ML20076L555

Monthly Operating Repts for Aug 1983

ML20076L555
Person / Time
Site:	Quad Cities
Issue date:	09/08/1983
From:	Kalivianakis N, Misak A COMMONWEALTH EDISON CO., IOWA-ILLINOIS GAS & ELECTRIC
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-83-304, NUDOCS 8309160103
Download: ML20076L555 (24)

Text

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1983 CCHMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 8309160103 830908 PDR ADOCK 05000254 R

PDR

TABLE OF CONTENTS I,

Introduction II, Summary of Operating Experience U'it One A.

n 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 Expertnents 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 Reduct lons VI, Unique Reporting Requirements A,

Main Steam Relief Valve Operations B,

Control Rod Drive Scram Timing Data

VII, Refueling Information VIII, Glossary

I, INTRODUCTION Quad-Cities Nuclear Power Station is camposed of two Boiling Water Reactors, each with a MaxLaus 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 condenser 4

cooling method is a closed cycle spray canal, and 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 critica11tles for Units 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit I and March 10, 1973 for Unit 2.

This report was couplied by Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.

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II,

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One August 1-10:

Unit One began the month increasing load normally from a load drop due to low Service Water pressure caused by high Spray Canal tempera-ture. This load increase was terminated on August 2, at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, at 770 MWe due to the IDI Feedwater Heater being out of service.

On August 4, at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />, the unit dropped load to minimum Recirculation pump speed (430 MWe) due to low Service Water pressure.

Between 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> on August 5 and 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> on August 6, the unit operated an open cycle cooling to reduce the Suppression Chamber temperature and increase Service Water pressure.

This load was maintained until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on August 10, when a nornal load increase was initiated.

August 11-15:

Unit one continued increasing load until 1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br /> on August 12, when the unit dropped load from 720 MWe to 680 MWe in order to maintain Main Condenser Vacuum. The apparent cause of the vacuum leak was discovered and remedied, and a normal load increase was initiated at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br /> on August 12.

At 0005 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, on August 13, the Main Condenser Vacuum leak reappeared, and the unit dropped load to 395 MWe.

The unit maintained this load until 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> on August 14, when the Generator was taken off line, and the Reactor mode switch was placed in HOT STAND-BY for identification and repair of the vacuum leak.

August 16-21: Unit One continued operating in Hot Stand-by until 1722 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.55221e-4 months <br /> on August 16 when the unit was placed on line. The unit inc reased load to 300 MWe and maintained that load until 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on August 18 when the unit dropped load to return an Of f-Gas Recombiner to service following repair of the Main Condenser Vacuum leak at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br />. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, the unit began increasing load normally to 400 MWe. The unit maintained this load, as requested by the Load Dispatcher, uniti 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> on August 19 when the unit began a normal load increase. Also, at 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br />, the unit began operating on open cycle cooling to reduce the Suppression Chamber temperature and increase Service Water pressure.

The load increase continued until 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on August 20, when the unit held load at 670 MWe as requested by the Load Dispatcher. At 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />, open cycle cooling was terminated, and at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, the unit dropped load to 400 MWe due to low Service Water pressure.

August 22-31: At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, on August 22, Unit One began increasing load normally from 400 MWe.

At 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br />, open cycle cooling commenced and continued until 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br />.

At 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br />, the load increase stopped with the unit at 675 MWe.

This load was maintained until 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br /> when the unit dropped load to 500 MWe.

The unit maintained a load of 500 MWe until 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on August 25 when the unit increased load to 600 MWe.

At 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, on August 29, the unit began increasing load normally from 600 MWe

Unit One (Continued) to full power. The unit operated on open cycle cooling from 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> to 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, the normal load increase was terminated, and the unit dropped load from 750 MWe to 600 MWe.

At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, on August 31, the unit dropped load to 377 MWe for MSIV testing.

Following the testing, at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />, a normal load increase to 600 MWe was initiated. The unit achieved a load of 600 MWe at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> and maintained that load for the remainder of the month.

B.

Unit Two Unit Two operated throughout the month derated due to End of Cycle fuel depletion.

August 1-9: At 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />, on August 1, the unit increased load from 325 MWe to 425 MWe as requested by the Load Dispatcher. The unit maintained this load until 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> on August 3 when the unit dropped load to 295 MWe as requested by the Load Dispatcher. At 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, on August 4, the unit increased load to 430 MWe, and then at 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />, the unit increased load to 480 MWe, both as requested by the Load Dispatcher.

At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, on August 5, the unit dropped load to 300 MWe and maintained this load from 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> to 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, and then increased load to 480 MWe.

Open cycle cooling was commenced at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> and continued until 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on August 6.

During this time, at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br />, on August 5, the unit dropped load to 400 MWe to take the 2A Circulating Water pump out of service due to high differential pressure across the Traveling Screen. The Traveling Screen was cleaned, the 2A Circulating Water pump was retur.'ed to service, and at 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br /> the unit increased load to 490 MWe.

August 10-16: At 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />, on August 10, the unit dropped load to 300 MWe as requested by the Load Dispatcher, and at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />, the unit increased load to 440 MWe.

At 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br />, on August 12, the unit dropped load to 285 MWe as requested by the Load Dispatcher, and at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br />, the unit increased load to 440 MWe.

At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the unit dropped load to 270 MWe as requested by the Load Dispatcher. At 1040 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.9572e-4 months <br />, on August 14, the unit increased load to 500 MWe.

At 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br />, on August 16, the unit dropped load 50 MWe/ hour from 450 MWe due to high Suppression Chamber temperature. This load drop was terminated at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />, and then the unit increased load to 450 MWe.

August 17-24: Unit Two maintained full load throughout this period.

Open cycle cooling was utilized twice, from 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> on August 19 to 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br /> on August 20, and from 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> to 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> on August 22.

4.

Unit TWo (Continued)

August 25-31: At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, on August 25, the unit dropped load to 325 MWe to offset the Unit One load increase and maintain a constant Station load. At 0915 hour0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />s-, on August 29, the unit increased load to 455 MWe. The unit operated on open cycle cooling from 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br /> to 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, the unit dropped load to 350 MWe as requested by the Load Dispatcher and maintained this load during the remainder of the month.

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l III, PLANT AR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELA.

'AINTENANCE A.

Amendments to Facility License or Technical Specification 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 Unit One and Unit Two during the reporting period.

This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

a ONE UNIT MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q26302 83-21/0lT Reactor Vessel A pinhole leak The leak was not large During a short outage, Constant Head possibly caused by enough to affect plant the weld was ground out, Vent slag entrapment operation. Drywell NDE inspected,'re-within the weld.

leakage is monitored.

welded, and NDE inspected again.

Q26934 83-26/03L Unit 1 Steam-The cauge was not The other gauges were The gauge was re-line Flow zeroed, as a accu ra te.

calibrated and zerced.

Gauge 1-261-result of 2J instrument drift.

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q26209 Suppression Faulty breaker.

The breaker tripped The breaker was A

Chamber to RHR when the valve replaced.

Pump Circuit reached full closed. The Breaker 2-1001-breaker was reset & the 7C valve was operated successfully, i

027398 83-il/03L Suppression Too high of a The valve tripped when The breaker and over-Chamber setting on the the valve was given an load were replaced; Cooling & Test close torque open signal. When the all cubicle 2-1001-36B switch.

operator started the connections were checked (Valve) valve manually, it and the torque switch worked properly, reset.

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IV.

LICENSEE EVENT REPORTS The f ollowing 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 There were no Licensee Event Reports for Unit One for the reporting period.

UNIT TWO 83-12/03L 8-16-83 Torus Temperature Greater Than 95 F J

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V, DATA TABUIATIONS The f ollowing data tabulations are presented in this report:

A, Operating Data Report B,

Average Daily Unit Power Level C,

Unit Shutdowns and Power Reductions

OPER ATING DATA REPORT DOCKET NO.

50-254 UNIT ONE I

DATE09-08-83 COMPLETED BYAlex Hisok 4

TELEPHONE 309-654-224ix194 OPERATING STATUS 0600 080183 1.

Reporting period:2400 083183 Gross hours in reporting period:

744 2.

Currently authorized power level (MWt): 2511 Max. Depend copocity (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 744.0 5623.6 80794.8 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 692.0 5531.5 77618.2 8.

Unit reserve shutdown hours.

0.0 0.0 909.2 9.

Gross thernal energy generated (MWH) 1167091 12630033 158843024

10. Gross electrical energy generated (MWH) 362493 404160q 51213490 337974 3848481 47677389 ii. Het electrical energy generated (MWH)

12. Reactor service factor 100.0 96.4 81.5

13. Reactor avo11obility factor 100.0 96.4 85.0

14. Unit service factor 93.0 94.9 78.3

15. Unit avoilobility factor 93.0 94.9 79.2

16. Unit capacity factor (Using HDC) 58.8 85.8 62.5

17. Unit capacity factor (Using Des.MWe) 57.3 83.6 61.0

10. Unit forced outage rate 7.0 2.2 6.4

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

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

• The HDC nay be lover than 769 MWe dsting periods of high onblent tenperatere due to the thernal perfernance of the sprey canal.

$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATE09-08-83 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 OPERATING STATUS 0000 080183 1.

Reporting period 2400 083183 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 any):

lhis Month Yr.to Date Cunulative 5.

Number of hours reactor was critical 744.0 5567.0 77830.4 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 744.0 5537.7 75125.8

8. Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thernal energy generated (MWH) 1013860 10692006 155283500

10. Gross electrical energy generated (MWH) 305481 3369805 49407340

11. Het electrical energy generated (HWH) 276649 3138655 46322222

12. Reac+or service factor 100.0 95.5 79.3

13. Reactor avo11obility factor 100.0 95.5 82.3

14. Unit service factor 100.0.

95.0 76.5

15. Unit avo11obility factor 100.0_

95.0.

77.2

16. Unit capacity factor (Using MDC) 48.7 70,0 61.3

17. Unit capacity factor (Using Des.MWe) 47.4 68.3 59.8

18. linit forced outage rate 0. 0.

1.9 8.6

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

20. If shutdown at end of report period,estinated date o f s t or t u p __I_2_- 18_-81____

lihe 1100 not be lever then 769 leie dering perleds of high onbient tenperatere due to the thernal perfernonce of the sprey canal.

$U110FFICIAL C0lFANY MUMERS ARE USD IN THIS REPORT l

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATE09-08-83 COMPLETED BYAlex Misak TELEPHONE 309-654-2241xi94 HONTH Aunust 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(MWe-Net) 1.

596.8 17.

266.3 2.

697.1 18, 246.6 3.

714.0 19.

479.1 4.

567.8 20, 545.0 5.

425.0 21, 383.0 6.

416.2 22.

494.4 7.

409.3 23, 453.9 8.

414.7 24.

476.1 9.

410.8 25, 515.8 10, 430.4 26.

549.2 ii.

524.7 27.

559.4 12, 633.5 28, 548.0 13, 375.9 29.

634.8 14, 159.8 30, 548,1 15.

-17.4 31, 505.4 16, 45.0 INSTRUCTIONS On this forn list the overage daily enit power level in lWe-Het for each day in the reporting nonth Conpete to the treseewhole negew,ett.

These figeres will be esed to plot a graph for each reporting nenth. Note that when narinen dependable capacite is esed for the net electrical rating of the snit,there ney be occasions when the daily overage power level exceeds the illI line (or the restricted power level line).In sech cases,the overage daily enit power outpet sheet sheeld be feetnoted to esplein the opperent enenely

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATE09-08-83 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 MONTH Auaust 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

357.6 17.

403.4 2.

378.3 18, 394.3 3.

272.i 19.

405.2

-4.

366.3 20, 395.3

~5.

414.4 21, 393.7 6.

423.5 22, 396.4 7.

409.0 23, 391.4 8.

421.3 24, 389.5 9.

413.2 25, 339.8 10.

401.4 26.

317.6 ii.

414.3 27, 315.6 12, 389.9 28.

316.3 13.

263.8 29.

372.9 14, 376.5 30, 319.4 15.

413.0 31.

329.5 16.

403.7 INSTRUCTIONS On this forn list the everage daily eqit power level in Mile-Net for each day in the reporting nonth.Conpete to the Sesseuhele negou,stt.

These figures Will be used to plot a graph for each reporting nonth. Note that when notinen dependoble copatity is esed for the net electrical rating eT the snit there ney be occasions when the daily overage power level exceeds the 100Illae (or the restricted power level line),.In soch cases,the average daily snit power output sheet should be festnoted to esplein the apperent enenely

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n ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWEK REDUCTIONS Revision 6 DOCKET NO. _050-2q4 August 1982 UNIT NAME Ouad-Cities Unit One COMPl.ETED BY _ Ale d 'uak DATE Seotember 2.

1983 REPORT HONTil AUGUSI__1383 TEl.EPil0NE 309-6S4-2241 8

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EVENT o"

NO.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS o

83-51 830804 S

0.0 H

5 WA ZZZZZZ Reduced load due to Spray Canal tempe ra t u re 83-52 830813 F

0.0 A

5 HC llTEXCH Reduced load due to Main Condenser Vacuum leak 83-53 830814 F

52.0 B

1 IIC HTEXCH Unit placed in Hot Standby to locate and repai r Main Condenser Vacuum leak 83-54 830818 5

0.0 11 5

MB RECOMB Reduced load to put Off-Gas Recombiner on line 83-55 830820 S

0.0 11 5

WA ZZZZZZ Reduced load due to high Spray Canal temperature 83-56 830822 S

0.0 H

5 WA iZZZZZ Reduced load due to high Spray Canal tempe ra t u re 83-57 830829 5

0.0 H

5 WA ZZZZZZ Reduced load due to high Spray Canal tempe ra t u re 83-58 830831 S

0.0 B

5 CD VALVEX Reduced load to perform Main Steam isolation Valve Timing APPROyED AUG 1 G 1982 (final) ygg3g

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I"""1 ID/5A APPENDIX D QTP 300-S13 UNIT SilHTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-265 Augur.t 1982 UNIT NAME Quad-Cities Unit Two Cot 1PI.ETED BY Alex tQiak DATE Septembe r 2, 1983 REPORT HONTil AUGUST 1983 TEI.EPil0flE 309-654-2241 N

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DATE (IlOURS)

REPORT NO.

CORRECTIV6 ACTIONS /CotitlENTS o

A 83-56 830803 S

0.0 H

5 WA ZZZZZZ Reduced load due to high Spray Canal temperature 83-57 830805 5

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-58 830805 F

0.0 B

5 HF FILTER Reduced load due to high differential

. pressure across 2C Circulating Water Pump Traveling Screen 83-59 830810 5

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-60 830812 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-61 830813 5

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-62 830816 S

0.0 D

5 SA VESSEL Reduced load to cool Suppression Chamber due to high Spray Canal temperature 3

APPROVED l

AUG 1 G 1982

-l-(final)

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M M

M E!M M

M M

M M

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ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. _D50-26c; August 1982 UNIT NAME Ouad-Cities Unit Two COMPl.ETED BY Alex Misak DATE September 2.

1983 REPORT t10NTil AUGUST 198J TEl.EPIIONE 309-654-2241 5

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DURATION d

EVENT u

"g o

O NO.

DATE (Il0URS)

REPORT NO.

CORRECTIVE ACTIONS /CotitlENTS oa 83-63 830825 5

0.0 F

5 EA ZZZZZZ Reduced load to offset Unit One increase as requested by Load Dispatcher 83-64 830829 5

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 4

APPROVED AUG 1 G 1982 (final) ygg3g

VI, UNIQUE REPORTING RF1)UIREMENTS The following items are included in this report based on prior cemitments to the camission:

A.

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

B.

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

i e

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.

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QTP 300-532 Revision 1 QUAD-CITIES REFUELING March 1976

(

INFORMATION REQUEST r-a 1.

Unit:

Q1 Reload:

6 Cycle:

7 2.

Scheduled date for next refueling shutdown:

9-6-82

[

3 Scheduled date for restart following refueling:

12-18-82 F

4.

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

Yes 5

Scheduled date(s) for submitting proposed licensing action and supporting In forma tion:

8-19-82: Tech. Spec. changes submitted to the NRC.

6.

Important IIcensing 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:

a) All TxT fuel assemblies vill be removed from the core.

b) MAPLHGR curves for fuel types in the core are being extended to h0,000 MWD /ST.

c) MCPR limits vill be determined by GE's ODYN computer code.

f',

d) The vessel pressure safety limit is being modified to accommodate the s

potential for higher reactor pressures as calculated by ODYN.

7 The number of fuel assemblies.

a.

Number of assemblies la core:

724 b.

Number of assemblies in spent fuel pool:

800 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 IIcensed storage:

O S.

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

[

XPPROVED APR 2.01978

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Q.C.O.S.R.

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QTP 300-S32 o

i Rsvision 1 I

QUAD-CITIES REFUELING Harch 1978

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INFORMATION REQUEST lL, o

1.

Unit:

Q2 Reload:

6 Cycle:

7 2.

Scheduled date for next refueling shutdown:

9-5-83 3

Scheduled date for restart following refueling:

11-12-83 4.

Will refueling or resumption of operation thereaf ter require a technical 5

specification change or other license amendment:

No, however, a c$ange to the Technical Specifications is being submitted

?

(see below).

5 Scheduled date(s) for submitting proposed IIcensing action and supporting 2

Information:

s June 14, 1983 (Scheduled)

R 6.

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

' different fuel design or supplier, unreviewed design or performance analysis 3

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

a)

All new fuel assemblies will be of barrier design; MAPLHGR curves will be g

re-labeled to include the barrier designation.

b) The use of I.mproved assumptions in the load reject without bypass analysis resulted in a much improved MCPR operating limit.

Technical Specifications are being changed to provide this additional operating margin.

l f

7 The number of fuel assemblies.

[

a.

Number of assemblies in core:

724 L

b.

Number of assemblies in spent fuel pool:

204 l

l 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 i

in number of fuel assemblies:

1 a.

Licensed storage capacity for spent fuel:

3897 0

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 4PPROVED L

._ APR 2 01978 Q.C.O.S.R.

)

VIII, GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

Atmospheric Containnent Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor Anticipated Transient Without Scram ATWS BWR Bolling Water Reactor CBD Control Rod Drive EHC Electro-Hydraulic Control System EOF Bnergency Operations Facility GS EP Generating Stations Emergency Plan High-Ef ficiency Partleulate Filter HEPA HPCI High Pressure Coolant Injection System High Radiation Sampling System HRSS IPCLRT Integrated Primary Containment Leak Rate Test Intennediate Range Monitor IRM Inservice Inspection ISI LER Licensee Event Report LIRT Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI LPRM Local Power Range Monitor Maximum Average Planar Linear Heat Generation Rate MAPLHGR MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Pouer Ratio MPC Maximum Permissible Concentration Main Steam Isolation Valve MSIV National Institute for Occupational Safety and Health NIOSH Primary Containment Isolation PCI Precondition 1ng Interim Operating Management Recommendations PCIOMR RBCCW Reactor Building Closed Cooling Water System Rod Block Monitor RBM RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RRRS Reactor Protection System RPS Rod Worth Minimizer RRM SBGTS Standby Cas Treatment System SBLC Standby Liquid Control Shutdown Cooling Mode of RRRS SDC SDV Scram Discharge Volume SRM Source kange Monitor Turbine Building Closed Cooling Water System TBCCW Traversing Incore Probe TIP TSC Technical Support Center

l

1. h Commonwealth Edison

) 22710 206 Avenue North Outd Citiss Nucl:ar Powsr St: tion O

g Cordova, Illinois 61242 N

Telephone 309/654-2241 NJK-83-304 August 31, 1983 Director, Of fice of Inspection & Enforcanent United States Nuclear Regulatory Canmission Washington, D, C, 205S5 Attention:

Document Control Desk Gentlemen:

Enclosed for your infonnation is the Monthly Perfonnance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of August 1983.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION

/ 4?f l

N J, Kallvianakis Station Superintendent bb Enclosu re

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