Text

Monthly Operating Repts for Jul 1985
	ML20134E121
Person / Time
Site:	Quad Cities
Issue date:	07/31/1985
From:	Kronich C, Tamlyn T; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	0027H, 0061Z, 27H, 61Z, TKT-85-42, NUDOCS 8508190623
	Download: ML20134E121 (23)
	v • d • e

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY 1985 COMMONNEALTH EDIS0N COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY 4

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 0027H 8508190623 850731 h

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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 i

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 4

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 0027H 0061Z

I.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling Hater Reactors, each with a Maximum Dependable Capacity of 769 MHe 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 Hater Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.

The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.

This report was compiled by Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 127 and 193.

0027H 0061Z

II.

SUMMARY

OF OPERATING EXPERIENCE A. -Unit One July 1-7 Unit One began the month of July increasing load to full power. On July 1, at 2115 hours0.0245 days 0.588 hours 0.0035 weeks 8.047575e-4 months , load reached 810 MWe. On July 2, at 1652 hours0.0191 days 0.459 hours 0.00273 weeks 6.28586e-4 months , the unit was placed on Economic Generation Control (EGC). EGC was tripped on July 6, at 0012 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and load was dropped to 700 MWe for Turbine surveillances. At 0605 hours0.007 days 0.168 hours 0.001 weeks 2.302025e-4 months load began an increase to 730 MWe and, the unit was placed on ECC at 0642 hours0.00743 days 0.178 hours 0.00106 weeks 2.44281e-4 months .

July 8-15 On July 8, at 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months , EGC was tripped and the unit began a load increase to full power. At 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , load reached 812 MWe and held steady. On July 9, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , load began a decrease to 730 MWe so that condenser flow could be reversed. At 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months load began an increase to 800 MWe. At 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months load was dropped to 7501Rhi in preparation for EGC. At 0340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months the unit was placed on ECC. On July 10, at 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months , load began a drop to ninimum power as per the Load Dispatcher. Minimum power was reached on July 11 at 0105 hours0.00122 days 0.0292 hours 1.736111e-4 weeks 3.99525e-5 months .

At 0452 hours0.00523 days 0.126 hours 7.473545e-4 weeks 1.71986e-4 months load began a normal increase to full power. On July 12, at 0325 hours0.00376 days 0.0903 hours 5.373677e-4 weeks 1.236625e-4 months , load held steady at 812 1852.

July 16-24 On July 16, at 1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months , load was dropped to 790 MWe in preparation for EGC. The unit was placed on EGC at 1748 hours0.0202 days 0.486 hours 0.00289 weeks 6.65114e-4 months . On July 21, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , EGC was tripped and load began a drop to 550 MWe for a rod pattern exchange. Five hundred and fif ty MWe was reached at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months , and load was increased normally. On July 22, at 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months , load was decreased by 30 inha to 700 MWe for rod adjustments.

On July 23, at 0835 hours0.00966 days 0.232 hours 0.00138 weeks 3.177175e-4 months , load began a drop to 550 MWe for rod pattern adjustments due to thermal limit problems. Load reached 550 1Rhn at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months , and began a 5 MWe/ hour increase at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months .

On July 24, at 1645 hours0.019 days 0.457 hours 0.00272 weeks 6.259225e-4 months , load was dropped to 550 MWe for rod pattern maneuvers due to thermal limit problems. At 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months load was increased 100 MWe/ hour to 650 MWe and then increased 5 MWe/ hour.

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July 25-31 On July 25, at 1120 hours0.013 days 0.311 hours 0.00185 weeks 4.2616e-4 months , a normal orderly shutdown commenced at 25 IfWe/ hour due to Technical Specifications, because LPCI became inoperabic. At 1412 hours0.0163 days 0.392 hours 0.00233 weeks 5.37266e-4 months the shutdown was terminated at 650 MUe, and a normal load increase to full power began. On July 27, at 0815 hours0.00943 days 0.226 hours 0.00135 weeks 3.101075e-4 months , load reached 812 IEh3 and remained steady. On July 28, at 0015 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months , load was dropped to 700 MWe for Turbine surveillances.

At 0135 hours0.00156 days 0.0375 hours 2.232143e-4 weeks 5.13675e-5 months load began an increase to 808 MWe and held steady for the remainder of July.

B.

Unit Two July 1-7 Unit Tuo began the month holding load at 809 MWe, On July 2, at 0835 hours0.00966 days 0.232 hours 0.00138 weeks 3.177175e-4 months , load was dropped to 770 MWe in preparation for Economic Generation Control (EGC). At 0924 hours0.0107 days 0.257 hours 0.00153 weeks 3.51582e-4 months , the unit was placed on ECC.

On July 7, at 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months , ECC was tripped and load was decreased to 700 MWe for Turbine surveillances. At 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months load was increased to 740 IEhe and at 0340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months the unit was placed on EGC.

July 8-10 On July 8, at 0725 hours0.00839 days 0.201 hours 0.0012 weeks 2.758625e-4 months , EGC was tripped and load began a normal increase to full power. Eight hundred and ten IEhr was reached at 0822 hours0.00951 days 0.228 hours 0.00136 weeks 3.12771e-4 months on July 9; at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months load was decreased to 750 IGh! for EGC operation. At 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months , 750 HRe was reached and the unit was placed on ECC. At 0611 hours0.00707 days 0.17 hours 0.00101 weeks 2.324855e-4 months , EGC was tripped and load was increased to full power. On July 10, at 0405 hours0.00469 days 0.113 hours 6.696429e-4 weeks 1.541025e-4 months , load was decreased to 700 MWe as per the Load Dispatcher. At 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months the load decrease was stopped and the unit began an increase to full power.

July 11-31 Cn July 11, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , load began a decrease to 650 MWe as per the Load Dispatcher. Six hundred and fifty MUe was reached at 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

At 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months , load began a normal increase to full power. Full power was reached at 1410 hours0.0163 days 0.392 hours 0.00233 weeks 5.36505e-4 months and held steady. On July 20, at 0015 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months , load was decreased to 600 MWe for Turbine surveillances and was held for main transformer problems and tests. On July 22, at 0840 hours0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months , load began an increase to full power. On July 27, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , load was dropped to 700 MRe for Turbine surveillances. At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months load began a normal increase to full power. Full power was reached at 1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months and was held steady. On July 31, at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , load was dropped to 790 MWe and the unit was placed on ECC.

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

Amendments to Facility License or Technical Specifications On February 25, 1985, the NRC issued Amendment 85 to License DPR-30.

This amendment establishes an increase in the maximum allowable Linear Heat Generation Rate (LHGR) for the End of Cycle 7 Barrier Fuel Ramp Test.

On !by 30, 1985, the NRC issued Amendments 86 and 87 to License DPR-30.

Amendment 86 establishes the implementation of Analog Trip Systems in the Reactor Low Water Level, Reactor Water Level, HPCI High Steam Flow, and HPCI Steamline Low Pressure Instrumentation.

It also establishes the installation of level switches and related instrumentation in the Scram Discharge Volumes. This includes changes to the pertinent Reactor Protection System Instrumentation Requirements, Logic Systems Functional Tests, and Minimum Calibration Frequencies Tables. The amendment also shows the new Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Planar Average Exposure Curve for the new Unit Two core.

Amendment 87 establishes Hafniam metal as an allowable material of control rods.

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 sunnary 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 l

UNIT 1

MAINTENANCE SUW4ARY CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUW3ER NulEER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION There were no Safety Related Work Requests closed out for Unit One for the reporting period.

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UNIT 2

MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO l

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q42478 85-13 Unit 2 Diesel Governor compensa-Diesel Generator ran Correctly adjusted the Generator ting mechanism was 30 seconds, then governor compensating out of adjustment tripped out on over-mechanism, due to normal speed. Unit 1/2 l

operational wear.

Diesel Generator out I

of service. Declared CSEP.

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-Q42952 2B Main Steam Instrument set-Line Radiation point drift.

Monitor (Recalibrated)

Q43519 2-1001-18A Unknown at this Valve was cycling open Valve operator was found RHR Pump time.

See Work and closed with no separated from valve body, Minimym Flow Request Q43885.

pumps on, and was continuously Valve operating. This gave an erroneous open and close signal. For final action see Work Request Q43885; August 1985 Monthly Report.

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0027H/0061Z l

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.I. and 6.6.8.2. of the Technical Specifications.

UNIT ONE Licensee Event 4

Report Number Date Title of Occurrence 85-09 7-25-85 Low Pressure Coolant Injection Inoperable; Required Shutdown 1

j 85-10 7-28-85 Reactor Core Isolation Cooling Inoperable Due i-to Failed Overspeed l

Meter

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UNIT IUO l

Licensee Event i

Report Number Date Title of Occurrence 85-16 7-29-85 Standby Cas Treatment Auto-Start Due to Fuel Pool Monitor Spike i

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V.

DATA TABULATIONS 4

l The following data tabulations are presented in this report:

1 A.

Operating Data Report j

B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions i

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0027H' 0061Z

OPERATING DATA REPURT DOCKET NO.

50-254 UNIT ONE

1) ATE @[ GUST 6 1985 COMPLETED BYCAROL L, KRONICH TELEPHONE (309)654-2241X19 OPERATING STATUS 0000 070105 1.

Reporting period:2400 073185 Gross hours in reporting period:

744 2,

Currently authorized power level (MWt>' 2511 Max. Depend copocity (MWe-Net): 769* Design electrical rating (Muc-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 744.0 4838.0

'73160,4 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator ' on line 744.0 4780.4 89815.7 8.

Unit reserve shutdown hours.

0.0 0.0 909.2 9.

Gross thermal energy generated (MWH) 1724887 11206254 186952644

10. Gross electrical energy genercted(MWH)

561727, 3693568 60471019

11. Net electrical energy generated (MWH) 537014 3536102 56491004

12. Reactor service factor 100.0 95.1 80.4

13. Reactor ovallobility factor 100.0 95.1 83,3

14. Unit service factor 100,0 94.0 77.5

15. Unit availability factor 100.J, 94,0 78.3

16. Unit capacity factor (Using MDC) 93.9 90.4 63.4

17. Un it copocity factor (Using Des.MWe) 91.5 88,1 61.8

10. Unit forced outage rote 0.0 6,0 6,1 19, Shutdowns scheduled over next 6 months (Type,Date,ond Duration of each):

20. If shutdown at end of report period, estimated date of startup NA tThe PDC e n k l wer then 769 MWe during periods of high cabient temperature due to the the m l perfernance of the spray canal.

TUN 0FFICIAL CCr?ANY NUMBERS ME U50 IN THIS REPORT

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEAUGUST 6 1985 COMPLETED BYCAROL L.

KRONICH TELEPHONE (309)654-2.241X19 OPERATING STATUS 0000 070185

i. Reporting period:2400 073t85 Gross hours in reporting period:

744 2.

Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net)- 789 3.

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

Reasons for restriction (if anv):

This Month Yr,te Date CuMulotive 5.

Number of hours reactor was critical 744.0 2975.8 07081.8 6,

Reactor reserve shutdown hours 0,0 0.0 2985.8 7.

Hours generator on line 744.0 2903.9 84953.1 8.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thermal energy generated (MWH) 1780205 6649052 178168119'

10. Gross electrical energy generated (MWH) 575235 2161789 56815200

11. Net electrical energy generated (MWH'.

550535 2065040 53383025

12. Reactor service' factor 100.0 58.5 76.4

)

13. Reactor availability factor 100.0 58.5 79.0

14. Unit service factor 100.0 57.1 73.9 4

15. Unit availability factor 100.0 57.1 74.5

16. Unit capacity factor (using MDC) 96.2 52.8 60.4

17. Unit capacity factor (Using Des.MWe) 93__.8 51.5 58.8 l

18. Unit forced outage rate 0.0 6.2 8.3

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

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

The MDC ncy be laer than 769 MWe decir.g periods -f high cmbient temperatore due 19 the thermal perfern ete of the sprcy c;nal.

UNOFFICIAL COMPANY NTIERS ARE USED IN THIS REPORT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-254 UNIT ONE DATEAl! GUST 6 1985 COMPLETED BYCAROL L.

KRONICH j

T ELEP HONEg 09 ') 654-2241 X 19 l

MONTH Julv 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

764.3 17.

714,3 2.

'741.3 10, 730,8 3.

741.0 19, 734.5 4

73i.8 20.

"? 2523 5,

731,6 21, 578.1 6,

716,5 22, _

654,9 7.

728,9 23.

607.7 8.

759.3 24, 580,2 9.

728.1 25, 651.7 10.

725',1 26.

719,2 11, 617,6 27, 772,7 12.

773,5 28.

762,5 13, 765,0 29.

774,2 14,

'759.2 30, 775.0 15.

764,6 31, 780.0 16.

759,9 INSTRUCTIONS

.On this forn, list the overage daily snit power level in Mie-Net for each day in the repstting nonth, Compute to the nearest whole negcwatt.

These figtres will be ssed to plot a crash for enth reperting conth, Note that when noxinen dependable capacity is uset for the net electrical rating of'the snit there may be occasions when the daily overage power level exceeds the 13011 ice (or the restricted power level lire),In ssth cases,the overage daily snit power estput sheet shesid be festnoted to esplein the cap: rent entnsly

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APPENDIX D AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEAUGUST 6 1985 COMPLETED BYCAROL L.

KRONICH TELEPHONE (309)654-2241Xi9 MONTH Julv 1985 DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

800.5 17.

764.8 2.

718.2 iB.

769.3 3.

723.5 19, 761.0 4.

716.2 20, 573.0 5.-

735.0 21, 580.2 6.

733.7 22.

663.6 7.

732.8 23.

748.7 8.

754.1 24.

776.4 9.-

754.9 25, 752.9 10.

'773.5 26.

767.4 ii.

712.5 27, 736.0 12, 763.2 28.

765.7 13.

764.0 29.

766.6 14.

761 3 30, 769.7 15, 762.2 31.

778,i 16.

761.7 4

INSTRUCTIONS' -

On this f[re, list the overcge daily vnit power level in PW-Net for each dty in the reporting nonth.Consste to the' ntirest w< ele nee m tt.

These fiques will be esed ts plot a q?ch for each reporting nonth. Note that when narinun dependeble cc;ccity is used for the net electrical rating of the vait,there nas te occasions when the daily overo;e psuer level exceeds the 1961 lint (or the restricted power level line).In such cases,the averagt daily Unit power cotpet sheet shsvid he festnoted to explain the apparent anssaly t

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1 ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C. Kronich l

DATE August 6, 1985 REPORT MONTil JULY 1985 TELEPil0NE 309-654-2241 p

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DATE (110URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS A

85-34 850706 S

0.0 11 5

llA TURBIN Reduced load to 700 INe for Turbine surveillances 85-35 850709 S

0.0 11 5

XX ZZZZZZ Reduced load to 750 INe to place unit on Economic Generation Control (EGC) 85-36 850710 S

0.0 11 5

ZZ ZZZZZZ Reduced load to minimum per Load Dispatcher 85-37 850716 S

0.0 11 5

XX ZZZZZZ Reduced load to 790 INe to place unit on Economic Generation Control (EGC) 85-38 850721 S

0.0 11 5

RC CONROD Reduced load to 550 INe for Control Rod pattern adjustment l

85-39 850723 S

0.0 11 5

RC FUELXX Reduced load to 550 INe for rod pattern adjustment due to thermal limit problems 85-40 850724 S

0.0 11 5

RC FUELXX Reduced load to 550 FNe for rod pattern adjustment due to thermal limit problems I

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

050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C. Kronich DATE August 6, 1985 REPORT MONTil JULY 1985 TELEPil0NE 309-654-2241 5

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NO.

DATE (IIOURS)

REPORT NO.

CORHECTIVE ACTIONS / COMMENTS ca 85-41 850725 F

0.0 D

5 85-09 ZZ ZZZZZZ Commenced orderly shutdown due to LPCI inoperability (terminated shutdown--

2.87 hours0.00101 days 0.0242 hours 1.438492e-4 weeks 3.31035e-5 months ) 85-42 850728 S

0.0 11 5

IIA TURBIN Reduced load to 700 !!We for Turbine surveillances APPROVED AUG 1 G 1982

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ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY C. Kronich DATE August 6, 1985 REPORT HONTil JULY 1985 TELEPil0NE 309-654-2241 g

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DURATION M

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NO.

DATE (110URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS ca 85-26 850702 S

0.0 11 5

XX ZZZZZZ Reduced load to 770 MWe to place unit on Economic Generation Control (ECC) 85-27 850707 s

0.0 11 5

HA TURBIN Reduced load to 700 FMe for Turbine surveillances 85-28 850709 S

0.0 11 5

XX ZZZZZZ Reduced load to 750 INe to place unit on Economic Generation Control (ECC) 85-29 850710 S

0.0 H

5 ZZ ZZZZZZ Reduced load per Load Dispatcher 85-30 850711 S

0.0 11 5

ZZ ZZZZZZ Reduced load per Load Dispatcher 85-31 850720 S

0.0 11 5

IIA TURBIN Reduced load to 600 !Me for Turbine surveillances, and remained at 600 INe for main transformer problems and tests 85-32 850727 S

0.0 11 5

HA TURBIN Reduced load to 700 !Me for Turbine surveillances APPROVED AUG 1 G 1982

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VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

A.

MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B.

CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There'was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

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I 0027H 0061Z

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

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

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QTP 300-S32 b

I Revision 1 I

QUAD-CITIES REFUELING Harch 1978 INFORMATION REQUEST e

1.

Unit:

QI Reload:

7 Cycle:

8 1-2-86 2.

Scheduled date for next refueling shutdown:

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 IIcensing action and supporting Y

Information:

g DECC4BER 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.

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7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 k

l b.

Number of assemblies in spent fuel pool:

2340 i

8.

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

(

l a.

Licensed storage capacity for spent fuel:

3657 l

b.

Planned increase in licensed storage:

O P

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

spent fuel pool assuming the present IIcensed capacity: 2003 WPPROVED APR 2 019'18 L.,

Q.C.O.S.R.

10 A'

7-QTP 300-S32 l*

Rsvision 1 I

QUAD-CITIES REFUELING March 1976 INFORMATION REQUEST l

o 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:

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 proposed licensing action and supporting Information:

Not Applicable.

6.

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

' dif ferent fuel design or supplier, unreviewed design or performance analysis i

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

i None planned at present time.

r

/

7 The number of fuel assemblies.

L a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

176 8.

The present licensed spent fuel pool storage capacity and the size of any l

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

I a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in IIcensed 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 Y

y

o. c. o. s. a.

L 5._..._...._._..

m

m; i

a 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 BWR Bolling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System l

HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Event Report l

LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LFRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate HCPR 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 Worth 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 0027H 0061Z

1 1

1 Commonwealth Edison Quad Citie= Nuclear power Station l

22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 TKT-85-42 August 1, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention Document Control Desk Enclosed for your information is the !!onthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of July, 1985.

Respectfully, CO?DIONWEALTil EDISON C0!!PANY AD-CITIES NUCLEAR POWER STATION T. K.

lyn Services Superintendent bb Enclosure

.h i

ML20134E121

Text

SUMMARY

SUMMARY

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