Text

Monthly Operating Repts for Sept 1985
	ML20133H479
Person / Time
Site:	Quad Cities
Issue date:	09/30/1985
From:	Kronich C, Tamlyn T; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	TKT-85-51, NUDOCS 8510170388
	Download: ML20133H479 (28)
	v • d • e

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.4

' QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2

. MONTHLY PERFORMANCE REPORT SEPTEMBER 1985 COMMONWEALTH EDISON COMPANY AND

~IONA-ILLIN0IS GAS & ELECTRIC COMPANY g

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

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8510170388 850930 PDR ADOCK 05000254 R

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D 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.

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 ano Iowa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary T

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, 1

respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor critica11 ties 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 127 and 193.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One September 1-8 Unit One began the month of September on Economic Generation Control (EGC). On September 1, at 0122 hours0.00141 days 0.0339 hours 2.017196e-4 weeks 4.6421e-5 months , EGC was tripped and load was decreased at 100 MWe/ hour to 700 MWe for MSIV and Turbine surveillances.

Seven hundred MWe was reached at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months and held until 0715 hours0.00828 days 0.199 hours 0.00118 weeks 2.720575e-4 months when load was increased at 100 MWe/ hours to 775 MWe, and then increased 5 MWe/ hour. At 1040 hours0.012 days 0.289 hours 0.00172 weeks 3.9572e-4 months 788 MWe was reached and the unit was placed on EGC. On September 3, at 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months , ECC was tripped, load was increased to 815 MWe at 5 MWe/ hour, and held steady. On September 4, at 1845 hours0.0214 days 0.513 hours 0.00305 weeks 7.020225e-4 months , load was decreased to 785 MWe and the unit was placed on EGC.

On September 5, at 0610 hours0.00706 days 0.169 hours 0.00101 weeks 2.32105e-4 months , EGC was tripped and load was increased at 5 MWe/ hour. At 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months , 817 MWe was reached and held steady, until September 5, at 2352 hours0.0272 days 0.653 hours 0.00389 weeks 8.94936e-4 months , when the unit was placed on EGC. On September 7, at 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months , EGC was tripped, as per the Load Dispatcher and load was increased at 5 MWe/ hour until 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months , when 800 MWe was reached and held steady. On September 8, at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months , the unit was placed on EGC.

EGC was tripped at 0705 hours0.00816 days 0.196 hours 0.00117 weeks 2.682525e-4 months , and load was increased at 5 MWe/ hour. At 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months load was holding at 804 MWe until 1640 hours0.019 days 0.456 hours 0.00271 weeks 6.2402e-4 months , when load was dropped to 790 MWe in preparation for EGC. At 1650 hours0.0191 days 0.458 hours 0.00273 weeks 6.27825e-4 months , 790 MWe was reached and at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months the unit was placed on EGC.

September 9-11 EGC was tripped on September 9, at 1218 hours0.0141 days 0.338 hours 0.00201 weeks 4.63449e-4 months . Load _was increased to 790 MWe and then 5 MWe/ hour. At 1420 hours0.0164 days 0.394 hours 0.00235 weeks 5.4031e-4 months , 805 MWe was reached and held until 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months , when load was dropped to 790 MWe in preparation for EGC. At 1840 hours0.0213 days 0.511 hours 0.00304 weeks 7.0012e-4 months , 788 MWe was reached, and the unit was placed on EGC at 1855 hours0.0215 days 0.515 hours 0.00307 weeks 7.058275e-4 months . EGC was tripped on September 10, at 0815 hours0.00943 days 0.226 hours 0.00135 weeks 3.101075e-4 months .

At 0820 hours0.00949 days 0.228 hours 0.00136 weeks 3.1201e-4 months load began an increase at 5 MWe/ hour until 808 MWe was reached at 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months .

On September 11, at 0145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months , load was decreased at 140 MWe/ hour to 600 MWe as per Load Dispatcher.

Six hundred MWe was reached at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months . At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months load began an increase to 720 MWe at 100 MWe/ hour.

At 0745 hours0.00862 days 0.207 hours 0.00123 weeks 2.834725e-4 months , load was increased 20 MWe to 748 MWe, and then began an increase at a rate of 5 MWe/ hour. At 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months , load was increased 15 MWe to 775 MWe, and then continued to increase at 5 MWe/ hour to maximum power. Two thousand five hundred and eleven MWt was reached at 1930

. hours.

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' A.

Unit One (continued)

September 12-15 On September 12, at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , load was dropped to 790 MWe for EGC.

_ At 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months , 790 MWe was reached and the unit was placed on ECC.

At 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months , EGC was tripped at 750 MWe. Load began a drop to 600 MWe at 150 MWe/ hour as per the Load Dispatcher. At 0420-hours, 600 MWe was reached, and at 0455 hours0.00527 days 0.126 hours 7.523148e-4 weeks 1.731275e-4 months load began an increase at 100 MWe/

hour to 750 MWe. At 0625 hours0.00723 days 0.174 hours 0.00103 weeks 2.378125e-4 months , 750 MWe was reached, and load began an increase at 5 MWe/ hour. Eight hundred and twelve MWe was reached at 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months . At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , load began a decrease to 200 MWe for required scram timing at 150 MWe/ hour from 810 MWe.

At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months , load was holding at 200 MWe, On September 13, at 1420 hours0.0164 days 0.394 hours 0.00235 weeks 5.4031e-4 months , the control rod pattern change began. At 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months , load reached 500 MWe and was held until 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months when load began an increase to 550 MWe.

Five hundred and fifty MWe was reached at 2040 hours0.0236 days 0.567 hours 0.00337 weeks 7.7622e-4 months , and at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months load was increasing at a rate of 5 MWe/ hour. On September 14, at 0940 hours0.0109 days 0.261 hours 0.00155 weeks 3.5767e-4 months ,-load was increased to 600 MWe, and then continued at 5 MWe/ hour on September 15, at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months , 795 MWe was reached and held steady.

September 16-21 On September 16, at 1135 hours0.0131 days 0.315 hours 0.00188 weeks 4.318675e-4 months , load was increasing at a rate of 5 MWe/

hour until 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months , when 819 MWe was reached and continued to hold steady. On September 17, at 1235 hours0.0143 days 0.343 hours 0.00204 weeks 4.699175e-4 months , load was dropped to 795 MWe in preparation for EGC.

The unit was placed on ECC at 1254 hours0.0145 days 0.348 hours 0.00207 weeks 4.77147e-4 months .

EGC was tripped on September 18, at 1040 hours0.012 days 0.289 hours 0.00172 weeks 3.9572e-4 months , at 823 MWe. Load was held steady until 1310 hours0.0152 days 0.364 hours 0.00217 weeks 4.98455e-4 months , when a load Prop to 700 MWe began for a Feedwater Pump swap. Seven hundred MWe was reached at 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months , and load began an increase at 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months to 810 MWe. At 1425 hours0.0165 days 0.396 hours 0.00236 weeks 5.422125e-4 months , 810 MWe was reached, and load continued to increase at~5 MWe/ hour to maximum power. A 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months , 823 MWe was reached ani held. steady until September 19, at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months , when load began a decrease to 700 MWe for a Feedwater Pump swap. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months , load was increased to 750 MWe, and at 0235 hours0.00272 days 0.0653 hours 3.885582e-4 weeks 8.94175e-5 months the unit was placed on EGC. At 1340' hours, ECC was tripped and load was increased to 800 MWe, and then continued at 5 MWe/

hour. At 1705 hours0.0197 days 0.474 hours 0.00282 weeks 6.487525e-4 months load was dropped to 795 MWe in preparation for EGC and the unit was placed on ECC'at 1717 hours0.0199 days 0.477 hours 0.00284 weeks 6.533185e-4 months .

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.4 A.

Unit One (continued)

September 22-30 On September 22, at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months ,-EGC was tripped and load began a decrease to 750 MWe for surveillances,'at 150 MWe/ hour. Seven hundred and fifty MWe was reached at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months , and at 0240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months the unit returned to EGC. On September 23, at 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months , EGC was tripped and load was increased to 800 MWe as per Load Dispatcher. At 1210 hours0.014 days 0.336 hours 0.002 weeks 4.60405e-4 months , the unit ~was returned to EGC, until September 26,.at 1005 hours0.0116 days 0.279 hours 0.00166 weeks 3.824025e-4 months , when EGC was tripped, and load was increased to 800 MWe as per Load Dispatcher. At 1020 hours0.0118 days 0.283 hours 0.00169 weeks 3.8811e-4 months , load reached 800 MWe and held steady until 1158 hours0.0134 days 0.322 hours 0.00191 weeks 4.40619e-4 months , when the unit was placed on EGC.

On September 28, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , EGC was tripped and load began a drop to 700 MWe at 100 MWe/ hour for a control rod pattern adjustment. At 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months , load was increased to 750 MWe.

At 0156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months , load reached 750 MWe, and continued to increase at 5 MWe/ hour until 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months when 825 MWe was reached.

On September 29, at 1040 hours0.012 days 0.289 hours 0.00172 weeks 3.9572e-4 months , load was dropped to 800 MWe, and at 1105 hours0.0128 days 0.307 hours 0.00183 weeks 4.204525e-4 months the unit was placed on EGC. On September 30 at 0920 hours0.0106 days 0.256 hours 0.00152 weeks 3.5006e-4 months EGC was tripped and load was increased to full power as per the Load Dispatcher. At 1310 hours0.0152 days 0.364 hours 0.00217 weeks 4.98455e-4 months load was dropped to 800 MWe in preparation for EGC. The unit was placed on EGC at 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months and remained through the'end of September.

B.

Unit Two September 1-4 Unit Two began the month of September on Economic Generation Control (EGC). On September 1, at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , EGC was tripped and load began a drop to 400 MWe for surveillances, at-200 MWe/ hour. At 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months the load drop was terminated at 575 MWe as per the Operating Engineer and Shift Engineer due to a Feedwater Regulation Valve problem. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months , load began a normal increase to full power. Eight hundred and nineteen MWe was reached at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months . At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months load was decreased to 800 MWe in preparation of EGC. The unit was placed on EGC at 2150 hours0.0249 days 0.597 hours 0.00355 weeks 8.18075e-4 months .

On September 2, at 0136 hours0.00157 days 0.0378 hours 2.248677e-4 weeks 5.1748e-5 months , EGC was tripped and load was holding at 780 MWe until 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months when the unit returned to EGC. EGC was tripped on September 3, at 0510 hours0.0059 days 0.142 hours 8.43254e-4 weeks 1.94055e-4 months , as per Load Dispatcher. At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months , load began increasing 5 MWe/ hour, until 0805 hours0.00932 days 0.224 hours 0.00133 weeks 3.063025e-4 months when load reached 804 MWe.: Load was held steady until September 4, at 1845 hours0.0214 days 0.513 hours 0.00305 weeks 7.020225e-4 months when load was decreased to 800 MWe and the unit was placed on EGC.

4 B.

Unit Two (continued)

September 5-15 On September 5, at 1602 hours0.0185 days 0.445 hours 0.00265 weeks 6.09561e-4 months , EGC was tripped and load was increased to 808 MWe.

The unit returned to EGC on September 6 at 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months .

EGC was tripped at 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months and load was held at approximately 810 MWe until September 7, at 0110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months , when the unit was placed on EGC.

At 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months , EGC was tripped as per Load Dispatcher, and load was increased 5 MWe/ hour until 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months , when maximum power 2511 MWt was obtained. At 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months load began a drop at 50 MWe/ hour to 600 MWe for MSIV testing. At 0110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months , on September 8, the load drop was increased to 150 MWe/ hour.

Six hundred MWe was reached at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months .

Due to the failure of the MSIV's, a normal shutdown began at 0820.

At 1140 hours0.0132 days 0.317 hours 0.00188 weeks 4.3377e-4 months , load was held steady at 280 MWe to repair the MSIV's.

At 1315 hours0.0152 days 0.365 hours 0.00217 weeks 5.003575e-4 months a normal increase to full power began.

Eight hundred and thirteen MWe was reached on September 9, at 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months . On September 12, at 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months , the unit was placed on EGC, until September 15 at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , when EGC was tripped. Load began a drop at 150 MWe/ hour to 550 MWe as per Load Dispatcher.

Five hundred and fifty MWe was reached at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months , and at 0150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months , load was decreased further at 100 MWe/ hour to 500 MWe.

The unit was holding at 500 MWe at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months . At 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months , load began increasing at 100 MWe/ hour to 750 MWe until 0745 hours0.00862 days 0.207 hours 0.00123 weeks 2.834725e-4 months when the unit began holding at 690 MWe as per Load Dispatcher. At 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months load was dropped to 600 MWe as per Load Dispatcher, and began to hold steady at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months .

At 1830 hours0.0212 days 0.508 hours 0.00303 weeks 6.96315e-4 months , the unit began a normal increase to full power.

September 16-22 Eight hundred and twenty-five MWe was reached on September 16, at 1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months . At 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months , load was decreased to 800 MWe in preparation for ECC.

The unit was placed on EGC at 2153 hours0.0249 days 0.598 hours 0.00356 weeks 8.192165e-4 months . At 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months , the unit was taken off EGC, and began a load drop at 100 MWe/ hour to 600 MWe as per the Load Dispatcher.

On September 17, at 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months , 600 MWe was reached. At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months load was increased at 100 MWe/ hour to 750 MWe. At 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months , the unit was placed on EGC until September 18, at 1035 hours0.012 days 0.288 hours 0.00171 weeks 3.938175e-4 months , when EGC was tripped and load was increased to full power.

On September 19, at 0144 hours0.00167 days 0.04 hours 2.380952e-4 weeks 5.4792e-5 months , the unit returned to EGC. At 1340 hours0.0155 days 0.372 hours 0.00222 weeks 5.0987e-4 months , EGC was tripped and the unit was brought up to full power.

At 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months , load was dropped to 800 MWe in preparation for EGC, and the unit was placed on EGC at 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months .

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B.

' Unit Two ' (continued) l September 16-22 (continued) l I

i The. unit was taken off EGC at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months , at 735 MWe for a Condensate l

pump test. The unit was returned to EGC at 0845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months . At 1655 hours0.0192 days 0.46 hours 0.00274 weeks 6.297275e-4 months .

l EGC was tripped for a condenser flow reversal, and returned to EGC at j.

1735' hours.

September 23-30 i

On September 23, at 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months , EGC was tripped at.800 MWe. Load was held steady until 1212' hours when the unit returned to EGC, until September 26, at 1005 hours0.0116 days 0.279 hours 0.00166 weeks 3.824025e-4 months , when EGC was tripped and load was increased to full power.- The unit returned to EGC at 1157 hours0.0134 days 0.321 hours 0.00191 weeks 4.402385e-4 months .-

On September 30, at 0810 hours0.00938 days 0.225 hours 0.00134 weeks 3.08205e-4 months , the unit was taken off EGC, and load was increased to maximum power. Eight hundred and twenty-eight MWe was reached at 0835 hours0.00966 days 0.232 hours 0.00138 weeks 3.177175e-4 months , and was held steady for the remainder of September.

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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.

B.

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

C.

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

D.

Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

s

UNIT 1

MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUEER NLNBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q41378 85-002-1-1701A Fuel Loose capacitor Monitor spiked high, Loose capacitor and open 85-014 Pool Radiation and an open immediately reset, LED were replaced.

Monitor light emitting Standby Gas Treat-diode in sensor ment auto-started; unit.

Reactor ventilation-isolated.

Q42745 1-1601-63 Air valve Valve would not open.

Air valve operator Torus Valve operator out of Emergency (normal) adjusted to open within' adjustment position is closed.

ten seconds.

Q43889 l-2301-48 No problem found

-Valve would not open Full maintenance investi-HPCI Cooling in valve operator. or close from Control gation revealed no Water Valve Room. Manually left problem. Valve tested open so HPCI was satisfactorily. AIR 4-available, if needed.

84-30 written to investigate.

J 002iH/0061Z

UNIT 2

MAINTFfANCE SUWARY CAUSE RESULTS & EFFECTS W R.

LER OF ON ACTION TAKEN TO NUMBER NUEER COMPONENT MALFUNCTION SAFE OPERATION' PREVENT REPETITION Q42992 250 Volt Water falling on Battery charger-Circuit breaker and Battery Charger battery charger

tripped, cransformer replaced like-from above room for like. Holes in ceiling (mopping in sealea.

progress).

Q43285 85-15 2-1735A Failed Geiger-Monitor drifted and Tube replaced like-for-like Reactor Bldg.

Mueller tube in tripped upscale.

and monitor tested Radiation sensor and Initiated Standby satisfactorily.

Monitor convertor unit.

Gas Treatment and Reactor Bldg. Vent System tripped.

Q43286 85-15 2-5742A Unknown.

Damper failed tn close.

None. Tested satisfactorily.

Reactor Bldg.

Vent Isolation Valve Q43288 85-15 2A-5741 Failed Versa Valve Damper failed to close.

Solenoid replaced like-for-Reactor Bldg.

operated solenoid.

!ike, and tested satisfactorily.

Q43518 590-lC7C IRM Relay coil over-Relay failed, causing Relays are being upgraded 13 / APRM 3 heated causing the Channel 'A' half-scram, to model with longer lifetime.

Relay relay to burn up.

Q43683 2-1601-20A Dirty water found Vacuum breaker valve Accumulator tank was drained.

Valve Indicator in accumulator, did not open. In-line Vacuum breaker valve was Dirt caused the valve closed to assure successfully testad.

breaker valve to Primary Containment.

" lock-up".

002fH/0061Z j

UNIT 2

MAINTENANCE SLAAAARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NLASER NLABER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q38978 2-503C Condenser Instrument set-Tripping point Because of bad history, Low Vacuum Scram point drift.

below normal set-

.this pressure switch was Pressure Switch point.

replaced like-for-like.

Q42098 2-6601 Diesel Wiring circuitry No affects. Diesel Wiring was changed to Generator in starting still would have correct design.

logic.

started manually or automatically.

Q42166 85-007 2-8804 0xygen Small scratches Failed Local Leak Lapped valve seat.

Analyzer Valve on the velve Rate Test.

Retested satisfactorily, seat.

i Q42167 85-007 A0 2-8801C Very dirty Failed Local Leak Cleaned valve internals Oxygen (rusty) valve Rate Test.

and lapped valve seat to Analyzer Valve internals.

reduce leakage.

Q42536 85-007 2-1601-20B Worn packing on Failed Local Leak Replaced packing.

Vacuum Breaker shaft.

Rate Test.

Valve Q42664 2-300-J5 CRD Broken valve While scram timing, Like-for-like replacement 34-19 HCU stem. Blocked control rod J-5 of valve stem.

2-305-112 Valve flow of above exceeded maximum piston water to inserting time.

Scram Discharge Volume.

3 Q42672 2-3999-515C Valve disc was Excessive leak when Cleaned valve seats, honed RHR Service stuck in the tested.

side wall.

Water Vault OPEN position.

Sump Check Valve 002iH/0061Z

UNIT

.2 MAINTENANCE SLANARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUREER NulEER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q43715 2-302-109D Incorrect Transmitter gave Transmitter 0-ring Scram Discharge assembly by inconsistent low replaced, tested, and Barton Level manufacturer.

readings.

re-installed.

Transmitter Q44164 IV-LS-82G Level switch Gave a " Channel A/B Circuit board replaced.

Scram circuit board's Discharge Volume Hi-Tested satisfactorily.

Discharge transformer Level" alarm. Channel Volume North failed.

'A' half-scram.

Dump Tank 002iH/0061Z

3 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.B.1 and 6.6.B.2 of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 85-15*

8-30-85 RCIC Turbine Trip 85-16 9-05-85 1B Refuel Floor Monitor Spike

This LER was incorrectly identified as 85-13 in the August Monthly Performance Report.

UNIT TWO Licensee Event Report Number Date Title of Occurrence 85-19 9-08-85 MSIV Closure Times; Orderly Shutdown 85-20 9-17-85

' Condensate Pit Circulating Water Pump Trip l

1

i V.

DATA TABULATIONS

-The following data tabulations are presented in this report:

'A.

Operating Data Report i

B. -Average Daily Unit Power Level C.. Unit Shutdowns and Power Reductions 9

f OPERAT1NG DATA R F.P U H I l

DOCKE1 bU..._

30 "i4 Uru T tWF p

11 A T E.Or l Oi!F R 2 19H5 C O MP L t:T ED 1 0 C /.R O L t..

DONtCH T L LE P HONE 3 0 9 / /5 4 - 2 241 X i ? 3 OPERATING STATUS 0000 090185 Reporting p e r i. o d : 3 4 0 0 093085 Gross he;urs tn e.nortina per><ci:

?? U 2

Currently au thor t zed power level (MWt)* 2S11 Mm,Dcoend c o o n c.. t v

( MWe-tJe t )

76?* Design elettricoJ rnting (MWe-Net) 789 3.

Power level to which restricted (tf any)(MWe-Net)' NA 4.

Reasons for restriction (if anv) lhis Month Yr to Date Cunulative 5.

Numbar o f b c u r s>

reuctor was critical

'/PO.0 630?,0 946P4.4 f>. Reactor r e i a r '> u ubutdown

.ourc n.0 0,n 3421,9 7

Hourt a-nerat or on Itac 700.0 6?A4,4 01 :"/ 9, 7 9,

I h,.i ?

r-ervt :hutdGWG hout 5.

O.0 0,0 909.?

O.

Cr O m' i h e r,9 rt l e n e r g y Ge ne r q 1, e d ( H W H )

16;tp630

',4671,4',49 190417R49

1. 0. G r o '. s electricci nerny.; *; n e r a t e d ( M WM )

t ~.t~; 1 1 3 0 A n 2'/ 9 4.6

(' 16 P (K5 /> 7 ii Net olectricat :nerav g o.n c r a t e d ( MWII)

W*d41 46 ?N6il 17_Ff-9M 12, Reactor serv tce f ac t or 100.0 96.<

nh.6 13, Reactor ava t] nb ilit y factor 10 0, ti Y ti.. '

R3,r 14, Unit service roctar ion,o 95 3

/7.f-i t~.

Uni 1 n V a i l O b a 3 i t V.

fGCtor

- - - i h.O 5

7fi l

s A I,.

8 a

,.8 e

1 */, Un't capacity factor (Usina Deu.MWe>

9?.9 Do.t

/W ?

t i n,

'J n i t forced outage rate 4.0 4 6 6.3 19, 9hutdoWGG SchedulCd OVer n n 'X t 6 Months (1 ype, Du t e,und D u r u t 1(= n of

c. q c h ) '

20, IC .> h ') 1 (I O W D GT 2nd Of P 0 [) O r t narlod,o 1Lpqted (j u t t Of ' t ar t op _ _ NA _ _ _ _ _ _

3 lite POC My be ber tMn 769 P2e drir,; ;8tiads of higi ener-t tener*.ture he

'4 t',e thumi pe-f ern:rce of the s;r:y t=al, MFFEUl. CCFPMY NU"!E73 tJE USED IN THIS EPOU

f OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEOCT_0BER 2 1985 COMPLETED BYCAROL L, KRONICH TELEPHONE 309/654-Ij241X193 OPERATING STATUS 0000 090185 1.

Reporting period:2400 093035 Gross hours in reporting period:

120 2.

Currently authorized power level (MWt)- 2511 Max, Depend capacity (MWe-Net): 76'7* De si gn elec tr ical rating (MWe-Net): 789 3.

Power level to which restricted (if any)(MWe-Net)* NA 4,

Reasons for r e s t r.t c t i o n (if any):

This Month Yr,to Date Cumulative ti, Nursber of hours reactor was critical 720,0 4439,0 09345,0 6.

Reactor reserve shutdown hours 0,n 0,0 2985,0 7,

Hours generator on line 720,0 4367,9 86417.1 G.

Unit reserve shutdown hours.

0,0 0,0 702,9 9.

Gross thermal energy generated (MWH) 1685565 10130068 181649935 10, Gross electrical energy generated (MWH) 550405 3293084 57947295 11, Net electrical energy generated (MWH) 527434 3149633 54467618

1. 2, Reactor service factor 100.0 67,8 76,7 13, Reattor ovallab ill t y factor 100,0 67_,8 79,3 14, Unit service factor 100.0 66,7 74,2 iS,

'J n i t availability factor 100.0 66.7 74,0

16. Unit capacity factor (Usina HDC) 95.3 62,5 60,8 17, Unit capacity factor (Using Des MWe) 9?,0 60,9 59,3

10. Unit forced outage rate 0,0 4 u2 0.jl 19, Shutdouns scheduled over next 6 months (Type,Date,and Duration o f' each ) *

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

The PDC ny h lw the 767 %'t daring periods of high cabient te=;erature due te the th u N l perfer w ce of the sprey cen11, itN0FFICIAl. CCPPANY C.EERS M E USED IN THIS lie?CRT

APPtiNDIX B AVERAGE DAILY UNIl POWER LEVEL DOCKET NO.

50-254 UNIT

_0g DATEOCTOIER 2 1985 COMPLETED BYCAROL L, KRONICH TELEPHUNE309/654-PP4iXi93 MONTH Septenher 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1, 730,3 17, 767.0 l

2, 740.1-18, 700,8 j

3.

770.5 17, 729,0 1

4, 764,5 20, 742,6 5.

773.7 21.

743,2 4

e j

6.

-761,2 22, 750.3 l

7, 750,8 23, 747.0 i

.8.

753,1 24.

746,3 i

9, 732,5 25, 755,1 10, 748.3 26.

756.6

}

ii.

742.O 27, 7 2 7,47 12, 712,3" 28, 760,5 1

]

' 13,

311,0 29, 769,4 14.

614,0 30, 748.4 15, 737,2 7

16. -

700.7 i

INSTRUCTIONS i

On this forn, list the overage daily snit power level in NWe-Net for each day in the reparting nonth,Carpate to the nearest whole mecawatt.

These figures will be used to plot a grcph for each reporting nonth. Note that when muinsn dependeble capacity is.

used for the net electrical rating f the snit there may be occasions when the daily overage power level exceeds the 180% line (or the restricted power level line),In such cases,the overage daily snit pcwer estpst sheet should be a ~

fgatnoted te explain the appcrent unenaly

~. - -._._-,

APPENDIX B AVERAGE DAILY UNIT POWER L.EVEL DOCKET NO, 50-265 UNIT TWO

)

l DATEOCT0EgR 2 1985 0

I l

COMPLETED BYCAROL L, KRONICH I.

TELEPHONE 309/654-2241Xi93 l

{

MONTH Sgptember 1985 i

i LAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net) 4 i.

683,0 17, 703.0 2.

748,G 18, 720,6 I

3, 754,7 19.

790.7 i

4, 75n 5 20.

737.5 2

i j

5, 761,3 21, 738.8 i

i i

6.

75?,6 22, 740,i 1

l 7,

766.5 23, 752,i B.

514,0 24, 737.8 9,

697.1 25, 751.6 l

10, 756.2 26.

753.0 t

j 11, 788,3 27, 730.3-

}

12.

'745,6 28, 751.8 l

13, 748,6 29, 736.3 j

14, _

721.,7 30, 774,5 l

b 1

15, 614.6 16, 737,4 INSTRUCTIONS On this form, list the avercge daily unit plwer level in Ne-Net for ecch by in the reportir.g sonth.Concett to the j

recTeSt While Pec0dutt.

These figtres will be vsed to plot a gec:h for each reparting nonth N:te thct when notimum deoen hble cepetity is used for the net electric 11 rating of the cnit there mce te occasicr.s when ttt duly cieract power level exceds the-1001 line (or the restricted power level lir.e).,In such cases,the averace hily snit p;wer output theet should te footnoted ts explain the cc;crent caemalv I

b _.,.-,_,, _..-,.__ _.-.-- - _ _ _.._ _ _ _

M P"M P'"T M

M M

M P""1 M

M f

ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revisiou 6 DOCKET NO. _050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPI.ETED BY C. Kronich DATE October 7, 1985 REPORT MONTil SE'PTEMBER 1985

~ TEI.EPil0NE 309-654-2241 s

N g

w"

$9 gw Wm "c

{M LICENSEE m@

w DURATION M

E EVENT o"

NO.

DATE (IIOURS)

REPORT l*0.

CORRECTIVE ACTIONS / COMMENTS c3 85-49 850901 S

0.0 B

5 CD VALVEX Reduced load to 700 MWe for MSIV surveillance 85-50 850911 S

0.0 H

5 ZZ ZZZZZZ Reduced load to 600 MWe per Load Dispatcher 85-51 850912 S

0.0 H

5 ZZ ZZZZZZ Reduced load to 600 MWe per Load Dispatcher 85-52 850913 S

0.0 B

5 RB CONROD Reduced load to 200 MWe for required scram timing 85-53 850918 S

0.0 B

5 CH PUMPXX Reduced load to 700 MWe for a Feedwater Pump swap 85-54 850919 S

0.0 B

5 CH PUMPXX Reduced load to 700 !!We for a Feedwater Pump swap 85-55 850928 S

0.0 B

5 RC CONROD Reduced load to 700 MWe for a Control Rod Pattern adjustment APPROVED AUG 1 G 1982

, (final) ygg3g

M M

P'"I M

M M

E E

M E

E M

M M

c>

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

050-265 AuRust 1982 UNIT NA*tE

_ Quad-Cities Unit 2 COMPLETED BY C. Kronich DATE October 7,1985 REPORT MONTII SEPTEMBER 1985 TELEPIIONE 309-654-2241 s

5 m

e EU x

y$

m

=

$m

$ 0"d o

LICENSEE go g

-c mo mo DURATION d

EVENT m

u NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS /CONNENTS o

85-39 850901 S

0.0 B

5 CD VALVEX Reduced load to 400 MWe for MSIV surveillance (load drop was terminated at 575 MWe due to 2A Feedwater Regulation Valve problem) 85-40 850908 S

0.0 B

5 CD VALVEX Reduced load to 600 MWe for MSIV surveillance 85-41 850908 F

0.0 B

5 CD VALVEX Reduced load to 280 MWe to repair MSIV's E5-42 850915 S

0.0 H

5 ZZ ZZZZZZ Reduced load to 500 MWe per Load Dispatchez 85-43 850916 S

0.0 H

5 ZZ ZZZZZZ Reduced load to 600 MWe per Load Dispatcher APPROVED AUG 1 G 1982

, (final) ygg3g

.~,

/ - /

.Y i

VI.

UNIQUE REFORTING REQUIREMENTS s

1

[Thefollowingitemsareincludedinthisreportbasedonpriorcommitmento to the commission:

i

' A.

Main Steam Relief Valve Operations Relief valve operations during the reporting period are summarized in the folio'ing table. The table includes information as to which w

relief valve'was actuated, how it was actuated, and the circumstances I

resulting in its actuation.'

(

Unit: One r

Date: Ic~ptember 13, 1985 Valves _ Actuated No. & Type of Actuation 1-2 3-3A 1 Manual 1-203-3B 1 Manual 1-203-3C 1 Manual 1-203-3D 1 Manual 3

l 1-203-3E 1 Manual Plant Conditions:. Reactor Pressure - 940 lbs

~

l Description of Events: Surveillance Technical Specification 4.5.D.1.a l'

j,, ;

B.

Control Rod Drive Scram Timing Data for Units One and Two l!

l4 The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

i The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing 4

was performed with Reactor pressure greater-than 800 PSIG.

i a

i e

u w-r.w w

-n

-~

m em--

~ -

e-e

~

m. e m -

,wn.n-e,-e~n p=

RcSULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL R00 DRIVES, FROM 1-1 TO 12-31-85 AVERAGE TIME IN SECONDS AT %

MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION NUMBER S

20 50 90 Technical Specification 3.3.C.1 &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 (Average Scram insertion Time) 9-13-85 88 0.29 0.66 1.43 2.53 2.91 Unit 1 Sequence A Hot Scram Timina (C-4)

O 002JH/0061Z

i

- i i

VII.

REFUELING INFORMATION-The following information about future relgads 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.

E 1

j i.

i j-i d

E k

a i

I 7

i A--

e

,.y-r

-e.

+

, + -..

=

,4v

-=m

.,*d -

-me

~

QTP 300-S32 Revision 1 QUAD-CITIES REFUELING liarch 1978 INFORMATION REQUEST 1.

Unit:

Q1 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

1-2-86 3

Scheduled date for restart following refueling:

4-2-86 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 licensing action and supporting Information:

DECCIBER 19, 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.

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 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 WPPROVED

.., APR 2 01978 C3. C:. <>. 53. Ft.

I s-e e

m~

QTP 300-532 Revision 1

~

l QUAD-CITIES REFUELING March 1973

~

INFORMATION REQUEST 1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

10-6-86 3

Scheduled date for restart following refueling:

12-22-86 4.

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

Yes. A routine MAPLHGR amendment has been approved as a preparatory change to allow a 10 CFR 50.59 review.

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

Not Applicable.

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 procedurcs:

None planned at present time.

7 The number of fuel assemblies.

I a.

Number of assemblies in core:

724 t.

b.

Number of assemblies in spent fuel pool:

176 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:

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 9.

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

~- APR 2 01978

~

Q. C. o. S. R.

S'

o l

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 i

BWR Boiling 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 HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW 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 SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center

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

TKT-85-51 October 1, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention Document Control Desk Enclosed for your informatior, is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of September, 1985.

Respectfully, COMMONWEALTH EDIS0 p gANY N

QUAD-CITIES NUCL K P WER STATION b

T. K. Tamlyn Services Superintendent bb Enclosure l<

t k

---

ML20133H479

Text

SUMMARY

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