ML20062J486

Monthly Operating Repts for Jul 1982

ML20062J486
Person / Time
Site:	Quad Cities
Issue date:	08/03/1982
From:	Buss R, Weinfurter E COMMONWEALTH EDISON CO.
To:
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ML20062J463	List: ML20062J460 ML20062J486
References
NUDOCS 8208160381
Download: ML20062J486 (27)

Text

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QUAD-CITIES NUCLEAR POWER STATION I

i UNITS 1 AND 2 s

MONTHLY PERFURMANCE REPORT JULY 1982 i

CGtMONWEALTH EDISON COMPANY

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AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY j

NRC DOCKET NOS. 50-25 2 AND 50-265 -

LICENSE NOS. DPR-29 AND DPR-30 r

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P208160301 820802 t

PDR ADOCK 05000254 t

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TABLE OF CONTENTS 1.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant of. 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 Experimente 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

I.

INTRODUCTION Quad-Cities Nuclear Power Station is camposed 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 Compa ny.

The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The condenser 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 criticalities 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 1 and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Erich Weinfurter, telephone number 309-654-2241, extensions 127 and 192.

l I

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One July 1-15: The unit began the month holding load at about 515 MWe.

The unit was derated due to end of cycle fuel depletion /coastdown.

On ten occasions the Load Dispatcher requested the unit load be reduced due to low system demand between Midnight and approximately 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />.

Otherwise, the unit maintained an average load of approximately 495

MWe, July 16: On July 16, at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />, the unit dropped load to take the l A Recirculation pump Motor-Generator Set out of service to repair an oil leak. At 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br />, the Recirculation pump was restarted and the ur.i t began increasing load at 50 MWe/ hour to 476 MWe.

July 17-31: On ten occasions, from Midnight to approximately 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, Unit One was requested to reduce load due to low system demand.

The unit at all other times maintained an average load of about 470 MWe.

B.

Unit Two July 1-3: The unit was derated due to 2A Recirculation pump Motor-Generator Set high vibration. The unit started the month decreasing load at 100 MWe/ hour to 400 MWe to shut off the 2C Circulating Water pump.

At 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, the unit began increasing load nornelly at 50 MWe/ hour to 690 MWe.

On July 3, at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, the unit dropped load 50 MWe at 100 MWe/ hour due to low Condenser vacuum.

July 4-6: On July 4, at 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br />, the unit reduced load to 550 MWe at 200 MWe/ hour due to low system demand. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> load was increasing at 25 MWe/ hour to 750 MWe by 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.

At 2I00 hours, load was decreasing to 447 MWe to once again remove the 2C Circulating Water pump from service. On July 5, load was increased to 643 MWe by 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />.

At 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />, load was decreased to 600 MWe due to low Condenser vacuum.

On July 6, the Circulating Water pump was returned to service and at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, unit load was increased.

July 7-10: At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, on July 7, load was reduced at 50 MWe/ hour to 590 MWe at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> to take the 2C Circulating Water pump off line.

The pump was returned to service and load increased normally to 681 MWe.

On July 8, uni t load was twice reduced at the request of the Load Dispatcher due to low system demand.

At 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br />, load began increasing normally to 740 MWe by 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />.

II.

SUMMARY

OF OPERATING EXPERIENCE (Continued)

B.

Unit Two (continued)

July 11-19: At 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, on July 11, the unit dropped load at 100 MWe/ hour to 700 MWe to perform weekly Turbine tests. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, load was increased 5 MWe/ hour to 746 MWe at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />.

On four occasions the unit reduced load due to low system demand, returning normally to 740 MWe average load.

On July 17, at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, the unit reduced load 50 MWe and maintained an average load of 690 MWe through July 19 due to low Condenser vacuum.

July 20-23: On July 20, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, load was decreasing at 200 MWe/ hour for one-hal f hour due to low system demand. After two hours the unit load was increased to 720 MWe by 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.

At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, load was reduced 50 MWe to 664 MWe.

On July 22, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, load was increased to 750 MWe.

July 24-31: On July 24 load was reduced in two steps to 450 MWe at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> due to low system demand.

Af ter one hour, load increased normally to 685 MWe by 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />. At 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />, load was decreased to 650 MWe to lower the cooling water temperature. On July 25 at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, load was decreased another 50 MWe to lower the inlet water temperature.

On July 28 load was reduced 200 MWe/ hour for I hour due to low system demand at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />. At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, load was increased to 650 MWe and increased again to 685 MWe July 29 at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />.

III.

PIANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFEN RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifica-tions There were no Amendments to 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 Equipnent The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period..The headings Indicated in this summary include: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

UNIT 0:4E MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q16141 RHR Pamp itinimal The valve permissive The bypass valve would The pressure switches-Flow Bypass Valve pressure switches were not open when RHR System were recalibrated.

fi0-1-1001-10A out of calibration.

flow dropped below 1200 gpm.

Qi9517 Reactor Mode Several of the A 1/2 scram was The contacts were Switch System switch contacts were received in Startup inspected for loose 590

dirty, itode f rom closing the connections and itS I Vs.

cleaned.

Q20085 82-13/03L Unit 1 Diesel The pump was Flow could not be The pump rotating Generator determined to be established in the assembly was Cooling Water air bound.

The system.

replaced.

Pump 1-3903 wear rings were also found to be worn.

Q20109 Unit 1 Diesel The valve disc was The check valve was The check valve was Generator not seating leaking through.

replaced.

Cooling Water properly.

Pump Check Valve 1-3999-C6 Q20032 Fuel Pool The bug source on The Reactor Bldg The bug source on Monitor Channel GM tube was found Fuel Pool Monitor the GM tube of "A"

(ARM 1743A) broken.

Channel "A" read the senser con-System 1001 downscale.

verter was replaced.

e e

UNIT ON5 MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Qll338 HPCI Steam The. coil had The valve would not A new solenoid Supply A0 Drain shorted out.

ope ra t e.

HPCI was coll was installed.

Valve 1-2301-31 still operable.

Q14378 I Rtt 15 The preamp con-IRM 15 was spiking The preamp connector nector was dirty, high.

was cleaned.

Q19403 1-1301-50 RCIC The valve would The valve leaks by; Disassembled valve Check Valve not close RCIC was operable and shimmed actuator completely.

at all times.

rod.

Q19793 82-II/0lT

1. 4 Turbine The connector to The valve failed to The test switch was Con t rol Valve the fast acting fast close during replaced and hand-System 5600 solenoid valve was last 10% of travel wired the. coil for f a'u l t y.

during test.

fast acting solenoid valve.

Q15642 IRM 15 The pre-amplifier IRM 15 was spiking The pre-amp was 1-750-7B was not working upscale and down-repaired and tested.

properly.

scale.

Q17851 LPRM 24-57C The cable connector The LPRM read A new LPRM cable was faulty.

downscale.

connector was installed.

Q18020 1-1001-43A The auxiliary The valve would not The auxiliary contacts contacts were close from the in the closing circuit worn.

Control Room.

l.PC I were replaced.

was fully operable.

UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION l

Q18739 Torus Temperature The thermocouple There was faulty The defective thermo-T/C 1-1630A was found broken.

temperature couple was replaced.

indication for that channel.

Q20473 82-14/03L "B" Train SBGT The auxiliary The "B" SBGT train New auxiliary System I-7500 contacts in the would not auto-contacts were in-opening circuit of start curing testing.

stalled and the test the inlet damper The "A" train was was performed were worn.

ope rab l e.

satisfactorily.

Q20494 82-16/03L HPCI Motor The 2A amplifier The MGU will not stay The 2A amp board in Gear Unit board in the flow on the high speed stop.

the speed control 1-2300 controller was circuit was replaced.

faulty.

l Q19901 HPCI Gland Steam The circu't breaker The HPCI exhauster The circuit breaker Exhauster was defec ive.

would not operate.

was replaced.

HPCI System was still operable.

Q16140 RHR Pump M in The pressure Bypass valve would The pressure switches Flow Valve MO-switches were out of not open when the were calibrated and 1-1001-18B calibration.

RHR flow was less functionally tested.

than 1200 gpm.

Q20078 HPCI Inlet Steam The steam trap The trap was blowing The trap gasket was Trap 1-2301-1 gasket was worn.

steam into the room, replaced.

Q16145 1A Core Spray The torque switch The breaker tripped The torque switch Discharge Valve was worn, when the valve was was replaced.

1-1402-24A closing.

UNIT OME MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q19859 RHR Mininal Flow The breaker auxiliary The valve would not The auxiliary contacts Valve M0-1-1001-contacts were worn.

readily open.

were replaced.

18A Q19860 RHR Mininal Flow The breaker auxiliary The valve would not The auxiliary contacts Valve M0-1-1001-contacts were worn.

open.

were replaced.

18B l

1 f

UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERA!!0N PREVENT REPETITION Q16600 2-1001-60 A bad lug in the The local closing push-The lug inside the MCC was found.

button would not MCC was replaced.

the M0 valve.

Q18356 2B SJAE Suction Stand out of line.

Did not go closed on Adjusted stand under Valve 2-5401-B isolation signal.

air cylinder valve.

Q19487 RHR Suction Valve The torque switch The breaker keeps The torque switch was 2-1001-78 was worn.

tripping when valve replaced.

gets closed.

Q19956 RHR Heat Ex-The overload heater The breaker tripped New overload heaters changer Bypass was not operating while trying to re-were installed.

2-1001-16B p rope r l y.

open for operability test.

Q20128 82-09/03L Electromatic The valve disc The valve would not The electromatic relief Relief Valve rings were worn into open.

valve was replaced.

2-203-3C the guide.

Q20195 82-10/03L HPCI Pump The actuating arm of The valve will not open The tor que switch arm Discharge Valve the torque switch but goes to dual was repaired.

M0-2301-8 was broken.

Indication stops.

Q20167 CRD 42-23 The accumulator Water leaks to the The accumulator was piston seals were nitrogen side of the replaced.

worn.

accumulator.

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 82-14/03L 07-08-82 1/2 B Standby Gas Train Failure to Start in 7

Primary F

82-15/03L 07-05-82 1/2 A Diesel Fire Pump inoperable More Than 7 Days i

82-16/03L 07-11-82 HPCI Flow Controller f

Failure 4

l 82-17/03L 07-13-82 Core Spray Valve 1402-25B - Won't Open 82-21/03L 07-19-82 Reactor Pressure Set-point Drift i

82-18/03L 06-25-82 Diesel Generator Cooling Water Pump inoperable 82-19/03L 07-13-82 Relief Valve Setpoint Drift 82-20/03L 07-28-82 "A" SBGT Less Than 140F Difference in Temperature Across Heater UNIT TWO 82-10/03L 06-24-82

'HPCI Valve-2-2301-8-Falled to Open 82-ll/01T 07-15-82 LPCI 29B Valve Would Not Open 82-12/03L 07-14-82 Reactor Relief Valve Set-point Orift F

V.

DATA TABUIATIONS 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 l

OPERATING DATA REPORT DOCKET NO.

50-254 Ui41T ONE DATEAuuust 03 1982 COMPLETED BYErich Weinfurter TELEPHONE 199-654-2241xi92 OPERATING STATUS 0000.070182.-

i. Reporting period 2400 073182 Gross hours in reporting periods' 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):

This Month Yr.to Date Cumulative

5. Number of hours-reactor was critical.

744.0.

4968.4.

74067.5.

6.

Reactor reserve shutdown hours 0.0 0.0 3421.9

~

7. Hours generator on line 744.0 4912.9 71044.4 l

-8.. Unit reserve shutdown hours.

0.0 0.0.

909.2_._.

9.

Gross thernal energy generated (MWH) 1114812 9891413 144949772

10. Gross electrical energy generated (MWH) 340812 3198830 46727763 I -

11.-Net electrical energy. generated (MWH).

303155 2931228 43515312_

12. Reactor service factor 100.0 97.7 82.6

13. Reactor avullability factor 100.0 97.7 86.5

14. Unit service factor.

100.0 96.6_ -

79.3.._

L5. Unit availability factor 100.0 96.6 80.3

16. Unit capacity factor (Using MDC) 53.0 74.9 63.i L7. Unit-capacity factor--(Using Des.MWe) 51.6~

73.0 61.5_

18. Unit forced outage rate 0.0 1.8 6.8

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

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

____NA 8The litt ney'be lower then 7H leie dering periods of high edlent tenperatore det to the thernal perfernence of the sprey canal.

m OPER ATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEAuoust 03 iY82 COMPLETED BYErich Weinfurter TELEPHONE 30?-654-2241x192

/

OPERATING STATUS 0000 070182

1. Reporting period 2400 073182 Gross hours in reporting period 744

2. Currently authorized power level (MWt) 2511 Mux.. Depend copccity -_

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

3. Power level to.which. restricted (if uny)(MWe-Net), NA 4.

Reasons for rettriction (if any):

8 4

This Month Yr.to Date.

Cumulative 5.

Number of hours reactor-was. critical 744.0 3927.0- -

68778.8-_

6. Reactor reserve shutdown hours 0.0 0.0 2981tg-

. _ s _..

7. Hours generator on line 744.0 3885.9 66127.1 8.. Unit reserve shutdown. hours.-

0. 0-0.0 702.9_

V. Gross thermal energy generated (MWH) 1622246 8937888 136824971 2857177 43563417.

10. Gross electrical energy generated (MWH) 501288

- - 11. Het electrical. energy generated (MWH) 478004 2719924.

40844508 L2. Reactor service factor 100.0 77.2 77.5

13. Reactor ovallobility factor 100.0 77.2.

80.9f

--- 14. Unit-service factor 100.0-76.4 _

74. 6 t_ '

L5. Unit avo11ob111ty factor 160 0 76.4 75.3

16. Unit capacity factor (Using MDC)

.83;5 69.5 59.9.

17.-Unit copocity-factor--(Using-Des.MWe) 81.4 67.8 58.4.

18. Unit forced outage rate 0.0 22.8 9.4

19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Durat iori o f each ) :

20. If. shutdown.at.end of.. report period, estimated date of stettup __;}A

• The IWC not be leur the M9 Ilie dering perleds of high sabient temperatore dee to the thernal perfernence of tha spray cuel.

.t

~

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET No.

50-254 UNIT ONE

-DATEAmtvst 03 1982,,_

COMPLETED' BYErich Weinfurter TELEPtt0NE309-654-2241xi92 HONTH

-Jyly.1982 LAY AVERAGE DAILY POWER LEVEL.

DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(NWe-Net)-

L.

448.2 17.

389,3 2.

439.9 18.

421.5 3.

451,2

. 19, 415.1 3

4.

4R}'?

20, 381.6

5. _z '

1. 21.8 21.

411.3 22.

414.0 6.

436.5 7.

446.0

23..

383.2 7

D.

401 2 24.

300.5 9.

454.3 25.

371.9 10.

429.0 26.

401.7 L i '. __,

434.6 27.

397.1 L'2.

415.9

- 28, 367.1 13.

386.6 2 9.,,,

369.5 L4.

419,5 30, 362.3 15.

402.0 31.

371.6 16, 383.4 INSTRUCTIONS de shis forn, list the enregt delly enit power leul in llut-Net for toch det in the repwting nenth.Conpete to the neertst uhele negouett.

d to plot a graph for each reporting math. Wete that when notinen dependeble capetity is Thew figeres u1116e efcel rating of th' omit,In sKh cases the cieregt delly enit poutr esed for the net electr e

there not be ucesiens when the delly enrege peser leetl exceess the 1HZ line (or the restricted power itH line).

3 festeeted to suplein the opperent onens y

/

_ m..__

I APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 DATEAuaust 03 1982 COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241xi92

- HONTH Julv 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)-

-(HWe-Net)-

1.

598.8 17.

684.2 2.

658.2 18.

654.9 3.

614.6

- 19,

657.5 4.

571.7 20.

652.2 5.

524.0 21.

626.5 6.

579.5

22. -

667.0 7.

640.0 23.

702.3 B.

667.6 24.

614.4 9.-

714.0

. 25. -

586.0 10.

686.5 26, 570.7

~'

~'

11, 689.8 27.

575.7 L2, 703.1 28.

560.4 13.

683.0 29.

640.5 i

14.

6'90.0 3 0 '.

645.5 15, 704.7 31..

657.9 16, 695.8 INSTRUCTIONS On this fun, list the eserete delly enit power lesel in Illie-Met for each day in the reporting nenth. Compete to the neerest uhele ne tt.

ab el tEc!1$ ANN!ft e It $Ne $p

\\c!o eisEenhe !$f T ge sue eNceNs lhe f

iHI line (w the restricted power level line)IIn sech cases,the estrege daily enit power setpet sheet should be festnoted to esplein the apperent enenely w

a v

4

-,-..--e.,

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEAuaust 03 1982 COMPLETED BYErich Witinfurter i

TELEPHONE 309-654-2241xi92 HONTH Julv 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

. (HWe-Ne t ).

1.

598.8 17.

684.2 2.

658.2 18, 654.9 3.

614.6 19, 657.5 4.

571.7 20.

652.2 5.

524.0 21.

626.5 6.

579.5 22.

667.0 7.

640.0 23, 702.3

~ _..

B.

667.6 24.

614.4 9.

714.0

25..

586.0

1. 0.

686.5 26, 570.7

~

11, 689.8 27, 575.7 12.

703.1 28.

560.4 13, 683.0 29, 640.5

1. 4.

690.0 3 0 '.

645.5

~

-15.

704.7 31..

657.9 16.

695.8 INSTRUCTIONS On this fun, list the coeroge dolly enit power leoel in IWe-Met for each day in the reporting nenth Compete to the nearest whole ne vett, sEfeM'ab!1e!tUc1abg!ft eft $Ne'n!fh"\\c$sensdn

!$yl Inge ever heNxceeds $he illI line (w the restricted power level line)!In such cases,the soerage daily unit power setput sheet sheeld be festnoted to esplein the apperent onently

c, w r, e r, ; r, r,

e, r,

r, e,

e, m

ere, m

rm

, A "-

Q i

(7 APPENDIX D QTP 300-S13 UNIT SHUTOOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

050-254 March 1978 i

UNIT NAME Qu d-Cities Unit One i

COMPLETED BY R Buss DATE August 6, 1932 REPORT MONTH JULY 1902 TELEPHONE x

1 8

w r

Eb 5

=

=

hg gg E'e 8

LICENSEE j'E { $

C DURATION 5 EVENT

• 8 gg 3

(HOURS) y5g REPORT NO.

i NO.

DATE 8

CORRECTIVE ACTIONS / COMMENTS R

i 82-35 020702 S

0.0 F

5 EA ZZZZZZZ Load reduction requested by Load Dispatcher due to low system demand l

82-36 820704 5

0.0 F

5 EA ZZZZZZZ 82-37 020705 5

0.0 F

5 EA ZZZZZZZ 82-30 G20703 S

0.0 F

5 EA ZZZZZZZ l

82-39 820708 5

0.0 F

5 EA ZZZZZZZ 82-40 320712 S

0.0 F

5 EA ZZZZZZZ

"~

82-41 C?0713 5

0.0 F

5 EA ZZZZZZZ i

82-42 320713 S

0.0 F

5 EA ZZZZZZZ l

02-4J 820714 5

0.0 F

5 EA ZZZZZZZ 02-4b C20715 S

0.0 F

5 EA ZZZZZZZ 02-45 820718 F

0.0 B

5 CB XXXXXXX Load reduction to work on IA Recirculation Pump Hotor-Generator Set Oil Cooler

. (finaf)

.-n, v.-----

.-w,

,,,s.--

,----,--,m

-.-----r

,-.--------w-e,-

---,-.----~~n--,,-

- - - - - - ~, -

M P"1 M

M f'"i M

M f""3 M

M M

f""1 f""*i M

n n

C~ '

i

~~~'i

(%

(

APPENDIX D QTP 300-513 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 050-254 DOCKET NO.

March 1978 UNIT NAME Qu d-Lities Unit One p

August 6, 1982 309-654-2241, DATE REPORT MONTH JULY 1982 TELEPHONE ext 181 A

5 m

Eb 5

=

z x

Ea 8

@{$

LICENSEE pg gg R

DURATION $

I a" EVENT

• 8 gg (HOURS)

NO.

DATE yIj REPORT NO.

8 CORRECTIVE ACTIONS / COMMENTS R

82-46 820717 5

0.,0 F

5 EA ZZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-47 820/17 5

0.0 F

5 EA ZZZZZZZ l

82-4E G20720 S

0.0 F

5 EA ZZZZZZZ U2-49 820723 S

0.0 F

5 EA ZZZZZZZ J

G2-50 820724 5

0.0 F

5 EA ZZZZZZZ 02-51 320725 5

0.0 F

5 EA ZZZZZZZ C2-52 820728 S

0.0 F

5 EA ZZZZZZZ 82-53 820729 S

0.0 F

5 EA ZZZZZZZ 02-5L 820730 5

0.0 F

5 EA.

ZZZZZZZ i

32-55 820731 S

0.0 F

5 EA ZZZZZZZ

, (final) a

.y

-e-.-u

,,,-y

,y

,y

M F"1 M

F""J M

M M

M M

M M

I"*1 M

M M

f~ '

M

~~ ~7

()

(3 APPENDIX D QTP 300-513 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

050-254 March 1978 UNIT NAME Quad-Cities Unit One COMPlTTED BY R Buss DATE August 6, 19 ?

REPORT MONTH JULY 1982 TELEPHONE i

~

w p

Eb 5

w

=

z E'e 8

LICENSEE pg gg DURATION 5

1. h*

EVENT

=8 g:8 (HOURS)

NO.

DATE E

y5g REPORT NO.

8 CORRECTIVE ACTIONS / COMMENTS R

82-35 C20702 S

0.0 F

5 EA ZZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-36 820704 5

0.0 F

5 EA ZZZZZZZ 82-37 C20705 5

0.0 F

5 EA ZZZZZZZ 82-30 020703 5

0.0 F

5 EA ZZZZZZZ 82-39 G20708 5

0.0 F

5 EA ZZZZZZZ 32-40 320712 S

0.0 F

5 EA ZZZZZZZ 82-41 G20713 S

0.0 F

5 EA ZZZZZZZ l

82-42 320713 S

0.0 F

5 EA ZZZZZZZ 1,

02-4j 820714 5

0.0 F

5 EA ZZZZZZZ 02-4!'

C20/15 5

0.0 F

5 EA ZZZZZZZ 32-45 82071d F

0.0 B

5 CB XXXXXXX Load reduction to work on lA Recirculation Pump j

Hotor-Generator Set Oil Cooler

. (final) 1

_r_

m P

M M

M M

M M

M F '1 M

M M

M M

I

I' f~'

~

( ~.

APPENDIX D QTP 300-s13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revisio*i 5 050-265 DOCKET NO.

March 1978 UNIT NAME Quad-Cities Unit Two COMPLETED BY R Buss 309-654-2241, DATE August 6, 1982 REPORT MONTH JULY 1982 TELEPHONE ext 181 l

I o

5 w

SC 5

m z

x

%e 8

@; 5 LICENSEE pg gg I

Co DURATION $

I$"

EVENT

• 8 g: 8 (HOURS) y5g REPORT NO.

NO.

DATE 8

CORRECTIVE ACTIONS / COMMENTS R

82-30 820701 F

0.0 B

5 HF PUttPXX Reduced load to take 2C Circulating Water Pump out of service 82-31 820703 F

0.0 H

5 HC XXXXXX Load reduced due to low Condenser Vacuum 82-32 820704 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-33 820704 F

0.0 8

5 HF PUMPXX Reduced load to take 2C Circulating Water Pump out of service 82-34 820705 F

0. '0 H

5 HC XXXXXX Load reduced due to low Condenser Vacuum l

82-35 820707 F

0.0 B

5 HF PUMPXX Reduced load to take 2C Circulating Water Pump out of service 82-36 820708 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-37 820708 S

0.0 F

5 EA ZZZZZZ 82-38 820711 S

0.0 B

5 HA XXXXXX Reduced loa'd to perform weekly Turbine tests

. ( f inal')

n P*1 P"'al f"""l n

r"""

n f"""5 T"""

M n

n F.*~J F1

,7 '1 T~'

r' t--'

7"

(%

( ~'

APPENDIX D QTP 300-013 050-265 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

March 1978 Qu d-Cities Unit One UNIT NAME COMPLETED BY R Buss DATE August 6, 1982 309-6M'-224 3 '

REPORT MONTH JULY 1982 TELEPHONE ext 181 i

5 w

et 5

m z

x Em 8

S LICENSEE pg gg R

DURATION $

5 {_., "

EVENT

• 8 g:8 (HOURS) y! 5 g REPORT NO.

NO.

DATE u-8 CORRECTIVE ACTIONS / COMMENTS R

82-39 820712 S

0.0 F

5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-40 820713 S

0.0 F

5 EA ZZZZZZ l

82-41 820714 S

0.0 F

5 EA ZZZZZZ 82-42 820717 5

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine tests 82-43 820717 F

0.0 H

5 HC XXXXXX Load reduced due to low Condenser Vacuum I

82-44 820720 S

0.0 F

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

82-45 820720 S

0.0 F

5 EA ZZZZZZ i

82-46 820724 S

0.0 F

5 EA ZZZZZZ 82-47 820724 S

0.0 F

5 EA ZZZZZZ 82-48 820724 5

0.0 H

5 HF ZZZZZZ Load reduced to lower cooling water temperature

] (final)

~

I

n M

n n

n n

!"'*"1 n

n n

n M

."1 n

T~

F~

f~'

T '

m (3

APPENDIX D QTP 300-513 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

050-265 March 1978 UNIT NAME quad-cities Unit Tw COMPLETED BY R Buss DATE August 6, 1982 309-654-2241, REPORT MONTH JULY 1982 TELEPHONE ext 181 g

8 u

Et 5

m

=

x s'e 8

g LICENSEE gg gg

%g$

g DURATION $

E EVENT

• 8 g:8 3

(HOURS)

NO.

DATE y5 REPORT NO.

8 CORRECTIVE ACTIONS / COMMENTS i

^

82-49 820725 s

0.0 H

.5.

HF ZZZZZZ Load reduced to lower cooling water temperature 82-50 820728 S

0.0 F

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

i i

i l

i 9

l (finai)

VI.

UNIQUE REPORTING REQUIRIMENTS l

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 'IVO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

l t

4 l

l i

i i

l l

r k

n k

I W

i o

-~

P VII. LEFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandta (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Que.d-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

?

A r

T

.i

L.

QTP 300-S32 J~

Rsvision 1 QUAD-CITIES REFUELING March 1978 b,

INFORMATION REQUEST I

.~

1.

Unit:

1 Reload:

6 Cycle:

7 r'

2.

Scheduled date for next refueling shutdown:

Sept 12, 1982 3

Scheduled date for restart following refueling:

Dec 4, 1982 4.

Will refueling cr resumption of operation thereafter require a technical specification change or other IIcense amendment:

YES 5

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

Information:

H L-JULY 26, 1982 6.

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

' different fuel design or supplier, unreviewed design or performance analysis I., /

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

h.

'It1PLEf1ENTATION OF TH'E ODYN TRANSIEt;T ANALYSIS CODE Af40 RESULTS I

(tiCPR SCRAM TIME DEPENDENCE)

T

/

l,

[-

7.

The number of fuel assemblies.

a.

Number of assemblies in core:

224 new/724 total after the b.

Number of assemblies in spent fuel pool: outage 1940 8.

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

~~

a.

Licensed storage capacity for spent fuel:

2920

['

b.

Planned increase in licensed storage:

4636 new/7556 total H

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

LOSS 0F FULL CORE DISCHARGE CAPABILITY - 3/04 A' P P R O V E D V

LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2 01978 Q.c.o.S.R.

e QTP 300-S32 s' ~~

Rsvision 1 QUAD-CITIES REFUELING Harch 1978 I

ds INFORMATION REQUEST

'~

1.

Unit:

2 Reload:

6 Cycle:

7 a

2.

Scheduled date for next refueling shutdown:

Feb 27,1983 3

Scheduled date for restart following refueling:

April 23, 1983 r

4.

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

NO a

5.

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

NONE 6.

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

~

' different fuel design or suppiler, unreviewed design or performance analysis

, /,

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

~~~

NONE P

J-7 The number of fuel assembiles.

~

a.

Number of assemblies in core:

192 new/724 total i

after the b.

Number of assemblies in spent fuel pool: outage 2132 8.

The present licensed 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:

p a.

Licensed storage capacity for spent fuel:

2920 b.

Planned increase in IIcensed storage:

4636 new/7556 total 9

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

i LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84

' C p> p Ft () T/ E' [>

/

• /

LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 l APR 2.01978 Q.c.o.S.R.

VIII. CLOSSARY

{

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

Atmospheric Containment Atmospheric Dilution / Containment

[

ACAD/ CAM Atmospheric Monitoring ANSI American National-Standards Institute APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System Emergency Operations Facility EOF GSEP Generating Stations Emergency Plan HEPA High-Ef ficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System Integrated Primary Containment Leak Rate Test IPCLRT 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 'ower Range Monitor Maximum Average Planar Linear Heat Generation Rate MAPLHGR 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 Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RRRS Residual Heat Rcmoval 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 S RM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traveling Incore Probe TSC Technical Support Center