Text

Monthly Operating Repts for June 1986
	ML20207C293
Person / Time
Site:	Quad Cities
Issue date:	06/30/1986
From:	Kronich C, Robey R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	RAR-86-18, NUDOCS 8607210328
	Download: ML20207C293 (23)
	v • d • e

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JUNE, 1986 COMMONHEALTH EDISON COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. OPR-29 AND DPR-30 t

1IO +

0027H/00612

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8607210328 860430 PDR ADOCK 05000254 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 Requirer.. cats A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Refueling Information VIII.

Glossary 0027H/0061Z

l I.

INTRODUCTION i

1 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 f

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 complied by Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 2240 and 2157.

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1 0027H/0061Z 1

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i II.

SUMMARY

OF OPERATING EXPERIENCE 1

A.

Unit One June 1-13 4

j Unit One began the month of June holding load near full power. On June 3, at 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , the unit was placed on Economic Generation Control (EGC). At 0440 hours0.00509 days 0.122 hours 7.275132e-4 weeks 1.6742e-4 months the unit was taken off of EGC, and load was increased to full power. On June 5, at 0455 hours0.00527 days 0.126 hours 7.523148e-4 weeks 1.731275e-4 months , the unit was placed on EGC. On June 7, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , the unit was taken off of EGC for surveillances. At 0150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months the unit returned to EGC operation. On June 8, at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months , the unit was taken off of EGC, and load was dropped to 700 MWe for Turbine surveillances. At 0320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months the unit began a load increase and was placed on EGC at 0427 hours0.00494 days 0.119 hours 7.060185e-4 weeks 1.624735e-4 months .

On June 9, at 2025 hours0.0234 days 0.563 hours 0.00335 weeks 7.705125e-4 months , the unit was taken off of EGC, and load was decreased to approximately 770 MWe for Feedwater Heater problems. On June 10, at 0825 hours0.00955 days 0.229 hours 0.00136 weeks 3.139125e-4 months , the unit was placed on EGC.

At 1755 hours0.0203 days 0.488 hours 0.0029 weeks 6.677775e-4 months the unit was taken off of EGC, and load was increased to full power.

I On June 11, at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months , the unit was returned to EGC operation.

On June 12, at 0243 hours0.00281 days 0.0675 hours 4.017857e-4 weeks 9.24615e-5 months , the unit was taken off of EGC, and load was decreased to 760 MWe to change over Condensate pumps. The unit was returned to EGC at 0332 hours0.00384 days 0.0922 hours 5.489418e-4 weeks 1.26326e-4 months . At 0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months the unit was taken off of EGC to change over Condensate pumps. The unit returned to EGC at 0427 hours0.00494 days 0.119 hours 7.060185e-4 weeks 1.624735e-4 months . At 0905 hours0.0105 days 0.251 hours 0.0015 weeks 3.443525e-4 months the unit was taken off of EGC and load was decreased to approximately 625 MWe due to low Condensate System pressure.

At 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months load began an increase to 760 MWe, and at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months the unit was placed on EGC.

At 2220 hours0.0257 days 0.617 hours 0.00367 weeks 8.4471e-4 months the unit was taken off of EGC, and load was decreased to 500 MWe for IC3 Heater Level Control Valve maintenance. On June 13, at 1310 hours0.0152 days 0.364 hours 0.00217 weeks 4.98455e-4 months , load began an increase to 720

MWe, The load increase was stopped at 668 MWe at 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months for further 1C3 Heater Level Control Valve maintenance.

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1 June 14-30 On June 14, at 0000 hours0 days 0 hours 0 weeks 0 months , load began an increase at 5 MWe/ hour to full 4

power. Eight hundred twenty MWe was reached at 2005 hours0.0232 days 0.557 hours 0.00332 weeks 7.629025e-4 months . On June 15, l

at 0128 hours0.00148 days 0.0356 hours 2.116402e-4 weeks 4.8704e-5 months , the unit was placed on EGC.

On June 16, at 0705 hours0.00816 days 0.196 hours 0.00117 weeks 2.682525e-4 months , the unit was taken off of EGC, and load was increased to full power.

Full power was maintained until June 17 at 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months when the unit was returned to EGC operation.

The unit remained in EGC until June 18, at 2335 hours0.027 days 0.649 hours 0.00386 weeks 8.884675e-4 months , when load was dropped to 755 MWe due to a Recirculation pump seal high temperature. On June 19, at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months , the unit was placed on EGC. At 0920 hours0.0106 days 0.256 hours 0.00152 weeks 3.5006e-4 months the unit was taken off of EGC, and load was increased to full power.

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0027H/0061Z

A.

Unit One (cont.)

On June 21, at 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months , the unit was placed on EGC.

The unit was taken off of EGC on June 22, at 0633 hours0.00733 days 0.176 hours 0.00105 weeks 2.408565e-4 months . Load was increased to full power at 0910 hours0.0105 days 0.253 hours 0.0015 weeks 3.46255e-4 months . On June 24, at 0005 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , load was dropped to 700 MWe to change over Reactor Feed pumps.

At 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months load was in-creased to 740 MWe and at 0225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months the unit was placed on EGC. At 1955 hours0.0226 days 0.543 hours 0.00323 weeks 7.438775e-4 months the unit was taken off of EGC, and later returned at 2155 hours0.0249 days 0.599 hours 0.00356 weeks 8.199775e-4 months .

On June 25, at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months , EGC operation was tripped and load was in-creased to full power.

The unit was returned to EGC operation on June 27 at 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months . At 0510 hours0.0059 days 0.142 hours 8.43254e-4 weeks 1.94055e-4 months EGC operation was tripped, and load was increased to full power. At 0751 hours0.00869 days 0.209 hours 0.00124 weeks 2.857555e-4 months the unit returned to EGC operation. On June 28, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , the unit was taken off of EGC, and load was dropped to 600 MWe for MSIV surveillances. At 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months load began an increase and the unit was placed on EGC at 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months .

On June 29, at 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months , the unit was taken off of EGC, and load was held at approximately 800 MWe due to Feedwater Regulator valve problems for the remainder of June.

B.

Unit Two June 1-18 Unit Two began the month of June shutdown for a scheduled maintenance outage. The Reactor went critical at 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months on June 4.

The unit was placed on line on June 5, at 0356 hours0.00412 days 0.0989 hours 5.886243e-4 weeks 1.35458e-4 months . At 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months the unit was taken off line for a Turbine Overspeed Test, and placed on line again at 0822 hours0.00951 days 0.228 hours 0.00136 weeks 3.12771e-4 months . Load then began a normal increase to full power.

Full power was reached on June 6 at 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months . The unit was placed on EGC at 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months . On June 7, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , the unit was taken off of ECC for Turbine surveillances, and later returned at 0146 hours0.00169 days 0.0406 hours 2.414021e-4 weeks 5.5553e-5 months . At 1622 hours0.0188 days 0.451 hours 0.00268 weeks 6.17171e-4 months load was dropped to 700 MWe for Condensate Demineralizer problems. The unit was returned to EGC at 1910 hours0.0221 days 0.531 hours 0.00316 weeks 7.26755e-4 months .

On June 8, at 1622 hours0.0188 days 0.451 hours 0.00268 weeks 6.17171e-4 months , the unit was taken off of EGC at 775 MWe due to low Condenser vacuum. At 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months the unit was returned to EGC operation.

On June 9, at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months , the unit was taken off of EGC at 775 MWe for Main Steam Line Radiation Monitor work. The unit was returned to ECC at 1045 hours0.0121 days 0.29 hours 0.00173 weeks 3.976225e-4 months . At 1547 hours0.0179 days 0.43 hours 0.00256 weeks 5.886335e-4 months the unit was taken off of EGC, and load was in-creased to full power.

Load was held steady until June 12, at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months , when load was dropped to EGC range and the unit was placed on EGC at 0133 hours0.00154 days 0.0369 hours 2.199074e-4 weeks 5.06065e-5 months . The unit was taken off of EGC at 2357 hours0.0273 days 0.655 hours 0.0039 weeks 8.968385e-4 months on June 13 for Turbine surveillances.

EGC operation was continued at 0047 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months on June 14.

B.

Unit Two (cont.)

On June 15, at 0540 hours0.00625 days 0.15 hours 8.928571e-4 weeks 2.0547e-4 months , the unit was taken off of EGC, and load was dropped to 630 MWe at the Load Dispatcher's request. Load began an increase at 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months , and the unit was placed on EGC at 1356 hours0.0157 days 0.377 hours 0.00224 weeks 5.15958e-4 months . On June 16, at 0903 hours0.0105 days 0.251 hours 0.00149 weeks 3.435915e-4 months , the unit was taken off of EGC, and load was dropped to 780 MWe to recover Condensate booster suction pressure. At 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months load was increased to full power. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months load was decreased to EGC range and the unit was placed in EGC operation.

June 19-30 The unit remained in EGC until June 19, at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months , when load was dropped to 750 MWe to perform maintenance on the Moisture Separator Drain Tank. At 0320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months load was increased to 800 MWe, and at 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months the unit was placed on EGC. At 0840 hours0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months the unit was taken off EGC and load was increased to full power. On June 20, at 0050 j

hours, load was dropped to 750 MWe for further Moisture Separator Drain Tank maintenance. Load was increased and reached full power at 0515 hours0.00596 days 0.143 hours 8.515212e-4 weeks 1.959575e-4 months . The unit was placed on EGC at 1828 hours0.0212 days 0.508 hours 0.00302 weeks 6.95554e-4 months .

On June 21, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , the unit was taken off of ECC at the Load l

Dispatcher's request. At 0208 hours0.00241 days 0.0578 hours 3.439153e-4 weeks 7.9144e-5 months the unit returned to EGC operation.

At 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months the unit was taken off of EGC and load was increased at l

5 MWe/ hour. At 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months load was held steady at 790 MWe until June 22, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , when the unit was placed in EGC operation. EGC was tripped at 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months , and at 0850 hours0.00984 days 0.236 hours 0.00141 weeks 3.23425e-4 months load was increased to full power.

On June 24, at 0905 hours0.0105 days 0.251 hours 0.0015 weeks 3.443525e-4 months , the unit was placed in EGC operation after load was dropped in the EGC range. On June 26, at 1055 hours0.0122 days 0.293 hours 0.00174 weeks 4.014275e-4 months , the unit was taken out of EGC and load was increased to full power. Full power was held until June 28, at 0124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months , when the unit was placed on EGC. On June 29, at 1445 hours0.0167 days 0.401 hours 0.00239 weeks 5.498225e-4 months , the unit was taken off of EGC at 790 MWe.

At 1850 hours0.0214 days 0.514 hours 0.00306 weeks 7.03925e-4 months load was dropped to 700 MWe for Condensate i

Demineralizer maintenance.

On June 30, at 0220 hours0.00255 days 0.0611 hours 3.637566e-4 weeks 8.371e-5 months , load began an increase, and at 0801 hourc the unit was placed on EGC for the remainder of June.

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.A I

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_ -,. _._ I

l III.

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

Amendments to Facility License or Technical Specifications i

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

B.

Facility or Procedure Changes Requiring NRC Approval t

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 1 and 2 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.

0027H/0061Z

UNIT 1

MAINTENANCE SUWARY J

CAUSE RESULTS & EFFECTS

~

W.R.

LER OF ON ACTION TAKEN TO NUhBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q49688 TIP Ball Valve Saall pieces of Testing revealed the During the next outage,

1 metal flaked off Ball Valve would not the TIP Ball Valve was of the pipe in-close within the allowed replaced like-for-like, ternals, and these 5 seconds.

It did Maintenance procedures metal pieces eventually close, which were changed to do more caused excessive effectively isolated preventative maintenance friction within the TIP line, to the TIP Ball Valves.

the Ball Valve.

Q50095 1-1601-61 Lack of lubrica-While testing, the valve The valve shaft and Suppression tion in the valve would only open halfway.

packing were lubricated Chamber Bypass packing.

Several attempts were and the valve was Exhaust Valve made. The main exhaust successfully cycled.

valve (1601-60) was i

operable.

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1 0027H/0061Z J

UNIT 2

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUREER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q49256 EHC Turbine Stop The limit switch The limit switch could The limit switch was l

Valve #1 on the valve not make proper contact repositioned and fixed in operator had with its actuator. The proper position. The Stop loosened on its limit switch for Stop Valve function was then mounting bracket.

Valve #1 was always tested satisfactorily.

This allowed the open. The failure was j

limit switch to in the test circuitry move 1/8 inch.

and the regular control circuitry was fully operable.

Q49997 86-08 2-5748A Core Normal wear of The excessive wear of the The belts were immediately Spray Room belts occur when belts caused the

'A' loop replaced like-for-like.

Cooler the room cooler of Core Spray to be in-Operations personnel will is operated.

operable. Operability now be doing a monthly in-tests for the

'B' loop of spection of the belts.

Core Spray was begun.

7 Q49998 86-08 2-6601 Diesel A wire was loose While testing the Unit 2 The loose terminal was Generator on one of the Diesel, the breaker to tightened, breaker tested control relay's Bus 24-1 tripped, which successfully, & the Unit 2 terminals.

effectively made the

'B' Diesel was operable.

loop of Core Spray in-operable. Declared a GSEP Unusual Event & started i

shutting the Reactor down.

[

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0027H/0061Z

IV.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Tvo 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 1 Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports for Unit 1 for the reporting period.

UNIT 2 Licensee Event Report Number Date Title of Occurrence 86-09 6-26-86 2B Core Spray Room Cooler Inoperable 86-10 6-27-86 Group III Isolation -

Instronent Maintenance personnel installing switch 1

u 0027H/0061Z

V.

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

A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 0027H/00612

OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEJULY 7 1906 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 i

OPERATING STATUS 0000 060186 1.

Reporting period:2400 063086 Gross hours in reporting period:

720 1

j 2.

Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 7694 Design elec tr ical rating (MWe-Net): 789 3.

Power level to wh ich restricted (if any)(MWe-Net): NA 4.

Reasons for restriction (if any):

lhis Month Yr,to Date Cumulative i

5.

Number of hours reactor was critical 720.0 2156.3 98817.7 J

6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 4

l 7.

Hours generator on line 720.0 2110.0 95309.5 l

8.

Unit reserve shutdown hours.

0.0 0 n_

909j 9.

Gross thernal energy generated (MWH)

_ i750116 4960013 199925Y70

10. Gross electrical energy generated (MWH) 565507 1611770 64731141

11. Net electrical energy generated (MWH) 541112 1532.627 605E9160 l

i 12, Reactor service factor 100.0 49.7 79.7 j

13. Reactor availability factor 100.0 49.7 d2.5 i

{

t4. Unit ser v ico factor

._ __1J!J1. Il

_._._40.6

__7_7. O.

15. Unit availability factor 100,0 4f. 6 77.7 j

16 Unit capacity factor (Using MDC)

_ _ 9 7. l/.

49.9

_ _. 6;5 S

17. Unit capoci1y fuctor (Using Des.MWe)

._95 3

44,?'

Ai 9 2

10. Unit fortod outuge rato 0.0

.2 5.0 I

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

20. If t,hutdown at and o f repor t period, estimated date of startup _

NA OH0FFICIAL COMPAM NUMBER 3 APE U3EC IN THIS REPORT

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO I

DATEJULY 7 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 OPERATING STATUS 0000 060186 1.

Reporting period:2400 063086 Gross hours in reporting period:

720 2.

Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (Mue-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 635.7 4013.7 95281.4 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 619.2 3971.3 92268.9 1

8.

Unit reserve shutdown hours.

0.0 0.0 702.9 i

9.

Gross thernal energy generated (MWH) 1476124 9428897 195537920

10. Gross electrical energy generated (MWH) 473489 3083849 62500631

11. Net electrical energy generated (MWH) 452583 2952572 58826831

12. Reactor service factor 88.3 92.4 77.5

13. Reactor availability factor 88.3 92.4 79.9

14. Ur. i t service factor 86.0 91.4 75.0

15. Unit ovallobility factor 86.0 91.4 75.6

16. Unit capacity factor (Using MDC) 81.7 88.4 62.2

17. Unit capacity factor (Using Des.MWe) 79.7 86.2.

60.6 l

18. Unit forced outage rate 0.0

.6 7.9

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

20. If shutdown at end of report period,estinated date of startup ____@(_______

WOFFICIAL COMPANY MJMBERS ARE USED IN THIS REPORT 1

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 254 UNIT ONE DATEJ_QL,_Y.7 1986I COMPLETED BYCAROL L KRf'tICH'-

l 654-241 '

TELEPHONE (309) 1 MONTH June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWe-Net)

(MWe-Net) 1.

781.6 17.

769.5 2.

787.6 10.

735.6 3.

756.3 19, 756.4 3

4, 782.3 20, 770.5 5,

741.9 21, 742.6 '

6.

757.5 22, 770.8 7.

759.5 23.

769.0 1

8.

754.2 24.

754.1 9.

751.2 25.

734.4 10.

766.7 26, 747.8 11, 776.3 27, 782.6 12.

749.6 20.

754.1 13, 561.6 29, 696,i 14, 753.1 30.

754.1 15.

758.1 16, 766.0 INSTRUCTIONS On this fern, list the overage daily snit power level in MWe-Net for each day in the reporting nonth. Compete to the naartst whole negewitt.

These figures will be ssed to plot a graph for each reporting nonth. Note that when notinen dependcble capacity is used for the net elettrical rating of the unit there may be occasions when the daily overage power level exceeds the i

1008 line (or the restricted power level line),.In such tuses,the overage daily u it power entpet sheet should be footnoted to explain the apparent onently

}

4 c-.

.--c,

-,r

, - + -.., _ _ - - - - - -

,, - -- -+

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATElULY 7 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 MONTH June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAIL.Y POWER LEVEL (MWe-Net)

(MWe-Net) 1.

-7.3 17, 762.3 2.

-10.1 18, 730.6 3.

-10.0 19.

757.2 4.

-10.8 20, 752.3 5.

405.6 21.

725.7 6.

743.6 22.

751.4 7.

721.2 23.

750.1 8.

738.9 24.

726.9 9.

732.8 25, 712.4 10.

770.1 26, 739.8 11, 767.0 27, 765.8 12, 725.3 28, 735.5 13.

737.8 29.

719.5 14.

734.0 30, 709.8 15, 716.8 16.

748.4 INSTRUCTIONS On this fern, list the average daily enit power level in IWe-Net for each day in the reporting nonth Compete to the neoPest while negawatt.

These figures will be used to plot a graph for each reparting nonth. Note that when noxinun dependable capacity is used for the net electrical rating of the unit,there nay be occasions when the daily overage power level exceeds the 1888 line (or the restricted power level line).In such cases,the overage daily unit power evtput sheet shseld be footnoted to explain the apparent anonely

M M

F""t m

M M

M y

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 July 7, 1986 REPORT MONTil JUNE 1986 TELEPIIONE 309-654-2241 5

g m

w" 5

$EE gw Wm y

LICENSEE m@

R@

DURATION d

EVENT 5

g NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS /COMhENTS o

86-15 860608 S

0.0 B

5 HA TURBIN Reduced load to 700 MWe for Turbine surveillances 86-16 860612 F

0.0 H

5 HC XXXXXX Reduced load to 625 MWe due to low Condensate pressure 86-17 860613 S

0.0 B

5 CH HTEXCH Reduced load to 665 MWe for 1C3 Heater Level Control Valve maintenance 86-18 860624 S

0.0 B

5 CH PUMPXX Reduced load to 700 MWe to change over Reactor Feed Pumps 86-19 860629 S

0.0 B

5 CD VALVEX Reduced load to 600 MWe for MSIV surveillances i

APPROVED AUG 1 G 1982 (final) ygg3g

M M

m M

M M

M y

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 2 COMPLETED BY C. Kronich DATE July 7, 1986 REPORT MONTil JUNE 1986 TELEPIIONE 309-654-2241 H

N 5

$EE gw Am w

m@

2@

Q LICENSEE DURATION M

EVENT 8"

g u

NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

86-20 860615 S

0.0 H

5 ZZ ZZZZZZ Reduced load to 580 MW2 as per Load Dispatcher 86-21 860629 S

0.0 B

5 HH DEMINX Reduced load to 700 MWe for Condensate Demineralizer maintenance l

i f

APPROVED AUG 1 G 1982

_ (final)

VCUbH

I

)

VI.

UNIQUE REPORTING REQUIREMENTS i

The following items are included in this report based on prior commitments i,

to the commission:

A.

Main Steam Relief Valve Operations l

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.

a Unit: Two Date: June 5, 1986 4

I Valves Actuated No. & Type of Actuation 1

l 2-203-3C 1 Manual 2-203-3E 1 Manual Plant Conditions: Reactor Pressure - 925 psig Description of Events:

Surveillance Technical Specification 4.5.D.l.a j

Post-Maintenance; Replaced Pilot Valves B.

Control Rod Drive Scram Timing Data for Units 1 and 2 There were no Control Rod Drive Scram Timing Data for Units 1 and 2 for the reporting period.

t i

k

VII.

REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E.

O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

0027H/0061Z

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

Unit:

Q1 Reload:

8 Cycle:

9 2.

Scheduled date for next refueling shutdown:

9-14-87 3

Scheduled date for restart following refueling:

12-21-87 4.

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

NOT AS YET DETERMINED.

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

AUGUST 21, 1987 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:

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:

a.

Licensed storage capacity for spent fuel:

3657 0

b.

Planned increase in licensed storage:

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 Q.C.O.S.R.

QTP 300-S32 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 thereaf ter require a technical specification change or other license amendment:

TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPLHGR CURVES),

MCPR OPERATING LIMIT, AND A LICENSE AMENDMENT TO MOVE SINGLE LOOP OPERATION INTO TECHNICAL SPECUICMIONS.

5 Scheduled date(s) for submitting proposed licensing 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 8.

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

a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

0 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 APPROVED t APR 2 01978 C).c:.c).55.Ft.

VIII.

GLOSSARY i

The following abbreviations which may have been used in the Monthly Report, l

are defined below:

)

ACAD/ CAM -

Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor i

CR0 Control Rod Drive i

EHC Electro-Hydraulic Control System i

EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System i

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 MFC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation i

PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System l

RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Worth Minimizer l

SBGTS Standby Gas Treatment System SBLC Standby Liquid Control l

SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume i

SRM Source Range Monitor Turbine Building Closed Cooling Water System l

TBCCH TIP Traversing Incore Probe TSC Technical Support Center i

I I

l i

0027H/0061Z i

i

G.

O Commonwealth Edison cuad Cities Nuclear Power Station 22710 206 Avenue North k

Cordova, Illinois 61242 Telephone 309/654-2241 f

RAR-86-18 July 7, 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 I

covering the operation of Quad-Cities Nuclear Power Station, Units One and Twc, during the month of June, 1986.

Respectfully, COMMONWEALTH EDISON COMPANY CUAD-CITIES NUCLEAR POWER STATION f

Y R. A. Robe Services Superintendent l

j bb f

Enclosure l

l 76 0027H/00612 i

i

_ ________

ML20207C293

Text

SUMMARY

SUMMARY

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