Text

Monthly Operating Repts for Dec 1985
	ML20141K166
Person / Time
Site:	Quad Cities
Issue date:	12/31/1985
From:	Kronich C, Tamlyn T; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	TKT-86-7, NUDOCS 8601220288
	Download: ML20141K166 (26)
	v • d • e

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J QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER 1985 COMONHEALTH EDISON COMPANY I

AND i

IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS.',50-254 AND.-50-265 i

LICENSE NOS. DPR-29 AND DPR-30 a

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8601220288 851231 PDR ADOCK 05000254.

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PDR :

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'1 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 I

VII.

Refueling Information VIII.

Glossary 1

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I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling 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 Bolling Water Reactors.

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

construction contractor was United Engineers & Constructors. The Mississippt River is the condenser cooling water source.

The plant is subject to license i

numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, s

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

The date of i

initial Reactor critica11tles 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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II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One December 1-13 Unit One began the month of December increasing load at 5 MWe/ hour frota a Turbine test.

On December 2, at 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months , the load increase was stopped at 770 MWe due to Feedwater Heater problems., At 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months a load increase to full power continued.

Full power was reached on December 3, at 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months . Load was held steady until December 6, at 0035 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months , when load was dropped to 750 MWe to switch over the Con-densate and Condensate Booster Pumps. At 0125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months a load increase to full power began. Full power was reached at 0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months . At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months load began a drop to 640 MWe for a Control Rod pattern adjustment.. On December 7, at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months , load began an increase.

On December 8, at 0000 hours0 days 0 hours 0 weeks 0 months , the load increase was stopped at 735 MWe.

At 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months load was-dropped to 700 MWe,.for a Control Rod pattern adj ustment. A load increase to full power began at 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months .

Full power was reached on December 9, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , and continued to.

hold steady. The end of full power reactivity was reached on December 12.

December 14-31 On December 14, at 0950 hours0.011 days 0.264 hours 0.00157 weeks 3.61475e-4 months , load was dropped to approximately 740 MWe due to ID1 Feedwater Heater oroblems. At 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months load began an-increase at 5 MWe/ hour. At 1315 hours0.0152 days 0.365 hours 0.00217 weeks 5.003575e-4 months load was held steady at.750 MWe until 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , when load began a drop to 650 MWe for a Control Rod pattern adjustment. On December 15, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , load began an increase at 5 MWe/ hour. At 1255 hours0.0145 days 0.349 hours 0.00208 weeks 4.775275e-4 months , on December 16, load began holding at 615 MWe due to Feedwater Heater problems. A load. increase to full power began on December 17, at 0240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months .

Full power was reached at 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months on December 18.

On December 21, at 0150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months , a load drop to 760 MWe commenced for Turbine tests. At 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months 760 MWe was reached, and at 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months a load increase to full power commenced. Load was held steady until December 27, at 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months , when load was reduced to 700 MWe due'to Off Gas Recombination outside the Recombiner.. A load increase to full power began at 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months . At 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months 796 MWe was reached and held.

Until December 29, at 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months , when load was dropped to 700 MWe due to Off Cas Recombination outside the Recombiner. Load was maintained at approximately 700 MWe for the remainder of. December.

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. B.

Unit Two December 1-31 o

Unit Two began the month of December holding-load at approximately 805 MWe.- On December 2, at 0110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months , load was dropped to 780 MWe to' test -

a Recirculation Loop Pressure Differential Relay. At 0124 hour0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months s-load began an increase to full power. Eight hundred and thirteen MWe was reached at 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months on December 3.

On December 7, at 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months , load was dropped to 793 MWe, and the unit was placed on Economic Generation Control (EGC).

On December 8, at 0042 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months , EGC was tripped and load was increased to 800 MWe.

At 0138 hours0.0016 days 0.0383 hours 2.281746e-4 weeks 5.2509e-5 months the unit returned to EGC.

EGC was tripped on December 9 at 0320 hours0.0037 days 0.0889 hours 5.291005e-4 weeks 1.2176e-4 months , and load began an increase to full power.-

Eight hundred and fifteen MWe was reached at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months and held steady until December 15, at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months , when load began a drop to 750 MWe for Turbine surveillances..;AT 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months 750 MWe was reached,'and at 0245 hours0.00284 days 0.0681 hours 4.050926e-4 weeks 9.32225e-5 months load began an increase to full-power.

Eight hundred and fifteen MWe was reached at 0620 hours0.00718 days 0.172 hours 0.00103 weeks 2.3591e-4 months , and held steady until December 21 at 0015 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months when load began a drop to 760 MWe for Turbine surveillances. At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months load began an increase to 806 MWe.

At 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months 806 MWe was reached, and held until December 24, at 1320 hours0.0153 days 0.367 hours 0.00218 weeks 5.0226e-4 months , when load was dropped below 800 MWe and the unit was placed on EGC.

On December 26, at 0510 hours0.0059 days 0.142 hours 8.43254e-4 weeks 1.94055e-4 months , EGC was tripped and load was increased to full power. On December 28, at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months , load began a drop to 700 MWe for Turbine surveillances.

At 1235 hours0.0143 days 0.343 hours 0.00204 weeks 4.699175e-4 months , load began an increase to 810 MWe.

Eight hundred and ten MWe was reached at 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months .

On December 29, at 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months , load was dropped to 800 MWe and the unit was placed on EGC, On December 30, at 0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months , EGC was tripped and load was increased to 810 MWe. At 0940 hours0.0109 days 0.261 hours 0.00155 weeks 3.5767e-4 months load was dropped to 800 MWe and the unit was placed on EGC at 1005 hours0.0116 days 0.279 hours 0.00166 weeks 3.824025e-4 months . The unit remainded on EGC for the remainder of December.

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t III. PLANT OR PROCEDURE CHANGES. TESTS EXPERIMENTS AND SAFETY RELATED MAINTENANCE I

A.

Amendments to Facility License or Technical Specific-:*ons There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B.

Facility or Procedure Changes Requiring 'RC 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 surmary of the major safety related maintenance performed on Units 1 and 2 during the reporting period. This summary' includes the 4

following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and i

Effects on' Safe Operation, and Action Taken to Prevent Repetition.

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UNIT 1

MAINTENANCE

SUMMARY

l CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN T0.

NUhEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q45300 MO l-2301-48 Vibration caused The valve tripped, &

The motor was replaced &

Breaker-Motor cracking of the would not open a hanger has been added Broke Off; motor housing, completely.or close.

to this line; testing Repaired Motor eventually breaking However, it was open shows this hanger

& Operator the housing enough to assure eliminated critical Internals.

completely.

cooling of the HPCI vibrations.

Tested auxiliary systems.

Satisfactorily.

Redundant path avail-able.

Q45607 85-019 1/2 Diesel Possibilities When attempting to close When the breaker was re-Generator include: dirty the 1/2 Diesel Generator racked, proper contact Breaker to Bus contacts; loose to Bus 13-1, the breaker was made. Contacts were 13-1 wires and a bad tripped. This happened cleaned, several wires HACR synchro-check on several occasions replaced, and a HACR

relay, while testing.was in synchro-check. relay progress.

replaced.

Q45869 l-5746A RHR Thermostats were Thermostat was left in The thermostat'was re-a Room Cooler overlooked when-place until an E.Q.

placed with an E.Q.

4 Thermostat doing E.Q.

approved replacement documentated approved Replaced for inspections, was available. The room thermostat..

E.Q. Program cooler switch was-left in the 'ON' position, by-passing the thermostat-until the approved thermo-stat arrived.

0027H/0061Z

UNIT 1

MAINTENANCE

SUMMARY

t CAUSE RESULTS & EFFECTS W.R.

LER OF ON

' ACTION TAKEN TO NUlEER NIABER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q45870 1-5746B RHR Room The thermostat The thermostat was left The thermostat' was replaced Cooler Thermo-vas overlooked in place, & the room with an E.Q. approved stat Replaced during E.Q.

cooler switch was put thermostat when.one was for_E.Q.

Program.

in 'ON', which bypassed available.

Program inspections.

the non-E.Q. thermostat.

Q45871' l-5748A Core Same as above.

Same as above.

-Spray Room Cooler Thermo-stat Replaced for E.Q.

Program Q45872 1-5748B Core Same as above.

Same as above.

Same as'above.

Spray Room Cooler Thermo-stat Replaced

'for E.Q.

' Program

-Q45873 1-1001-19A Valve The original Valve was operable, but.

The terminal block was Terminal Block terminal blocks with a non-E.Q. approved replaced with an E.Q.

' Replaced for-were not E.Q.

terminal block.

approved' terminal block.

E.Q. Program approved, nor was it possible to-it (lack of documentation).

Q45874~

1-1001-19BLValve Same as above.-

Same as above.

Terminal-Block Replaced for

~ E.Q. Program 0027H/0061Z

UNIT 1

MAINTENANCE SLANARY

[,':c CAUSE RESULTS & EFFECTS W.R.

LER' 0F ON ACTION TAKEN TO NLASER NLASER -

COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION i

L Q45930 A0 1-1601-55 Hardened rubber The valve.did not close The solenoid was rebuilt components in the immediately, but did (the rubber components

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L valve solenoid (0-close 5 min. later.

replaced) and the valve.

rings & diaphragm)

Primary Containment was was tested satisfactorily.-

caused valve to not' maintained.

close completely.

L

'Q46068'&.

1-1001-65D Wood debris from

' Pump could not-produce The wood was removed, the

Q40203

.RHR Service river was not 3500 gpm at 198 PSIG as pump seals were rebuilt,.

Water Pump screened out and required by Technical-and the head gasket was:

passed into the Specifications. All three replaced.

service water, redundant RHR Service lodging in the big Water Pumps were available.

pump impeller.'

Q46317 1-1401-1A Vibration caused a The breaker trip springs The charging seiorlvas

. Core Spray wire inside.the were discharged and could replaced. thelia pump was:

Pump Breaker charging motor to not recharge the breaker.

tested,'and returned to wear the insula-This led to the 1A Core

service, tion off..eventu-Spray loop being in-ally shorting the operable, but redundant motor.

. systems were proved operable.'

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UNIT 2

MAINTENANCE SLANARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO pamFR MAEBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION 1

Q40369 Snubber 2-105 Snubber extension Poor thread engagement Installed longer machine flange was too but it did not affect screws to ensure adequate thick to yield snubber performance nor thread engagement.

good thread hinder thermal movement.

engagement for snubber screws.

Q40380 Snubber 2-122 Documentation Work Request showed in-Work Request was changed discrepancy.

correct size snubber to show correct size.

being installed, but was actually correct size for this application.

Q40383 Snubber 2-31 Unknown.

Cold position setting was SNED review concluded cold out of tolerance.

position setting wa<

satisfactory.

Q40390 Snubber 2-87 Unknown.

Cold position setting was SNED review concluded cold out of tolerance.

position setting was satisfactory.

Q41020 85-006 A0 203-2D Out-Excessive valve Failed Local Leak Rate Valve seats were lapped.

board MSIV seating surface Test during Refuel Main disc, pilot seats and wear.

Outage testing.

pilot discs replaced. Valve then tested satisfactorily.

Q41368 Snubber 2-26 Unknown.

Cold position setting was SNED review concluded cold out of tolerance.

position setting was satisfactory.

Q41894 Snubber 2-36 Snubber extension Poor thread engagement, Installed longer machine flange was too but it did not affect screws to ensure adequate gthick to yield snubber performance nor thread engagement, good thread thermal movement.

engagement for snubber screws.

0027H/0061Z

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MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO l

EREER NLAWER COMPONENT MALFUNCTION SAFE OPERAT10l; PREVENT REPETITION.

Q45861 2-1001-19B The original The valve was operable The terminal block was Replaced Terminal terminal block but with a non-E.Q.

replaced with an E.Q.

Block for E.Q.

was not E.Q.

approved terminal block.

Program approved, nor was it possible to update it (lack of documentation).

Q45862 2-1001-19A Same as above.

Same as above.

Replaced Terminal Block & Drilled Drain Holes for E.Q. Program Q45876 2-5746A RHR Room The thermostat was The thermostat was left The thermostat was replaced.

Cooler Thermo-overlooked during in place and the room with an E.Q. approved thermo-stat Replaced the E.Q. Program cooler switch was put stat when one was available.

for E.Q. Program inspections, in 'ON' position, by-passing the non-E.Q.

approved thermostat.

Q45877 2-5746B RHR Room Same as above.

Same as above.

Cooler Thermo-stat Replaced for E.Q. Program -

Q45878 2-5748A Core Spray Same as above.

Same as above.

Room Cooler Thermo-stat Replaced for E.Q. Program Q45879 2-5748B Core Spray Same as above..

Same as above.

Same as'above.

Room Cooler Thermo-stat Replaced for E.Q. Program 0027H/0061Z

UNIT 2

MAINTENANCE StANARY

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CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO IMBER pasRFR Cor0NENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q40363 2-5742A Reactor Dirt caused the The damper did not close The failed air solenoid Bldg Exhaust air solenoid during Secondary Con-valve was replaced like-Isolation valve to hang-up.

tainment testing, however, for-like. The damper was Damper This, in turn, the redundant 2-5742B then tested successfully.

prevented the closed as required, damper from fully closing.

0027H/0061Z-s

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.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 85-20 12-10-85 Auto-Start of Standby Gas Treatment System During Fuel Pool Radiation Monitor Surveillance 85-21 12-13-85 RCIC Inoperable Due to Fuse in Controller 85-22 12-28-85 Failure of Standby Gas Treatment System to Produce Flow; Failure of 'B' Standby Gas Treatment to Start in STANDBY UNIT TWO Licensee Event Report Number Date Title of Occurrence 85-23 12-26-85 HPCI Inoperable Due to Failure of 2-2301-4 Valve to Open I

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4 V.. DATA TABULATIONS-l The following data tabulations are presented.in this report:

A.

Operating Data Report B.

Average Daily Unit Power Level j

C.

Unit Shutdowns and Power Reductions i

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OPERATING DATA REPORT s

50-254 q

. DOCKET NO.

'{,

UNIT ONE s

le DATEJANUARY 3 1986 COMPLETED BYCAROL L KRONICH L

,V TELEPHONE (30V) 654-2241-1 OPERATING STATUS 0000 120185

[

i. Reporting period:2400 123185 Gross hours in reporting period 744

2. Currently authorized power level (MWt): 25ti Max Depend capacity (MWe-Net): 769* Desigt electrical rating (MWe-Net): 789

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3. Power' level to which restricted (if any)(NWe-Net): NA b

+

4.

Reasons for restriction (if any):

This Month Yr.to Date Cumulativa 5.

Number of hours reactor was critical

744Lp, 8338.9 96661.4 6.

Reactor reserve shutdown hours 0.0 O.0 3421'9 1

7.

Hours generator on line 744.0 8244.2 93279.5 8.

Unit reserve shutdown hours.

0.0 0.0 909.2 9.

Gross thermal energy generated (MWH) 17335S0 19218767 194965157

\\

10. Gross electrical energy generated (MWH) 578930

'6341920 63119371 s

11. Het electrical energy generated (NWH) 555014 6070831 59026533

12. Reactor service factor 100 1 95.2 80.8

13. Reactor avo11ob111ty factor 100.b' 95.2 83.7

14. Unit service factor s

100.0.

94.1 78.0

15. Unit availability factor 100.0 94.1 78.8

16. Unit capacity factor (Using MDC) 97.0 90.1 64.2

17. Unit capacity factor (Using Des.HWe) 94.5 87.8 62.6

18. Unit forced outage rate e 0.0 4.1 5.9

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

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

___EL________

sThe MSc ner be lever then %9 leie dering perleds of high emblent temperatore du to the thernal perfernance of the sprop cenel.

8WWFICIAL CCWM MHWERS ARE UK9 Ill THIS REPORT s

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~ 0PERATING DATA REPORT l-DOCKET N0'.

50-265 UNIT TWO DATEJANUARY 3 1986 COMPLETED BYCAROL L KRONICH f

TELEPHONE (309) 654-2241 j

OPERATING STATUS 0000 120185' l

1. Reporting period 2400 123185 Gross hours in-reporting period:

744

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

,;. t (hWe-Net): 769* Design electrical' rating (MWe-Net): 789 i

[

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

4. Reasons for restriction (if any):

f 1

This' Month Yr.to'Date Cumulative:

5. Number of hours reactor was critical 744,0 6361.7 91267.7 l

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 744.0 6248.5 88297.6' 8.

Unit reserve shutdown hours.

0.0 0.0-

'702.9

}

9. Gross thernal energy generated (MWH) 1812441 14589956' 186109023

10. Gross electrical energy generated (MWH) 596158 4763371-59416782; f

ii. Net electrical energy generated (MWH) 572136

'4556274~

~ 55874259

12. Reactor service factor 100.0 72.6

'76.9 i

13. Reactor availability factor 100.0

'72.6 79.'4 l

14. Unit service factor

-100.0 71.3 74.4

_-15.

Unit ovallobility factor 100.0 71.3 75.0 i

1.

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16. Unit capacity factor (Using MDC) 100.0' 67.6

' 61.'2

17.. Unit capacity factor (Using Des.MWe) 97.5 65.9 59.7

18. Unit forced outage rate 0.0 4.8 8.2-

!~

19. Shutdowns scheduled.over'next 6 nonths (Type,Date,and'Durationfor each)'s

20. If shutdown at and~of report period,estinated date of startup __,,,f_________

.8The 10C not be louer the 7M IRie dering perleds of high edlent temperatore doe to the thernal perfernece of the sprep canal.

8WWF1tlAL CNNilt IIIERS AAE M9 Ill 19115 IEPWT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEJANUARY 3 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 MONTH ~ December-1985 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

'739.4 17.

652.2 2.

730.4 18. -

764.4 3.

780.2 19.

786.3 4.

810.8 20.

789.1 5.

778.3 21, 763.9-6.

779.7 22, 770.8 7.

651.9 23.

779.1 8.

734.0 24.

754.5 9.

807.5 25, 752.4 10.

796.8 26.

763.3 ii.

817.3 27, 707.6 12, 768.6 28.

725d 13.s:

793.9 29.

690.0 14.

730.7

, 30, 677.5 15.

676.3 31.

678.7' 16.

677.5 INSTRUCTIONS CJ this fwn, list tk enrega delly enit power level in ille-tiet for each dey in the reporting math.Conpete to the neerest uhele negemett.

These figeres will be esed to plot a graph fw each repwting nenth. Note that when no inen dependeble cepecite is i

otti for the net electrical rating of the enit 1s51 line (or tk restricted power lesel line),there ney h eccesiens when tk delly eserege peuer leetl exceeds the i

.In sKh cases 3the seerege delly enit power eetpet sheet thseld be-festnoted to explain ik apperant anonely I

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y

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APPENDIX B l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEJANUARY 3 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 MONTH December 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(HWe-Net) 1.

786.8 17, 766.9 2.

761.7 18.

778.9 3.

770.0 19, 781.8 4.

793.4 20.

786.9 5,

759.6 21.

771.5 6.

770.6 22.

777.6 7.

752.0 23.

788.7 8.

739.8 24, 758.9 9.

782.7 25.

739.8 10, 775.6 26.

772.2 ii.

794.7 27.

752.6 12.

752.6 28, 771.7 13.

783.2 29.

747.8 14.

772.4 30.

752.0 15, 782.0 31.

730.8 16, 776.0

-INSTRUCTIONS On this fwn, list the enrege delly alt pouer lewl in ille-ht fu euh det in the repwting nenth.Compwte to the -

newest uhele negemett.

These figures alll be esed to slet a graph for each reporting nenth, liste that uhen ne:Inen dependable gepetitt is osed fw the net electrical reilng of the salt b

iltI line (or the restricted pouer len1 line),there not e eccesiens when the dellt enrege peer leset exceses the

.In sub cases,the enrega dellt mit peuer eetpet sheet sheeld be feetnoted to explain the oppe ent m onely

m M

P""1 M

M M

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 January 6, 1986 REPORT HONill DECEMBER 1985 TELEPil0NE 309-654-2241 g

N w"

B

@w Mw Q

LICENSEE m@

g"@

O w

DURATION M

EVENT o"

NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

85-64 851206 S

0.0 H

5 HH PUMPXX Reduced load to 750 MWe to switch Condensate Pumps 85-65 851206 S

0.0 H

5 RC CONROD Reduced load to 640 MWe for Control Rod Pattern adjustment 85-66 851214 F

0.0 H

5 CH HTEXCH Reduced load to 740 MWe due to 1D1 Feedwater Heater problems 85-67 851214 S

0.0 H

5 RC CONROD Reduced load to 650 MWe for Control Rod Pattern adjustment 85-68 851216 F

0.0 H

5 CH HTEXCH Reduced load to 610 MWe due to Feedwater Heater trip 85-69 851221 S

0.0 B

5 HA TURBIN Reduced load to 760 MWe for Turbine tests 85-70 851227 F

0.0 H

5 XX RECOMB Reduced load to 700 MWe due to Off Gas Recombination outside the Recombiner 85-71 851229 F

0.0 H

5 XX RECOMB Reduced load to 700 MWe due to Off Gas Recombination outside the APPROVED Recombiner AUG 1 G 1982 (final) ygg3g

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

050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY C Kronich DATE January 6, 1986 REPORT HONTil DECEMBER 1985 TELEPil0NE 309-654-2241 H

N et n

g m

x h

h LICENSEE EVENT o"

DURATION

!E g w

u NO.

DATE (Il0URS) o REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

85-51 851215 S

0.0 B

5 HA TURBIN Reduced load to 750 MWe for Turbine surveillances 85-52 851221 S

0.0 B

5 HA TURBIN Reduced load to 760 MWe for Turbine surveillances 85-53 851228 S

0.0 B

3 e

HA TURBIN Reduced load to 700 MWe for Turbine surveillances APPROVED AUG 1 G 1982 (final) yCUdH

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 ORIVE SCRAM TIMING OATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

6 l

t n

l 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.

j ll f

I l

4

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

Unit:

Q1 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

1-5-86 3

Scheduled date for restart following refueling:

3-29-86 4.

Will refueling or resumption of operation thereafter require a technical I

specification change or other license amendment: YES. A ROUTINE MAPLHGR AMENDMENT HAS BEEN SUBMITTED AS A PREPARATORY CHANGE TO ALLOW A 10 CFR 50.59 REVIEW OF THE RELOAD. TECHNICAL SPECIFICATION CHANGE TO ALLOW HAFNIUM ABSORBER MATERIAL HAS BEEN SUBMITTED.

l 5

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

6.

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

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

A) USE OF 8 ASEA-ATOM CONTROL BLADES CONTAINING HAFNIUM.

B) CONTINUED USE OF TWO BARRIER LEAD TEST ASSEMBLIES.

7 The number of fuel assembites.

I a.

Number of assemblies in core:

724 b.

Number of assemb!Ies in spent fuel pool:

1678 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 XPPROVED 1-APR 2 01978 Q.C.O.S.R.

,v-v-

l.

\\

t QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 1

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 thereafter require a technical specification change or other license amendment:

NOT AS YET DETERMINED.

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

SEPTEMBER 19, 1986, IF REQUIRED.

6.

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

' different fuel design or supplier, unreviamed 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 assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

838 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:

Licensed storage capacity for spent fuel:

3897 a.

1 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refue1Ing that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 XPPROVED APR 2 01978 C3. c:. C). !B. ft.

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 t

ANSI American National Standards Institute i

APRM Average Power Range Monitor ATHS Anticipated Transient Without Scram BWR Boiling Hater Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facili_ty GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter 1

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 Laak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor l

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 i

NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation.

PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH Reactor Building Closed Cooling Hater System RBM Rod Block Monitor J

RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System i

RPS Reactor Protection System RWM Rod North Minimizer l

SBGTS Standby Gas Treatment System j

SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCH Turbine Building Closed Cooling Water System l

TIP' Traversing Incore Probe:

j TSC Technical Support Center

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Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 TKT-86-7 January 10, 1986 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Gentlemen:

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 December, 1985.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION 2

T. K. Tamlyn Services Superintendent bb Enclosure

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l

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