Text

Monthly Operating Repts for Oct 1985
	ML20136F702
Person / Time
Site:	Quad Cities
Issue date:	10/31/1985
From:	Kronich C, Tomlyn T; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	TKT-85-57, NUDOCS 8511220173
	Download: ML20136F702 (25)
	v • d • e

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT OCTOBER, 1985 COMMONWEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30

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' B511220173 851031 PDR ADOCK 05000254 l , , R PDR I

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TABLE-OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. ' Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary

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i I. INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company 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 construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March _10, 1973 for Unit Two.

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

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit one October 1-12 Unit One began the month of October on Economic Generation Control (EGC).

On October 1, at 0013 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months , EGC was tripped at 748 MWe, and load was dropped to 700 MWe for Turbine surveillances. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months load began an increase to 750 MWe, and at 0325 hours0.00376 days 0.0903 hours 5.373677e-4 weeks 1.236625e-4 months the unit was returned to EGC.

On October 5, at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months , EGC was tripped at 750 MWe and load began a decrease to 500 MWe for a control rod pattern adjustment. On October 6, at 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months , load began a normal increase to full power. Eight hundred twenty-six MWe was reached and held on October 8, at 1625 hours0.0188 days 0.451 hours 0.00269 weeks 6.183125e-4 months .

On October.9, at 2345 hours0.0271 days 0.651 hours 0.00388 weeks 8.922725e-4 months , load was dropped to 800 MWe in preparation for EGC. The unit was placed on EGC on October 10, at 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months . At 0720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months , EGC was tripped and load was increased to full power. Eight hundred twenty-six MWe was reached at 1110 hours0.0128 days 0.308 hours 0.00184 weeks 4.22355e-4 months . At 2325 hours0.0269 days 0.646 hours 0.00384 weeks 8.846625e-4 months the unit was returned to EGC.

October 13-31 On October 13, at 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , EGC was tripped for a Turbine surveillance.

The unit was returned to EGC at 011b hours. EGC was tripped on October 14, at'2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , at 800 MWe and held until 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months , when the unit l .was returned to EGC. On October 15, at 0902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months , EGC was tripped and the unit was brought to full po'er w at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months . At 1710 hours0.0198 days 0.475 hours 0.00283 weeks 6.50655e-4 months load was-dropped to 800 MWe and the unit was placed on EGC.

At 0705 hours0.00816 days 0.196 hours 0.00117 weeks 2.682525e-4 months ,.on October'17, EGC was tripped and load was increased to full power.. On October 18, at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , load was dropped to 790 MWe and the. unit was placed on EGC. At 0937 hours0.0108 days 0.26 hours 0.00155 weeks 3.565285e-4 months EGC was tripped for a control rod: pattern adjustment. The unit was returned to EGC at 1008 hours0.0117 days 0.28 hours 0.00167 weeks 3.83544e-4 months . On October 19,lat 0142 hours0.00164 days 0.0394 hours 2.347884e-4 weeks 5.4031e-5 months , EGC was. tripped and load began a drop to 690 MWe-for Turbine surveillances. At 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months load began a normal increase to full power after a control rod maneuver at 600 MWe.

Eight hundred twenty-five MWe was reached on October 21 at 0615 hours0.00712 days 0.171 hours 0.00102 weeks 2.340075e-4 months .

On October 26, at 0120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months , the unit was placed on EGC. At 2250 hours0.026 days 0.625 hours 0.00372 weeks 8.56125e-4 months EGC was tripped and load began a decrease to 550 MWe for Turbine 4

surveillances and control rod pattern adjustments. On October 27, at

- :0125 hours, the 1A Recirculation Pump tripped. At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months load was increased to 550 MWe, and at 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months load began a normal increase to full power.- Eight hundred twenty MWe was reached on October 29 at 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months , and held steady for the remainder of October.

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B. Unit Two October 1-5 Unit Two began the month of October holding load near full power. On October 2, at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months , load began a drop to 700 MWe for Turbine surveillances. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months load began a normal increase to full power. Eight hundred twenty-six MWe was reached at 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months on October 3. At 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months load was dropped below 800 MWe and the unit was placed on EGC. At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months EGC was tripped and a normal shutdown commenced at 25 MWe/ hour due to a GSEP Unusual Event in progress.

(The 2B Core Spray and 2B RHR Room Coolers were inoperable.) The shut-down was terminated at 2213 hours0.0256 days 0.615 hours 0.00366 weeks 8.420465e-4 months . The unit was returned to EGC at 2220 hours0.0257 days 0.617 hours 0.00367 weeks 8.4471e-4 months .

On October 4, at 1325 hours0.0153 days 0.368 hours 0.00219 weeks 5.041625e-4 months , the unit was taken off of EGC for a switch of Condensate pumps and a reversal of Condenser flow. At 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months EGC operation resumed. On October 5, at 0025 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months , EGC was tripped for Turbine surveillances. The unit was returned to EGC at 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months .

October 6-23 On October 6, at 0748 hours0.00866 days 0.208 hours 0.00124 weeks 2.84614e-4 months , EGC was tripped and load maintained while maintenance was performed on the Condensate Demineralizers. The unit returned to EGC at 0915 hours0.0106 days 0.254 hours 0.00151 weeks 3.481575e-4 months . At 2125 hours0.0246 days 0.59 hours 0.00351 weeks 8.085625e-4 months EGC was tripped and maintained at 730 MWe while maintenance was performed on a Condensate Demineralizer. On October 7, at 0026 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months , the unit was returned to EGC. On October 8, at 1015 hours0.0117 days 0.282 hours 0.00168 weeks 3.862075e-4 months , EGC was tripped and load was increased to full power. At 2145 hours0.0248 days 0.596 hours 0.00355 weeks 8.161725e-4 months the unit was returned to EGC.

On October 9, at 0352 hours0.00407 days 0.0978 hours 5.820106e-4 weeks 1.33936e-4 months , EGC was tripped and load was increased to full power. The unit was returned to EGC on October 10 at 0008 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

AT 0720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months EGC was tripped and load was increased to full power.

The unit returned to EGC at 2347 hours0.0272 days 0.652 hours 0.00388 weeks 8.930335e-4 months .

EGC was tripped on October 15, at 0902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months , and load was increased to full power. At 1710 hours0.0198 days 0.475 hours 0.00283 weeks 6.50655e-4 months load was dropped to 800 MWe and the unit was returned to ECC.

At 2246 hours0.026 days 0.624 hours 0.00371 weeks 8.54603e-4 months the Reactor scrammed due to a valving error during an instrument maintenance surveillance test. The unit remained shutdown for a scheduled maintenance outage.

October 24 The Reactor went critical during a normal startup at 1640 hours0.019 days 0.456 hours 0.00271 weeks 6.2402e-4 months , on October 24. On October 25, at 0535 hours0.00619 days 0.149 hours 8.845899e-4 weeks 2.035675e-4 months , the main Generator was synchronized. Two hundred MWe was reached at 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months and held for control rod scram timing. At 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months a normal increase to full power resumed. Eight hundred twenty-three MWe was reached on October 28, at 0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months .

On October 29, at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months , load was decreased to 785 MWe for a Reactor Feedwater pump problem. At 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months load was increased to full power. On October 31, at 1237 hours0.0143 days 0.344 hours 0.00205 weeks 4.706785e-4 months , a control rod maneuver too,k place, and at 1308 hours0.0151 days 0.363 hours 0.00216 weeks 4.97694e-4 months load was picked up to 802 MWe where p load was held steady for the remainder of October.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Techncal Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

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

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

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

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UNIT 1 MAINTENANCE SLANARY CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION- PREVENT REPETITION Q44135 1-5746 1B RHR One of two belts One belt was not broken. Belts replaced, as was Room Cooler was broken, probably Room cooler still one pulley.

due to age and operable. When taken out cyclic fatigue. of service.for repairs, GSEP Unusual Event initiated.

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UNIT 2 - MAINTENANCE SLANARY '

CAUSE RESULTS & EFFECTS W.R. LER OF- ON ACT10N TAKEN.TO

NLABER NLABER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q41003 85-007 2-220-1 Main- Dirty valve inter . Excessive leaks caused - Cleaned valve internals

Steamline nals. Valve seat Local-Leak Rate Test and lapped valve seat.

i Drain Valve surface in poor- failure. . Valve will be replaced condition. during next outage.

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.Q42684 2-3999-515B Rusty and dirty Failed leak testing, The valve internals were RER Service valve internals but redundant valve cleaned, lapped the disc Water Vault caused the performed satisfactorily and seat, and replaced, Sump Pump plunger to become to provide flood ' cover gasket.

Check Valve frozen in the~ protection.

OPEN position.

Q45063 'B' RHR Through normal The 2B RHR pump and 2B Both fan belts and motor Room Cooler operation, the set Core Spray pump declared pulley replaced.' Pulley screws on the drive inoperable. A GSEP set screws reinstalled shaft pulley Unusual Event declared. using a locking compound.

loosened; the pulley then moved enough to throw the belts.

Q45064 2B Core Spray Through normal The 2B RHR pump and 2B Both fan belts and motor

Room Cooler operation, the set Core Spray pump delcared pulley replaced. Pulley screws on the drive inoperable. A GSEP set screws reinstalled l

shaft pulley Unusual Event declared. using a locking compound. ,

loosened; the

. pulley then moved

enough to throw the belts.

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IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications ~.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 85-17 10-15-85 RCIC Pump Discharge Valve 1-1301-48 Would Not Open UNIT TWO Licensee Event Report Number Date Title of Occurrence 85-21 10-15-85 Reactor Scram - Low Level During Testing 85-22 10-24-85 Relay Block Drop-Out -

Three Quarter Scram 0027H/0061Z

1 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 1

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i OPERATING DATA REPORT ;

DOCKET NO. 50-254 UNIT ONE DATENOVEMBER 4 1985 COMPLETED BYCAROL L KRONICH TELEPHONE 309/654-2241 OPERATING STATUS 0000 100185

1. Reporting period:2400 103185_ Gross hours in reporting period: 745

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

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

4. Reasons for restriction (if any):

This Month Yr,to Date Cumulative

5. Number of hours reactor was critical 745.0 7&47.0 95369.4 6.-Reactor reserve shutdown hours 0,0 0.0 3421.9

7. Hours generator on line 745.0 6989.4 92024.7 B, Unit reserve silutdown hours. 0.0 0.0 909.2

.9 . - G r o ss thermal energy generatad(MWH) 1729198, 16390657 192146047

.10 _ Gross electrical energy generated (MWH) 573813 5401729 62179180 11, Net clectrical energy generated (MWH) 548984 5171546 58127248-

-12. Reactor service-factor 100.0 96.6 80,7

13. Reactor availability factor 100.0_ 96.6 83.6

14. Unit service factor 100.0 95.8 77.9 t

i 15. U.11 t availability factor 100.0 95.8 78.7

16. Unit capacity factor (Using MDC) 95.8 92.2 64 0 i- 17.. Unit capacity factor (Using Des.MWe) 93.4 89.8 62.4 j, 18. Unit forced outage rate 0.0 4.2 5.9

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

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! 20. If shutdown at end of report period, estimated date of startup ___NA_____,___

l *The P.DC n y be lewar th:n 769 Ne during erisds of high cnbient temperetare he 2 90 the thereal perhrmance af the s;rcy to.41.

LNCFFIC!rl CC"1ANY WPERS ARE USED IN THIS REPORT

OPERATING DATA REPORT l

l DOCKET NO. 50-265 UNIT TWO D AT Et10 MEMBER 4 1985 COMPLETED BYCAROL L KRONICH l

TELEPHONE 309/654-2241 OPERATING STATUS 0000 100185

1. Reporting period:2400 103185 Gross hours in reporting period: 745 l

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

.(MWe-Net): 769* Design electrical rating (MWe-Net): 789

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

This Month Yr.to Date Cumulative

5. Nunber of hours reactor was critical 534.1 4973.9 89879.9

6. Reactor reserve shutdoQn hours 0.0 0.0 2985.8-

7. Hours generator on line 521.2 4889.1 86938.3

8. Unit reserve shutdown hours. 0.0 0.0 702.9

9. Gross thermal energy generated (MWH) __ 1215533 11346401 182865468

10. Gross electrical energy generated (MWH) 402294 3696178_ 58349589

11. Net.electrital energy generated (MWH) 384441_ 353409. 54852059

12. Reactor service factor 71.7 68.2 76.7

13. Reactor availability factor 71.7 6 8 u2 79.2 14, Unit service factor 70,0 67.0 74.2

15. Unit availability factar 7 0 . 0.. 67.0 74.8

16. Unit capacity f~ctor a (Using MDC) 67.1 63.0 60,9

'17. Unit cuancity factor (Usina Des.MWe) 65.4 61.4 59.3

.10. Unit corced outage rate _

3.3 4.1 8 . __2

-19 Shutdowns scheduled o 'v e r next 6 ncnths (Type.Date,and Duration of each)~:

20. If shutdown at and of report period,estinated date af startup _ _ _N_A_ _ _ _ _

IThe MC ny te Itwer NTi H9 Na hriq periods of hip cMient tesercture 6 to the thereci ;trhrmce of t.9e s;tcy ccncl.

WCFFICIAL CC9Wf C?EIS ME 'JSED IN THIS REPORT

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APPENDIX B AVERACE DAILY ~. UNIT POWER LEVEL

- DOCKET NO. 50-254' UNIT ONE DATENOVEMBER 4 1985 COMPLETED'BYCAROL L KRONICH TELEPHONE 309/654-2241 MONTH October 1985 DAYLAVERAGE' DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 734.7 17, 774.6

2. 736.7 18. 771.8 3, 722,3 19, 616.9

4. 746.3 20, 727.9 S '.1 717.8 21. 774.7

6. 581.2 22. 809.2

'7. 71542 23, 766.3' S. 790.0 24, 797.~8

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789.0 25. 782.6 7

10. 768.4 26, 737.8

11. 746'.7 27. 585.7 12; 773.0 20. 669.8 13, 730.0 29, 751.9 14 .- 747.3 30. 819.0

15 , 772iB 31, 747.4 16, 736.3 INSTRUCTIONS On this forn, list the average daily unit power level in Ne-Net for etch day in the reporting nanth Compute to the ;

h nearest while necawatt. . .

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These figures will be used to plot a graph for each repertina nonth. Nate that whtn Parinan dependcble tapetity is

" used for the net electratal rating of the Unit there may be ittasiens when the daily averoge power level excee.s the 1HZ line (or the restricted oswer level line),.In such teses,the average daily snit power evtput sheet shseld be footnoted to explain the ccparent ananaly k

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-265 UNIT TLD DATENOVEMBER 4 1985 COMPLETED BYCAROL L KRONICH TELEPHONE 309/654-2241 MONTH- Og,1ober 1985 DAY AVERAGE DAILY POWER-LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net > (MWe-Net)

1. 788.5 17. -0.8

2. 700.7 18. -7.5

3. 754.2 19. _ -9,7 4, 746,5 20, -11,8 5- 741.2 21. -11.3 6, 722.9 22. -10,8 7 .- 733,8 23. -10',7 8' ,

764,3 24. -12,3 9, 771,1 25. 180.6

- 1. 0 . 765.8 26. 644;i 11, 741,8 27 . - 773.8 12 .- 762.5 28. 798.8

13, 727,4 29. 784,1

.14, 744.3 30. 812.4

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794.0 31. -732,i

1. 6 . -12,4 INSTRUCTIONS On this fern, list the everage daily snit power level in MWe-Net for ecch day in the reporting nonth Compete to the necrest w5 le regcwatt, These figures will be used te plot a gresh f ar ecch reportina nnth. Note that when nominun depenhble capacity is used for the net electrical rating cf the vait,ttere ncy be iccasicr,s when tne daily overagt power level excee.s the 1023 line (er the restricted power level line).In ssch cases,the everage daily snit power output sheet should be footnoted to explain the caperent ancnoly

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M ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 50-254 August 1982 UNIT NAME Quad-Cities Unit One COMPLETED BY C. Kronich DATE November 7, 1985 REPORT HONTil OCTOBER 1985 TELEPil0NE 309-654-2241 s

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$ $ @ LICENSEE h@ @

w DURATION @ "g EVENT $0 o NO. DATE (IIOURS) o REPORT NO. CORRECTIVE ACTIONS / COMMENTS o

85-56 851001 S 0.0 B 5 HA TURBIN Reduced load to 700 MWe for Turbine surveillances 85-57 851005 S 0.0 H 5 RC CONROD Reduced load to 500 MWe for a control rod pattern adjustment 85-58 851019 S 0.0 B 5 HA TURBIN Reduced load to 690 MWe for Turbine surveillances 85-59 851026 F 0.0 H 5 CB PUMPXX Load reduced dua to 'A' Recirculation Pump trip APPROVED AUG 1 G 1982 (final) g g, g 3 g w ___

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ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 50-265 August 1982 UNIT NAME . Quad-Cities Unit Two COMPLETED BY C. Kronich DATE November 7, 1985 REPORT HONTil OCTOBER 1985 TELEPIIONE 309-654-2241 s

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$m l

m o o yw H

$ M LICENSEE m@ @

u w DURATION M g g EVENT $u o u

NO. DATE (IIOURS) o REPORT NO. CORRECTIVE ACTIONS / COMMENTS o

85-44 851002 S 0.0 B 5 HA TURBIN Reduced load to 700 MWe for Turbine surveillances 85-45 851003 F 0.0 D 5 ZZ ZZZZZZ Commenced normal shutdown due to GSEP Unusual Event. The 2B Core Spray and 2B RHR Room Coolers were inoperable (shut-down terminated 3.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) 85-46 851015 F 18.0 H 3 IA VALVEX Reactor scram due to a valving error on low water level surveillance (remained S 192.54 shutdown for a scheduled maintenance outage)

APPROVED AUG 1 G 1982 (final) yCUbH

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l l VI. UNIQUE REPORTING REQUIREMENTS l

i l The following items are included in this report based'on prior commitments to the commission.

A. Main Steam Relief Valve Operations 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.

Unit: Two Date: October 25, 1985 Valves Actuated No. & Type of Actuation 2-203-3A 1 Manual 2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual Plant Conditions: Reactor Pressure - 918 lbs Description of Events: Surveillance technical Specification 4.5.D.1.a B. Control Rod Drive Scram Timing Data for Units One and Two The basis for reporting this data to the Nuclear. Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with Reactor pressure greater than 800 PSIG.

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 ' CONTROL R00 DRIVES, FROM 1-1 TO 12-31-85 AVERAGE TIME IN SECONDS AT % MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION NUMBER S 20 50 90 Technical Specification 3.3.C.1 &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Time) 10-25-85 89 0.31 0.69 1.46 2.55 2.88 Unit 2 Sequence B Hot Scram Timing (F-12) (Includes H-8 After Replacement) i

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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 Rsvision 1 l

I QUAD-CITIES REFUELING March 1978 s ., ,

INFORMATION REQUEST 7 Cycle: 8

1. Unit: 41 Reload:

2. Scheduled date for next refueling shutdown: 1-5-86 3 Scheduled date for restart following refueling: 4-2-86 -

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

YES. A ROUTINE MAPLHGR AMENDMENT WILL BE SUBMITTED AS A PREPARATORY CHANGE TO ALLOW A 10 CFR 50.59 REVIEW OF THE RELOAD.

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

. Information:

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, m

J 7 The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1679

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

a. Licensed storage capacity for spent fuel: 3657

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 IIcensed capacity: 2003 C APPROVED APR 2.01978 C). ( . C). 53. Ft.

~ '

QTP 300-S32 e Revision 1 !

-. l QUAD-CITIES REFUELING March 1978

' l g ,, INFORMATION REQUEST ,

e

1. Unit: Q2 Reload: 7 Cycle: 8

2. Scheduled date for next refueling shutdown: 10-6-86

3. Scheduled date for restart following refueling: 12-22-86 *

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

NOT AS YET DETERMINED.

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

. Information:

SEPTEMBER 19, 1986, IF REQUIRED. i.

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.

. *N d

7 The number of fuel assemblies,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 837

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 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 C WPPROVED APR 2.01978 C3. c:. c). si. Ft.

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

w 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 HRSS -

High Radiation Sampling System IPCLRT -

Integrated Primary Containment Leak Rate Test IRM - Intermediate Range Monitor ISI -

Inservice Inspection LER -

Licensee Event Report LLRT -

Local Leak Rate Test LPCI -

Low Pressure Coolant Injection Mode of RHRS LPRM -

Local Power Range Monitor MAPLHGR -

Maximum Average Planar Linear Heat Generation Rate MCPR -

Minimum Critical Power Ratio MFLCPR -

Maximum Fraction Limiting Critical Power Ratio MPC -

Maximum Permissible Concentration MSIV -

Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI -

Primary Containment Isolation PCIOMR -

Precondition 1ng 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 l

.TBCCH -

Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC -

Technical Support Center 0027H/0061Z

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

I TKT-85-57 November 1, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Centlemen:

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 October, 1985.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR P,0WER STATION

/ ,> '

T. K. Tamlyn Services Superintendent ,

bb Enclosure t

l L_

ML20136F702

Text

SUMMARY

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