Text

Monthly Operating Repts for May 1990 for Quad-Cities Nuclear Power Station Units 1 & 2.W/900602 Ltr
	ML20043F402
Person / Time
Site:	Quad Cities
Issue date:	05/31/1990
From:	Deelsnyder L, Robey R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RAR-90-48, NUDOCS 9006140485
	Download: ML20043F402 (28)
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Quad Cities Nuclear Power Station

,' 22710 206 Avenue North Cordova. Illinois 61242

- Telephone 309/654 2241

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RAR-90-48 June 2, 1990 '

D1' rector of Nuclear Reactor Regu'ations U. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D. C. 20555 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 May, 1990.

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

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. . Robey Tc;hnical Superintendent RAR/LFD/jlg Enclosure 3

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MONTHLY PERFORMANCE REPORT- g

.May, 1990=

a-COMMONHEALTH EDISON COMPANY AND

.-m IONA-ILLIN0IS GAS & ELECTRIC COMPANY-.

NRC~ DOCKET NOS, 50-254 AND 50-265

' LICENSE NOS, DPR-'29 AND DPR-30 .

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. i TABLE 0F' CONTENTS l

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-I.: -Introduction !

I I .- . Summary of Operating Experience- 1

, A.- Unit One B. Unit Two ,

III. . Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance' A. Amendments to-Faci'lity License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval- -'

C. Tests and Experiments Requiring NRC Approval t '

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

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VI. Unique Reporting Requirements

A. Main Steam Relief Valve Operations. i B. Control Rod Drive Scram Timing Data VII. ' Refueling Information VIII. Glossary *

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I. INTRODUCTION- ,

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a Quad-Cities Nuclear Power Station is composed of two Bolling Water- -

Reactors,'each with a Maximum Dependable Capacity of 769 MHe Net, located in Cordova,-Illinois. The Station is jointly owned by Commonwealth-Edison: ;

Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors. The Architect / Engineer was>Sargent & Lundy, Incorporated, and the primary i

construction contractor was United Engineers & Constructors. The Mississippi:

River is the condenser cooling water source. The plant is subject to license :

. numbers OPR-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 complied by Lynne Oeelsnyder and Verna.Koselka, telephone- ,

number- 309-654-2241, extensions 2185 and 2240.

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-II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One ,

i Unit One~ began the month of May operating at 450 MWe for main steam-isolation valve room cooling maintenance. At 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months , on May 1, a load' increase to full power was taken. On May 2, at 0110 hours0.00127 days 0.0306 hours 1.818783e-4 weeks 4.1855e-5 months , ,

.the unit was placed in Economic Generation Control (EGC). From May 3 through May 18.-normal operational activities occurred and routine i surveillances were performed. The unit remained near full power or ,

operated in EGC per the demands of the Chicago Load Dispatcher. Power i levels were adjusted accordingly.

On May 18, at 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months , Unit One entered into a Limiting Condition ;

of Operations (LCO). In December of 1989, during a self. assessment / -

improvement program, several untested pathways for containment leakage-were discovered.- These pathways are not specified in Tech Specs or the FSAR.- The NRC regarded the containment inoperable since these volumes had not been tested. An emergency Tech Spec change was verbally accepted'and the LCO was exited at 1510 hours0.0175 days 0.419 hours 0.0025 weeks 5.74555e-4 months on May 18.

Normal operational activities occurred and routine surveillances were performed from May 19 through May,26. The unit remained near full power or operated in EGC per the demands of the Chicago Load Dispatcher.

Power levels were adjusted.accordingly.

On May 26, at 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months , an alarm was received An the control room ,

indicating "Adsorber Vessels Hi DP". The adsorber mode switch was taken to bypass and a power reduction was taken. Upon investigation, it was discovered that the off gas-system loop scal appeared to have failed. Repairs were made and at 0410 hours0.00475 days 0.114 hours 6.779101e-4 weeks 1.56005e-4 months , load was increased to full power. (h1 May 27, the unit was placed in. EGC. On May 28, at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months , it was discovered while performing QOS 5600-1, Turbine Stop Valve and-Turbine Control Valve Closure Testing, that the #2 Turbine Control Valve did not fast close or give a half-scram signal as expected. Load.was dropped to 300 MWe while maintenance was performed.

At 1105 hours0.0128 days 0.307 hours 0.00183 weeks 4.204525e-4 months , the unit was taken to full power.

I For'the remainder of the month, the unit remained near full power or operated in ECC per the demands of the Chicago Load Dispatcher.

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. . 4-B. Unit Two

- The End .of . Cycle- Ten- Refueling Outage activities continued _ normally for Unit Two during the' month _of May. On May 7, the mode switch was g -

.placed in,STARTUP, the master startup checklist was completed. and h the reactor ~became critical at 0541 hours0.00626 days 0.15 hours 8.945106e-4 weeks 2.058505e-4 months ._ On May 8', at 0122 hours0.00141 days 0.0339 hours 2.017196e-4 weeks 4.6421e-5 months , the generator'was synchronized to the grid. At 0207 hours0.0024 days 0.0575 hours 3.422619e-4 weeks 7.87635e-5 months ,-the generator

was; tripped manuall* / due to high. vibrations. At 0415 hours0.0048 days 0.115 hours 6.861772e-4 weeks 1.579075e-4 months , the generator was again synchronized to the grid. At 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months , hot scram timing for the control rod drive system was begun. On May 9, at 0119 hours0.00138 days 0.0331 hours 1.967593e-4 weeks 4.52795e-5 months , the:

,. turbine was_ tripped to perform turbine overspeed testing. At 0240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months ,-

F the generator was synchronized to the grid. At 2024 hours0.0234 days 0.562 hours 0.00335 weeks 7.70132e-4 months , hot scram timing was successfully completed. Power levels were held constant while additional testing was performed before an ascent to ful1~ power could be taken.

r 6- On May 11. at 1141. hours, an ascent to seventy-five percent power was

. begun with cor. trol rods and recirculation pumps. At 1214 hours0.0141 days 0.337 hours 0.00201 weeks 4.61927e-4 months , power levels were held constant at 457 MWe due to a 2A condensate demineralizer-flow control-valve failure. At 1635 hours0.0189 days 0.454 hours 0.0027 weeks 6.221175e-4 months , a power increase was begun

, and at 2150 hours0.0249 days 0.597 hours 0.00355 weeks 8.18075e-4 months , full power levels were achieved. i From May 12 through May 19, normal operational activities occurred and routine surveillances were performed. On May 20, a power reduction was taken for a drywell entry. On May 21, the unit was taken back to full power.

For the remainder of the month, normal operational activities occurred 3 and routine surveillances were performed. The unit remained near full q power-or operated according to the demands of the Chicago Load Dispatcher.'

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III. PLANT OR PROCEDURE CHANGES,~ TESTS, EXPERIMENTS. AND SAFETY t RELATED MAINTENANCE <

t A. Amendments,to Facility License or Technical Specifications r

Technical-Specification Amendment No. 116 was issued on April 26, 1990 .

to> Facility Operating License DPR-30. This amendment revises the -r Technical; Specifications to eliminate cycle specific ard fuel specific thermal limits.- These limits have been incorporated t a Core Operating

' Limits-Report. j Technical Specification Amendment No, 117 was issued on April 26, 1990 l to Facility Operating License DPR-30. This amendment revises Technical }

Specifications to reduce the number of instrument channels required for HPCI and RCIC area high temperature isolations. The setpoints t for these area high temperature switches were also reduced.

i B. Facility or Procedure Changes Requiring NRC Approval There were -rus Facility or Procedure changes requiring NRC approval (

for the reporting period.

C. Tests and' Experiments Requiring NRC Approval

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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 1 maintenance performed on Units One and Two during the reporting period.

This summary includes: Work Request numbers, system component description.

and work performed. ,

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, 7 UNIT l'MAINTENANCEJ

SUMMARY

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c WORK REQUEST - SYSTEM EID 6ESCRIPTION- . WORK' PERFORMED

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Found two cold solder joints at R3 and -R16.; Resoldered'I .,

the connections and checked the power supply.3_.Reinstalle'd?

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out:.100 VDC'and calibrated LPRM.

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UNIT 2 MAINTENANCE

SUMMARY

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WORK REQUEST- SYSTEM - EID DESCRIPTION WORK PERFORMED Q82383 - 0030 - Penetration MK127 "C"'RHRSW. Removed and replaced outer link seal..

Pump Suction Header Q82381 0030 Penetration MK487 "C" RHRSW Disassembled and replaced seal.

Vault Fire Protection Pipe Q82384 0030 Penetration MK489 "C" RHRSW Cleaned penetration and installed new link seal.

Vault Instrument Air Line Q82385 0030 Penetration Condensate Pump Room Cleaned penetration and installed new link seal.

Vault "C" MK490 Q84421 0100 Penetration Elect. Primary Removed condulet' covers from center conduit.above-Containment external door and applied sealant. Installed covers.

Q84377 0203 Actuator 2C Outboard MSlV Removed air manifold.with 2, 3, 4-way valves.- Dis -

assembled operator cylinder in place to change'out E-rings which were badly worn and hard. Replaced all necessary parts on cylinder. - Rebuilt all manifold valves and installed manifold on cylinder. EM's reconnected solenoids.

Q83999 0220 Hanger Misc for Drywell Piping Revelded pipe support.

Q82806 0261 Thermocouple.3A Target Rock Valve Replaced old thermocouples with new sveglok type thermo--

couples with armor cable.

Q82806 0261 - Thermocouple 261-14E for Relief- Replaced old thermocouples with new sveglok type thermo-Valve 203-3E. couples with armor cable.

Q84273 0737 Solenoid Operated' Ball Tip Machine Found - the coupling between the valve and the solenoid -

not positioned correctly. Repositioned the coupling and put solenoid back on the valve, tested the solenoid and ran a trip probe through the' valve.-

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WORK REQUEST SYSTEM. EID DESCRIPTION WORK PERFORMED Q84159 ,1001. Valve'RHR'2A Pump Suction From~ - Repacked l valve.

Torus Q84343 1025- Hanger LPCI Line Spring Can- Adjusted the spring cans on 2-1025-H46 to 1266#.

' Support Q84366 1601' -Valve Torus Drywell_ Vent from Rebuilt solenoid and bench tested. ' Installed solenoid Reactor Building: Solenoid for . valve. .Had valve stroked and verified proper operation Valve 2-1601-20B and that there wasn't any air leaks. LDisassembled piping to Asco. valve, cleaned threads, tightened.

Q84362 2303- Valve Modulating Relief HPCI Checked and set as necessary the HPCI lube oil. regulating Turbine valves.-

QS4362 2303- Valve, Regulating; HPCI Turbine Checked and set as necessary the HFCI-lube' oil regulating

' Bearing Oil 10# valves.

Q84362 '2303 Valve, Regulating; HPCI Pump Checked and set as necessary the HPCI lube oil regulating..

Bearing 011 20# valves.

Q84362 2303 ' Valve, Regulating; HPCI Control Checked and set as necessary the HPCI lube oil regulating 011 50# valves.

-Q77178 2419 Monitor Local Radiation Torus .. Calibrated on bench, worked'ok. Reinstalled and noise problem came back. Found and repaired cold solder joint -

on K-4 switch lead. Recalibrated. -Works fine now.

Q65858 3053 Line 2A MSIV Packing Leak-Off Removed section of leak off line and capped open< ends 2-3053-A-3/4"-L . per ECN 04-00097M.

Q65860 3053 Line 2C MSIV Packing Leak-Off Cut'out'section of leak off line and capped:open ends ~

2-3053-C-3/4"-L per ENC 04-00097M.

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- -- n m pj ;,- (f i IV. LICENSEE' EVENT REPORTS 4 0'

The following11s a tabular, summary of all licenseeLevent 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.lf, and 6.6.B.2. of the Technical Specifications, af UNIT 1 1 ,

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Licensee Event iReport Number- Date Title of Occurrence 90-09 5-18-90 Various Containment Volumes not LLRT'ed_

m- '90-10 22-90 Clean-Up Isolation on High Temperature 1 UNIT 2 90-06' 5-08-90 RCIC Inop 90-07 5-31-90 Partial Loss of Rod-Position Indicators t

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V. DATA TABULATIONS' -!

[tWie 1 P The following data. tab'ulations are presented!1n this-report:

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-B'. AverageIDailyUnitPowerLevel ]

i; C! Unit Shutdowns!and Power Reductions

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'* Appendix C for~Tebruary, March-and April for Unit.Two are being:

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's , resubmitted with this report due to-an error found in Reactor- [

a li. Critical and Generator On-Line: hours.

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A5 FEN:ll C 0FERI.i!G DATA RE*0RI Declet No. 50-254 hit One Date kne 7, 1990 Cer;1etedfy Lynne feelsnyder Tele: tere 309-634-2241 0FERAI N STATUS !

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1. RecertingPericd 1111. 21H92 Grcss Pcurs in Report Peried: 114

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2. Currently Authori:ed Pener Level (MWt): 21]1 Max.Decend.Caca:ity(Mae-Net): H!

Lesign Electrical Fating ,(Mne-het): Hi

!. Fe er Level to Wtich Restricted (!f Any)' N e-het): BL!

4. Feasons For Restricticn (If any):

THIS MONTH YR 10 D4TE CUMJLATIVE

!. Nueer cf Hours Reactor has Critical 744.0 3506.6 127672.4

6. Reacter Reserve Shutdenn Hours 0.0 0.0 3421.9

7. hours Benerater On Line 744.0. 3454.1 123574.7

6. Unit Reserve shutdenn Hears 0.0 0.0 909.2

9. Eress Therral Ener;y Generated (PWh) 1766452.0 E253679.0 263936040.0

10. Srcss Electrical Energy 6ererated (Min) 574967.0 2706569.0 E5:53126.0

!! Net Electrical Energy Generated (MWh) 550240.0 2595274.0 iO436280.0

12. Reacter Service Factc- 100.0 96.6 60.3

13. Reacter Availability Facter 100.0 96.6 82.5 14.-Unit Service Facter 100.0 96.2 77.7

15. Unit Availability Facter 100,0 96.2 72.3

16. Lait Capacity Facter (Using MDC)- 96.2 93.2 65.E

17. Unit Caca:ity Facter (Using Iesign MWe) 93.7 90.0 64.1

12. Unit Fceced Catage Rate 0.0 2.3 5.3

19. Sautdowns Scheduled Over Next 6 Months (Type, tate, a d Euratien of Each):

20. If Shut b n at End of Report Pericd, Estimated Date of Startue:

21. Units in Test Status (Frier to Cetaerciai Operation): Fc ecast Achieved Initial Cricicality initial Electricity ___

Ccerercial Oceration _ _ , _

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AtfEND!t C DFERAllh5 OATA REFORT De:let .u. 50-265 Onit Two Date kne 7, 1990 Ccarleted iy Lynr.e feelstyder Tele;hore 309-654-2241 DFERATIN5 STATUS 222L9121% .

1. Re:ortin; Period 140) 0,11[M ,

GrossHoursinRe;;rtPerted:?41,.

2. Currently Authcri:ed Fener Level (Mt): 1111 Mas, te:end. Ca:a:ity ("de-keth ?ti Lesign Ele:trical Rating (Par-heth ?!?

3. F:eer Level to Which Restri:ted (If Any) (ne-het): kLA

' 4. Feas:ns Fcr Restri: tion (If any):

THl! M0hid YR TO DATE CUMULAi!VE

5. hater of H:ars Rea:ter Was Critical ti4.3 1369.5 120774.1

6. -Rea:ter Reserve Shutd:4n H:ars 0.0 0.0 2135.8

7. Hours Seterater On Line 571.2 1352.4 u?450.9

9. Unit Reserve Shutd:n1 Hsurs 0.0 0.0 702.9

9. -Gress inertal Energy 6enerated (HM -1255i70.0 2771522.0 252165139.0

10. Gr:ss Electrical Energy 6enerated ( m ) 413778.0 904407.0 80643491.0

!!; Net Ele:trical Energy Generated tu h) 354231.0 046662.0 76326311.0-

12. Rea:ter Se vice Fa:ter 79.9 32.4 76.7

13. Fea t:r Availability Fa:ter 79.9 33.4 70.6

14. Unit Service Fact:r 76.0 37.3 74.6

15. (l nit Availability Fa:ter 76.B 37.3 75.1

16. Unit Capa:ity Fa:ter (Using MX) 65.9 30.4 63.1

17. Unit Ca;a:ity Fa:ter (Using tesign Ne) 67.2 29.6 61.5

19. Unit F:r:e1 Octa;e Rate 0.0 0.0 9.1

19. Shutd:nns 5:heduled Cser heat 6 Menths (Type, Date, and turatien :f Ea:h):

20. If Shut Doun at End of Re;:rt Feriod,'Esticated Date c' Sta*tu :

21. Units in Test Status (Frict to Conser:ial 0:eratten): Feretast A:hieved Initial Criticality

!citial Ele:tri:ity __

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n ercial useratic ___

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APPENDilC ,

' ON RAilN6 DATA REPORT- ;

- Docket No. 50-265 Unit Two i Date May 14,1990 CompletedBy Lynne Deelsnyder Telephone 309-654 2241- .;

OPERATIN6 STATUS 2920-020190 1.' Reporting Period 2400- 022890,, 6ross Hours in Report Period: {72

2. Cctrently Authorized Power Level (Mt): n!! Max. Depend. Capacity (Me-Net): IM Design Electrical Rating (Me-Net): 'lH

3. Fower Level to Which Restricted (If Any) (Me-het): N,lA i

. -4. Reasons for Restriction (If any): I THIS MONTH YR TO DATE CUMULATIVE

5. Nuater of Hours Reactor Was Critical 73.3 795.2 120179.8,

6. Reactor Reserye Shutdown Hours 0.0 0.0 -2985.8

-7 Hours Generator On Line 73.3 781.2 116879.7 ;

8. Unit' Reserve Shutdown Hours 0.0 0.0 702.9 9.- Gross Thermal Energy Generated (Mht 128673.0_ 1512552.0 '250909169.0- +

10, 6ross Electrical Energy 6enerated (Mh)' 42632.0 490629.0 80429713.0

-!!. Net Electrical Energy Generated (Mh) 36425.0 463729.0. 75943378.0

-12. Reactor Service Factor 10.9 56.2 77.4-

13. Reactor Availability Factor 10.9. 56.2 79.4

14. Unit Service Factor 10.9 55.2 75.3

'15. Unit Availability Factor 10.9~ 55.2 75.8 ' f 16.~ Ur!'; Capacity Factor (Using MDC) 7.0 42.6 63.6

17. Unit Capacity Factor (Using Design Me) 6.9 41.5 62.0

18. Unit Forced Outage Rate 0.0 0.0 8.1

19. Shutdowns Scheduled Over Next 6 Months 'fype, Date, and Duration of Each):

20.IlShutDoanatEndofReportPeriod,EstieatedDateofStartup:

21. Units in Test Status (Prior to Consercial Operation): Forecast' Achieved i

Initial Criticality

-s Initial Electricity Coesercial Operation-1.16-9

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i' APPENDilC ,

0FERAllN5DATAREFORT Docket No. 50-265 Unit Two Date May14,1990 !

Coapleted Py Lynne Deelsnyder Telephone 309-654-2241 1

I DPERATIN6 STATUS 9220 030190 l

1. Reporting Feriod 2400 033dt Gross Hours in Report Period: 744 j

2. Currently Authorized Power Level (MWt): D u Man. Depend. Capacity (MWe-Net): 111 l Design Electrical Rating (MWe-Net): !{}

3. Power Level to Which Restricted (!f Any) (MWe-Net): N/A ,

4. . Reasons For Restriction (If any): -

l THIS MONTH YR10DATE CUMULATIVE-l

5. Number of fleurs Reactor Was Critical 0.0 795.2 120179.8 ;

6. Reactor Reserve Shutdown Hours 0.0 0.0 2985.8

' 7. Hours Generator On Line 0.0 781.2 116879.7

8. Unit Reserve Shutdown Hours 0.0 0.0 702.9

9. Gross Thersal Energy Generated (MWh) 0.0 1512552.0 250909169.0 10, 5ross Electrical Energy Generated (MWh) 0.0 490629.0- 80429713.0

11. Net Electrical Energy Generated (MWh) -5581.0 456148.0 75937797.0

12. Reactor Service Factor 0.0 36.8 77.1 ,

13. Reactor Availability Factor 0.0 36.8 79.0 i

14. Unit Service Factor 0.0 36.2 74.9

15. Unit Availability Factor 0.0 36.2 75.4

16. Unit Capacity Factor (Using MDC) -1.0 27.6 63.3

17. Unit Capacity Factor (Using Design MWe) -1.0 26.9 61.7

18. Unit Forced Outage Rate 0.0 0.0 8.1

19. Shutdowns Scheduled Over Nert 6 Months-(Type, Date, and Duration of Each):

20. 11 Shut Down at End of Report Period, Estiaated Date of Startup l

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21. Units in Test Status (Prior to Cassercial Operation): Forecast Achieved Initial Criticality initial Electricity Ceasercial Operation 1.16-9

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, i APPENDII C OPERATIN6 DATA REPORT Docket No. 50-265 Delt Two ,

Date May 14, 1990 Cospleted By Lynne Deelsnyder Telephone 309 654 2241-OPERATING STATUS 0299._Q49190

1. Reporting Period M0 043090 Gross Hours in Report Pariod 7.1,9 r

2. Currently Authorized Power Level (MWt): MlMax. Depend. Capacity (MWe-Net): M Design Electrical Rating (MWe Net): M

3. Power Level to Which Restricted (11 Any) (MWe-Net): N,LA

4. Reasons For Restriction (if any):

4 THIS MONTH YR TD DATE CUMULAi!VE

5. Nuaber of Hours Reactor Was Critical 0.0 795.2 120179.8

6. Reactor Reserve Shutdown Hours 0.0 0.0 2985.8

7. Hours Generator On Line 0.0 781.2 116879.7

8. Unit Reserve Shutdown Hours 0.0 0.0 702.9

9. Gross Thereal Energy Generated (MWh) 0.0 1512552.0 250909169.0

10. Gross Electrical Energy Generated (MWh) 0.0 490629.0 80429713.0

11. Net Electrical Energy Generated (MWh) -5767.0 452381.0 75932030.0 12.- Reactor Service Factor 0.0 27.6 7L.7

13. Reactor Availability Factor 0.0 27.6 78.6

- 14.UnitServiceFactor 0.0 27.1 74.6

!$.UnitAvailabilityFactor 0.0 27.1 75.1

16. Unit Capacity Factor (Using MDC) -1.0 20.4 63.0

17. Unit Capacity Factor (Using Design MWe) -1.0 19.9 61.4

. 18. Unit Forced Outage Rate 0.0 0.0 8.1

19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration cf Each):

20. If Shut Down at End of Report Period, Estisated Date of Startup:

1

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I MFE%Dll t AVERA5! DAILY DIT POWER LEVIL t>cciet kc. 50-265 Unit Two Date June 7. 1990 Cot;letedfy Lynneteelstyder teleph:ne 309-654 2241 PONTH . M DAYAVERAGEDAILYPC#ERLEVEL DAY AVERA5! DA!LY FCWER LEVEL (MWe-het) (PWe-het) 1 -5 17 794 2 -9 18 795

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t V1. UNIQUE REPORTING REQUIREMENTS q-

-The following items are included in this report based on prior-commitments-4 to.the commission:

Ai- MainlSteam 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.

Units- Two i

Date: EMay 7,'1990

. Valves Actuated No. & Type of Actuation

'2-203-3A 1 Manual ~ '

2-203-3B. 1 Manual j 2-203-3C 1 Manual 203-3D =1 Manual 2-203-3E 'l Manual

- Plant Conditions: Reactor Pressure - 923

\

Description of Events: Routine surveillance during startup.following.

refuel outage using the Semi-Annual. Manual Operation of Electromatic Relief Valves'(QOS 201-SI):.

Tech Spect ~Ref. 3.5/4.5.D.1.a .-

4 ~ Unit: 'Two

' Date:- May 9, 1990-Valves Actuated' No. & Type of Actuation

'2-203-3B 1 Manual :)

.l

<3 Plant Conditions: Reactor Presuste - 923 .!

Description of Events: Actuation of,'B' valve performed due to high' valve temperature using the-Semi-Annual. Manual- l; Operation of Electromatic-Relief Valves (QOS~201-SI):- i Tech Spec: Ref. 3.5/4.5.D.1.a j t

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k-B. ' Control Rod Drive Scram' Timing Data for Units--One-and Twol . ,

The basis- for reporting t.his data'to ,theLNuclear; Regulatory Commission' 6

3 ,

are specified in the surveillance, requirements of Technical ~ Specifications:. _q

', '4'. 3. C.1 and -- 4. 3. C. 2.- .

? .t

'The following table is-aTcomplete. summary of Units. One and Two Control Rod Drive Scram. Timing for the reporting period. All scram timing '

+

i i.~was performed with Reactor pressure greater than'800-PSIG. :

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RESULTS OF SCRAM TCING MEhSUREMENTS -

PERF0 FRED ON UNIT 1&2 CONTROL- , .

R00 DRIVES, FROM 1-1-90 TO 12-31-90 .

AVERAGE TIME IN SEC0f0S AT % MAX . T itE INSERTED FROM FULLY WITIORAWN FOR 90%

INSERTION DESCRIPTION NBASER 5 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) 1-22-90 1 0.27 0.65 1.42 2.52 N-10 Unit 1, Hot Scram Timing for test due (2.52) . to 127 Valve Diaphragm Replacement 1-31-90 1 0.29 0.64 1.34 2.36 R-7 Unit 1, Hot Scram Timing for test due (2.36) to 127 Valve Diaphragm Replacement 5-09-90 177 0.30 0.68 1.45 2.54 H-11 Unit 2, Hot Scram Timing during Start Up

. (3.29) Sequence A&B, Cycle 11 i

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VII. REFUELING INFORMNTION

~The.following information about future reloads at Quad-Cities' Station was.

requested in a--January 26, 1978,-11 censing memorandum-(78-24) from D. E,.

. 0'Brien to C. Reed, et al'., titled "Dresden,-Quad-Cities.:and Zion l Station--NRC.l Request for Refueling Information", dated January 18,'1978.

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' QTP 300-S32

Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: 01 Reload: 10 Cycle: 11

2. Scheduled date for next refueling shutdown: 10-27-90

3. Scheduled date for restart following refueling: 1-4-91 I

4. Will refueling or resumption of operation thereafter require a Technical i Specification change or other license amendment:

NONE AS YET DETERMINED.

5. i Scheduled date(s) for submitting proposed licensing action and ;

supporting information:

JULY 6, 1990 1

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 AT PRESENT TIME.

7. The number of fuel assemblies. ,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1537

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

a. Licensed storage capacity for spent fuel: 3657

b. Planned increase in licensed storage: 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 APPROVED i

14/0395t . OCT 3 01969 C).C.O.S.R.

t ;*

QTP 300-532

- Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST

1. Unit: 02 Reload: 10 Cycle: 11

2. Scheduled date for next refueling shutdown: 9-7-91

3. Scheduled date'for restart following refueling: 12-9-91

4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license-amendment:

NOT AS YET DETERMINED.

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

NOT AS YET DETERMINED.

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 AT PRESENT TIME.

7. The number of fuel assemblies,

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 2011 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 in number of fuel assemblies:

l a. Licensed storage capacity for spent fuel: 3897~

b. Planned increase in licensed storage: 0 l 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 l

L APPROVED ,

(final) i- 14/0395t OCT 3 0 549 Q.C.O.S.R.

< c; .

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 BNR - Bolling Hater Reactor CRD -

Control Rod Drive EHC - Electro-Hydraulic Control System E0F -

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 -

Preconditioning Interim Operating Management Recommendations RBCCH - Reactor Building Closed Cooling Hater System RBM -

Rod Block Monitor RCIC -