsvision 1 l -,

QUAD-CITIES REFilELING Mcrch 1978 I

Qy INFORMATION REQUEST F

[. ~

~1.

Unit:

2 Reload:

7 Cycle:

8 2.~ Scheduled-date for next. refueling shutdown:

4-2-85

~

i 3

Scheduled date for restart following refueling:

6-22-85 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 Itcens'ing action and supporting ji

'~

Information:

L*

January 18, 1985, if licensing action required.

P

_.]

6.

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

' different fuel design or supplier, unreviewed design or performance analysis t,

methods, significant changes in fuel design, new operating procedures:

. L _.

~

Hone planned at present time.

'r t r- -

M 7

The number of fuel assemblies.

a.

Number of assemblies in core:

724 U

b.

Number of assemblies in spent fuel pool:

0 8.

The present IIcensed spent fuel pool storage capacity and the size of any lg Increase in licensed storage capacity that has been requested or is planned

r-.

In number of fuel assemblies:

4, a.. Licensed storage capacity for spent fuel:

3897 li' b.

Planned increase in IIcensed storage:

0 L

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

]

spent

.41 pool assuming the present licensed capacity:

2003

(

APPROVED 4

Q APR 2.01978 Q.C.O.S.R.

3 y

4 t

y.....

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 ANSI Anerican National Standards Institute APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor CRD Control Rod Drive Electro-Hydraulic Control System EHC E0F Energency Operations Facility Generating Stations Emergency Plan GSEP High-Efficiency Particulate Filter HEPA HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling Systen Integrated Primary Containment Leak Rate Test IPCLRT IRM Intennediate Range Monitor Inservice Inspection ISI LER Licensee Event Report LLRT Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI Local Power Range Monitor LPRM MAPLHGR Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio MCPR Maximum Fraction Limiting Critical Power Ratio MFLCPR Maximum Pennissible Concentration MPC Main Stean Isolation Valve MSIV National Institute for Occupational Safety and Health NIOSH PCI Primary Containment Isolation Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Water Systen RBCCW Rod Block Monitor RBM Reactor Core Isolation Cooling Systen RCIC Residual Heat Removal Systen RHRS RPS Reactor Protection Systen Rod Worth Minimizer RWM Standby Gas Treatnent Systen SBGTS J

SBLC Standby Liquid Control Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SDV SRM Source Range Monitor Turbine Building Closed Cooling Water Systen TBCCW TIP Traversing Incore Probe Technical Support Center TSC

O Commonwealth Edison Quad Cities Nuclear Power St: tion 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 l

NJ K-84-298 October 1,1984 Director, Office of Inspection & Enforcenent United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Document Control Desk Gentlemen:

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

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION N. J. Kalivianakis Station Superintendent bb Enclosu re 4

S 4

.

ML20093L501

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