ML20211F621

Monthly Operating Repts for May 1986

ML20211F621
Person / Time
Site:	Quad Cities
Issue date:	05/31/1986
From:	Kronich C, Robey R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
RAR-86-14, NUDOCS 8606180413
Download: ML20211F621 (23)

Text

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m QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MAY, 1986 COMMONHEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 k"

$6D DO R

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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 Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary i

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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 Systems are General Electric Company Boiling Water Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source.

The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.

This report was compiled by Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 2240 and 2157.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One May 1-14 Unit One began the month of May dropping load to 420 MWe for a recircula-tion flow drop test.

At 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> load began a normal increase to full power. Full power was held until May 3, at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, when load was dropped to 795 MWe and the unit was placed on Economic Generation Control (EGC). The unit was taken off of EGC at 0356 hours0.00412 days <br />0.0989 hours <br />5.886243e-4 weeks <br />1.35458e-4 months <br />, and returned at 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br />. At 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br /> the unit was taken off of EGC for surveillances.

On May 4, at 0251 hours0.00291 days <br />0.0697 hours <br />4.150132e-4 weeks <br />9.55055e-5 months <br />, the unit was returned to EGC. On May 6, at 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, the unit was taken off of EGC, and load was increased to full power. Load was held steady until May 7, at 0228 hours0.00264 days <br />0.0633 hours <br />3.769841e-4 weeks <br />8.6754e-5 months <br />, when the unit was returned to EGC operation.

On May 8, at 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, the unit was taken off of EGC. Load was dropped to 700 MWe for Turbine surveillances. At 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br /> load remained at 690 MWe as per the Load Dispatcher. At 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> load began an increase to 750 MWe, and at 0531 hours0.00615 days <br />0.148 hours <br />8.779762e-4 weeks <br />2.020455e-4 months <br /> the unit was placed on EGC.

On May 9, at 0219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br />, the unit was taken off of EGC operation, and returned to EGC at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />. At 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br /> the unit was taken off of EGC, and load was increased to full power.. The unit returned to EGC operation on May 10, at 0039 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />. On May 11, at 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />, the unit was taken off of EGC for Turbine and MSIV surveillances. At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> load was dropped to 600 MWe due to a loss of condenser vacuum. At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> load began an increase to full power.

May 15-31 On May 15, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, a unit shutdown for a scheduled maintenance outage began. The unit came off line at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, and was manually scrammed at 0050 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. The unit remained shutdown until May 18, at 1048 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98764e-4 months <br />, when a normal unit startup commenced. The Reactor became critical at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, and was placed on line at 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br />. The unit reached full power on May 20, at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, after a normal increase in power.

Full power was held until May 22, at 0853 hours0.00987 days <br />0.237 hours <br />0.00141 weeks <br />3.245665e-4 months <br />, when it was placed on EGC.

On May 23, at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, the unit was taken off of EGC, and load was increased to full power. At 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br /> load was decreased to 700 MWe for repair of the condenser flow reversing valves. At 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> power was increased to 800 MWe, and the unit was placed on EGC operation at 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br />. On May 24, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the unit was taken off of EGC 4

and load was increased to full power. Load was held steady until May 28, at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br />, when the unit was placed on EGC.

m May' 15-31 (cont.)

On May 29, at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />, the unit was taken off of EGC, and load was increased to full power. At 1145' hours the unit was returned to EGC operation. EGC operation was tripped at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> on May 30.

Load was held at full power for the remainder of May.

B.

Unit Two-May 1-15 Unit Two began the month of May holding load at' full power. On May 1, at 0912 hours0.0106 days <br />0.253 hours <br />0.00151 weeks <br />3.47016e-4 months <br />, the unit was placed on EGC. On May 2, at 0320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br />, the unit was taken off of EGC, and load was dropped to 625 MWe to per-form control rod drive maintenance. Load was increased to EGC range and the unit was returned to EGC operation at 0607 hours0.00703 days <br />0.169 hours <br />0.001 weeks <br />2.309635e-4 months <br />. At.1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> the unit was tripped out of EGC at 750,MWe to perform control rod drive maintenance. The unit was returned to EGC operation on May 3, at 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />. The unit remained in EGC operation until May 6, 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, when EGC was tripped and load was increased to full power. The unit returned co EGC operation on May 7, at 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />.

The unit remained in EGC operation until May 9, at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br />. Load was then increased to full power. On May 10, at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, load was dropped to 775 MWe to change over the condensate pumps. The unit was then placed on EGC at.0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />. On May.12, at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br />, the unit was taken.off of.EGC, and load was dropped to 700 MWe for Condensate Demineralizer maintenance. On May 13, at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, load was increased to full power. At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> the unit was placed on EGC.

The unit was taken off of EGC on May 15, at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />. Load was then. increased to full power. The unit was returned to EGC operation at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />.

May 16-31 On May 16, at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, the unit was taken off of EGC, and load was increased to full power. On May 17, at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, load was reduced to 700 MWe for MSIV surveillances. At 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br />, load was brought to full power. Load was held at appror.imately full power until May 20, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, when the unit was placed on EGC. On May 25, at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />, the unit was taken off of EGC and a unit shutdown commenced at 25 MWe/hr

'due to Core Spray being inoperable. At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> the shutdown was terminated, and load began a normal increase towards full power. The j-unit was placed on EGC operation at 1719 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.540795e-4 months <br />.

{

May 16-31 (cont.)

On.May 27, at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />, the unit was taken off of EGC until 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br /> to perform surveillances. At 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br /> the unit-was taken off of EGC to perform surveillances. EGC operation was resumed at 0943 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.588115e-4 months <br />. On May 29, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the unit was taken off of EGC, and load was in-

-creased to 800 MWe to perform a special test.

Load was decreased to 750 MWe at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> for the special test.

The unit was returned to EGC operation at 2248 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.55364e-4 months <br />.

On May 30, at 0935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br />, the unit was taken off of EGC, and load was increased to maximum power. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> a unit shutdown commenced for a scheduled maintenance outage. The unit was taken off line at 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />, on May 31, and the unit was manually scrammed at 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br />. The unit remained shutdown for the remainder of May.

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

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

1 4

B.

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

l C.

Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

1 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, Licenane Event Report Numbers, Components, 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 NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q46910

, 86-02 AO l-203-2C Dirt & rust were The valve exceeded the The valve seat & main dise MSIV found on the' valve Technical Specification were machined smooth. The seat. Dirt was also leakage rate as dis-valve stem, pilot disc, found on the valve covered while Local Leak piston ring, & packing disc.

Rate Testing.

were replaced.

Q46911 86-02 AO l-203-2B Dirt & rust were The valve exceeded the The valve seat & main dise MSIV found on the valve Technical Specification were machined smooth. The seat. The valve leakage rate as dis-valve stem, piston ring, &

stem wrc bent, &

covered while Local Leak packing were replaced.

valve guide showed Rate Testing.

normal wear.

Q47052 86-01 1-220-62B Scale & dirt had' The valve failed the The valve's seating Feedvater built up on the allowable limit when surfaces were cleaned.

s Check Valse valve's seating Local Leak Rate Testing, surfaces.

Q47878 86-01 M9 l-1201-2 The stellite The valve failed the The old stellite was Clean-up coating on the valve allowable limit when Local removed & new stellite Valve disc was cracked.

Leak Rate Testing.

welded on the valve disc.

This allowed leakage Packing was replaced.

through the cracks.

The valve packing was also worn due to normal wear.

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UNIT 2

MAINTENANCE SUPMARY -

1

,j

.CAUSE RESULTS & EFFECTS-1-

W.R.-

LER OF-ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION lQ48069 2-1734D Main The. monitor soft-The monitor gave abnormally'.The software of all four

~

Steam Line ware was not low radiation reading for

' (A,,B. C, D) Main Steam' Radiation designed for reading the Reactor power level.

Line' Radiation Monitors l

' Monitor low level (normal)'

was replaced.

~

radiation.

~Q48607 595-141A Relay burned up due The relay burned up The relay was replaced.

j

- Hi-Radiation - to normal wear.

(failed) & caused a-1/2 Isolation Relay's age to a Group I.. Isolation signal.

Relay point where it ~

cannot handle the current.

Q49043 86-07 2-5748B Core Cause was due to.

The room cooler would not The pitted contactor was.

Spray Room pitting & burning run due.to the pitted replaced. The room'.

Cooler

' of contacts on the contacts not allowing.

cooler then operated motor control current to pass to the normally.

I center contactor room cooler motor.

i that supplies poder to the room cooler.

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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 occurrence reporting requirements as set forth in sections 6.6.8.1. and 6.6.8.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Data Title of Occurrence 86-22 5-1-86 CAM lines not meeting allowable code stress 86-23 5-5-86 Unit 1 RCIC inoperable due to overspeed trips

_ UNIT TWO Licensee Event Report Number Data Title of Occurrence 86-08 5-25-86 Failure of 2A Core Spray Room Cooler --

trip of Unit 2 Diesel Generator Breaker s

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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 i

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OPERATING ~ DATA REPORT.

DOCKET NO.

50-254 UNIT ONE DATEJUNE 5 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241

.0PERATING STATUS 0000 050186 i'.-Reporting period 2400 053186 Gross hours in reporting period:

744

2. Currently authorized power level (MWt): J2511 Max. Depend capacity (MWe-Net): 769* 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 reactor was' critical 683.8 1436.3 98097.7

.6.

Reactor reserve. shutdown hours 0.0 0.0 3421.9

'7.

Hours' generator on line 674.4 1390.0 94669.5 8.

Unit reserve shutdown hours.

0.0 0.0 909.2 9.' Gross thermal energy generated (MWH) 1629641 3210697

-198175854 10.. Gross electrical energy generated (MWH) 531859 1046263 64165634 li. Net'electricol energy generated (MWH) 509883 991515 60018048

12. Reactor service factor 91.9.

39.6 79.6 13.. Reactor avo11ob111ty factor 91'.9 39.6 82.4

14. Unit service factor 90.6 38.4 76.8

15. Unit ovullability factor 90.6 38.4 77.6

16. Unit capacity factor (Using MDC) 89.1 35.6 63.3

17. Unit copocity factor (Using Des.MWe) 86.9-34.7 61.7

. 18. Unit-forced outage rate 0 0

.3 5.8 2

' i9. Shutdowns scheduled ~ over next 6 months (Type,Date,and Duration of each):

- 20.=IfEshutdown at end of report period,estinated date of startup ___EL________

RelOFFICIAL Col H in IUIIERS ARE USED IN THIS REPORT l

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OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEJUNE 5 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241 OPERATING STATUS 0000 050186 1.

Reporting period:2400 053186 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 Cumulative 5.

Number of hours reactor was critical 724.7 3378,0 94645.7 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 724.1 3352.1 91649.7 8.

Unit reserve shutdown hours.

0.0 0.0 702.9

9. Gross thernal energy generated (MWH) 1725638 7952773 194061796

10. Gross electrical energy generated (MWH) 561188 2610360 6202714%

11. Net electrical energy generated (MWH) 538044 2499999 58374248

12. Reactor service factor 97.4 93.2 77.4

13. Reactor avoilobility factor 97.4 93.2 79.0 14 Unit service factor 97.3 92.5 74.9

15. Unit avo11obility factor 97.3 92.5 75.5

16. Unit capacity factor (Using MDC) 94.0.

09.7 62.1

17. Unit capacity factor (using Des.MWe) 91.7 87.5 60.5

18. Unit forced outage rate 0.0

.8 7.9 19.. Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of each) :

20. If shutdown at end of report period,estinated date o f s t ar t u p ___ 6-5dB_6__ ___

$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEJUNE 5 1786 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241 HONTH Mov 1986-

-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

672.6 17.

-10.9 2.

771.4 18.

2.7 3.

764.5 19, 548,9 4.

742.6 20, 771.8 5,

757.9 21, 791.5

.6.

779.9 22, 754.1 7'

758.5 23.

751.0 8.

745.6 24, 796.3

-9.

769.9 25.

787.7

~ 10.

746.8 26.

798.0

-11.

738.9 27.

786.1 12.

789.5 28, 767.0

[

13.

789.7 29.

771.1 14.

783.1 30, 787.9 l-15.

728.5 31.

798.3 f

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~9.4 INSTRUCTIONS On this forn, list the overage dolly unit power level in Mlle-ht for each day in the reporting nonth. Compete to the nearest whole negewett.

These figures will be used to plot a graph for each reporting nenth. Note that when notinen dependable capacitt is

- used for the net electrical rating of the unit,In such cases,the overage daily unit power setput sheet shee b

ill! line (or the restricted power level line).

festnoted to explain the apparent onenely

'=

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEJUNE 5 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309)654-2241 MONTH' Mov 1986 DAY AVERAGE DAILY POWER LEVEL

. DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(HWe-Net)

1. -

757.5 17.

764.2 2,

694.5 18, 786.4 3'

754.7 19.

781.8 4,

718.4 21.

749.6 5.

745.7 21.

749.0 6.

772.1 22.

725.5 7.

738.2 23, 745.5 8.

742.3 24.

753.4 9..

764.8 25, 692.6 10.

731.0 26.

738.7

. ti.

735.9 27.

734.7 12, 737.7 28, 740.8 13.

741.7 29.

753.6 14.

736.7 30.

737.3 15, 745.0 31.

33.8 16.

766.3 INSTRUCTIONS On this forn, list the average daily unit power level in ille-Met for each day in the reperting nenth Conpete to the nearest whole negouett.

These figeres will be used to plot a graph for each reporting nonth. Note that when notinen dependable capacity is osed for the net electrical rating of the unit there noy be occasiens when the daily overage power level exceeds the ill! line (or the restricted power level line),.In sich cases,the average daily enit power output sheet should be festnoted to explain the apparent onently L:

.. "T M

P"1 P""1 F=1 m

M M

M M

M m

P""1 P"1 P

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

050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C Kronich DATE June 10, 1986 REPORT HONTil MAY 1986 TELEPil'sNE 309-654-2241 5

g m Ru u

$2 O

0"#

m 2

r o

~h@

uTCENSEE mo a, o go EVENT DURATION gig w

u NO.

DATE (ll0URS)

"a REPORT NO.

CORRECfIVE ACTIONS / COMMENTS o

86-10 860501 S

0.0 B

5 CB ZZZZZZ Reduced load to 420 MWe for recirculation flow drop test 86-11 860508 S

0.0 B

5 HA TURBIN Reduced load to 700 MWe for Turbine surveillances 86-12 860511 F

0.0 A

5 HC HTEXCH Load was dropped to 600 MWe due to loss of condenser vacuum 86-13 860515 S

60.1 B

2 ZZ ZZZZZZ Unit shutdown for a scheduled Maintenance Outage -- EHC oil leak and IRM maintenance 86-14 860523 S

0.0 B

5 HC VALVEX Reduced load to 700 MWe for maintenance on condenser flow reversing valves APPROVED AUG 1 G 1982 I

' (final) f VGodH l

M M

M P"ll M

M M

M M

M M

M P"1 M

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

050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY C Kronich DATE June 10, 1986 REPORT MONTil MAY 1986 TELEPil0NE 309-654-2241 5

e w

EU r

$w m

x d@w R@

w o

os<

h$

Q M

LICENSEE m

EVENT

$u gu DURATION d

g g

NO.

DATE

'w u

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS (IIOURS) oo 86-15 860502 S

0.0 B

5 RC CRDRVE Reduced load to 625 MWe to perform CRD maintenance 86-16 860512 S

0.0 B

5 HG DEMINX Reduced load to 700 MWe for Condensate Demineralizer maintenance 86-17 860517 S

0.0 B

5 CD VALVEX Reduced load to 700 MWe for MSIV surveillances 86-18 860525 S

0.0 A

5 86-08 SF -

HTEXCH Commenced unit shutdown due to 2A Core l

Spray Room Cooler inoperable (terminated approx. 6 hrs) l 86-19 860530 S

19.4 B

2 ZZ ZZZZZZ Unit shutdevn for a scheduled Maintenance Outage -- stes.n leaks and condenser leaks l

l 1

I l

APPROVED AUG 1 G 1982 (final) yCUdH

4, s.

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 TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

4 i

1 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.

t-i

.s h

i i

1 1

0027H/0061Z

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

~

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

Uniti Q1 Reload:

8 Cycle:

9 l

2.

Scheduled date for next refueling shutdown:

9-14-87 l

3.

Scheduled date for restart following refueling:

12-21-87 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 Itcensing action and supporting Information:

AUGUST 21, 1987 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.

l 7

The number of fuel assemblies.

a.

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

i a.

Licensed storage capacity for spent fuel:

3657 0

(

b.

Planned increase in IIcensed storage:

i 9

The projceted date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 XPPROVED

< APR 2 01978 Q.C.O.S.R.

I se a

me on m-g m.

- - - + - - -

er

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:

NOT AS YET DETERMINED.

5.

Scheduled date(s) for submitting proposed IIcensing action and supporting 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 core:

724 b.

Number of assemblies in spent fuel pool:

836 l

l 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:

l a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 XPPROVED APR 2 01978 C). C:. C). !B. ft.

l p

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

ACAD/ CAM -

Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATHS Anticipated Transient Without Scram BHR Bolling Water 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 High Radiation Sampling System HRSS 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 Generatior. 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 Managcaent 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 RWM Rod North Minimizer SBGTS Standby Gas Treatment System l

SBLC Standby Liquid Control i

SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCH iurbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center 0027H/0061Z

n O 22710 206 Avenue North Commonwealth Edit,on ouad Cities Nuclear Power Glation Cordova, Illinois 61242 Telephone 309/654-2241 RAR-86-14 June 2, 1986 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of May, 1986.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES HUCLEAR POWER STATION

$h-R.A.Robey[

J' L

Services Superintendent bb Enclosure 0027H/0061Z e i

.