ML20056A741

Monthly Operating Repts for Jul 1990 for Quad-Cities Nuclear Station Units 1 & 2

ML20056A741
Person / Time
Site:	Quad Cities
Issue date:	07/31/1990
From:	Hamilton L, Robey R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RAR-90-59, NUDOCS 9008090136
Download: ML20056A741 (22)

Text

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F16 36: y,_,N Commonwealth Edison g7.? ,

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)! ound Cites Nuclear Power Station

. , ' t mti 22710 206 Avenue North-

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I -, \ / Cordova, Ilknois 61242 970

' ' d Telephone 309/654 2241 s.

RAR-90-59 l

August 1, 1990-  !

4 V'.~ S Nuclear Regulatory Commission ATTN: . Document. Control Desk.

Washington, D. C. 20555 q

-l SUBJECT;. Quad Cities Nuclear Station Units 1 and 2 }

Monthly Performance Report .]'

NRC Docket Nos. 50-254 and 50-265

'Enclos'edIfor-your information is the Monthly Performance Report covering 'l the operation of~Quac-Cities;NuclearcPower Station, Units One and Two, ;j during the monthlof' July, 1990.

l Respectfully,

! COMMONWEALTH EDISON COMPANY l L QUAD-CITIES' NUCLEAR POWER STATION  !

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. .R..A. Robey- .

oTechnical. Superintendent l l,, .RAR/LFD/nh Enclosure cc: A.B. Davis, Regional Administrator T.; Taylor,' Senior Resident Inspector 9008090136 900731  % 00n'co V'*

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P QUAD-CITIES NUCLEAR POWER STATION-UNITS 1 AND 2.

MONTHLY PERFORMANCE-REPORT July, 1990 COMMONHEALTH EDISON COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC,00CKET NOS 50-254 AND.50-265 LICENSE NOS.'DPR-29 AND DPR-30 4

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s TABLE OF CONTENTS l

I. Introduction ] ,

-II. Summary of Operating Experience '

A. Unit-One B. Unit Two III, Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance

~

A. , Amendments to facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval' >

C. ' Tests and Experiments Requiring NRC Approval D ' Corrective Maintenance of. Safety Related Equipment IV. - Licensee Event Reports.

V. Data Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions

+

VI. Unique Reporting Requirements-A. Main Steam Relief Valve Operations  ;

B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary L

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I. INTRODUCTION

-Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.- The Station is jointly owned by Commonwealth Edison

' Company and Iowa 1111nois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construccion contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers'DPR-29.and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265. The date of-initial Reactor criticalities for Units One and Two,-respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.

This report was compiled by Tynne Hamilton and Verna Koselka, telephone number 309-654-2241, extensions 2185 and 2240.

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SUMMARY

OF OPERATING EXPERIENCE p

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! A. J Unit One:

Unit One began the month of July-operating at fu'11 power _ levels. On-

.luly 2 Lat 0752-hours. the B Recirculation Motor-Generator Set' Field breaker tripped while Electricians were changing field! brushes on the Motor-Generator.

Set generator. Two groups of. control rods-were' inserted to achieve less AL than an 80% flow contro11line.while theLA. Recirculation pump speed was

-reduced to 65%. Power was reduced from 800'MWe to'296lMWe. . At 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br />, the-B Recirculation-pump.was restarted.: At 1418; hours.. load was increased to full power. j0n' July 4, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, the unit was placed11n Economic'

+ 1 Generation Control (EGC). The unit remained'in EGC or operated near_ full power:until' July 14. The unit was taken out of EGC to perform weekly q surveillances' . Power levels.were adjusted accordingly., '

On July 15, at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, while performing QOS 5600-1,1 Turbine Control Valve Fast' Closure Scram-Instrumentation Functional Test, Control Valve-E No .' I failed to fast close the final 10%. The' rest of the Control Valves j were tested. Valves 2<and'4 failed in-the same manner. Load was dropped  ;

to 244 MWe so this scram function was not required. At 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />, the- l Turbine Control' Valve. Fast Closure Scram Functional Test was_ completed following manual-exercisings of the' Control _ Valve fast closure solenoids.

Load was increased to 450 MWe. On July 16, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, the unit was ,

taken to full power.- 1 On Julyfl9, ant 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />,-power levels were adjusted and;the. unit was placed in-EGC. For the: remainder of the month -the unit remained in EGC-or, operated near full power.with power-levels being adjusted accordingly

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.while routine'surveillances'were performed.- 1 IN~ JUNE'S: MONTHLY REPORT, UNIT ONE

SUMMARY

OF OPERATING EXPERIENCE SHOULD BE. REVISED'TO READ AS:FOLLOWS:.

lon June ~15, during turbine weekly testing, the 'A'= master trip solenoid-

' valve)1ight failed;toLextinguish when'the NSO-attempted to test-the ,'A' -

side. .The 'B' side was-not tested. Weekly. testing was terminated, and fgenerator load was reduced to less than-40% to bypass the turbine trip' l reactor scram while troubleshooting was performed.. The 'A' master trip 1

solenoid valve was'then retested and it worked properly. It-was exercised.  !

several times without a'nalfunction. -Power' levels were. increased to. full  ;]

load at 1040. hours.- (The words " Main Steam Isolation Valve" change to j

Master' Trip Solenoid Valve".)

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. Unit ' Two began' the month .of July . operating at f ull power levels.'--At 2145 1

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hours.Lthe unit was"placed in Economic Generation Control (EGC); From D: July _Ifthru July:14i normal operation'al activities occurred with power .

, i . levels adjusted'according to the demands of'the Chicago Load-Dispatcher .

- with the.Lunit remaining-in ECC or: operating near. full power. Routine surveillances  :

i were[ performed.

-i OniJuly-.14,' load waardropped,to 180 MWe for entry into the-main steam isolation [

valve-(MSIV)) room to inspect the reactor core isolation cooling (RCIC) check: ,

valve. : On" July 15, the investigation was completed,Jand on July 16,,at 1 4

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0010 honts.11oad was increased to 450 MWe. . At 0525

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taken to full power. - On July.'20, at-0058 hours. the unit.was placed in.EGC. j i

For.the remainder:of the month, the unit remained 1n EGC.:or' operated'near, '

, ;fullipower withipower levels.being-adjusted accordingly while routine

, .1. , surveillances were performed.; '

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'l 111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY- RELATED MAINTENANCE t

1 4 A. Amendments to Facility License or Technical Specifications Technical-Specification Amendment No. 125 was issued on June 27, 19'90 1 to Facility Operating License DPR-29. This amendment revises the Technical Specifications to exclude eight containment leak pathways from Appendix J. Type C testing, until the next refueling outage scheduled for October, 1990. A temporary waiver of compliance was approved orally on May' 18, 1990, and in writing on May 22, 1990. The waiver allowed the staff sufficient time to process this emergency technical specification amendment.

'B. Facility or Procedure Chagtes_ Requiri'g NRC Approval  !

'There were no Facility or Prscedure changes requiring NRC approval for i the reporting period.

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

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period.

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

-and work performed.

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UNIT 1 ItAINTENANCE

SUMMARY

SYSTEM EID N SCRIPTION WORK PERFORMED WORK RF. QUEST-Q8370 6601 Piping Misc on 1/2 Diesel Generator Removed damaged line and resoldered joint.

0030 Penetration RHR Service Water Removed link seal and cleaned penetration, lubricated Q80112 Vault MK 484 and installed new seal.

Q77459 0750 RBM 7 Checked all RBM circuits associated with rod B-6 and RBM-7 and found them to be working okay. Bypassed two LPRM's and the INOP rod block did not come up. Bypassed a third and it came up. Every works okay.

As found condition: Found dirty SW 2 worn out. As Q85453 0756 APRM #6 left condition: Replaced switch 2.

2406 Recorder Oxygen-Hydrogen Can Found slight zero shift. Performed loop calibration QS0159 and verified signal converter output to recorder within acceptable tolerance.

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WORK REQUEST: - SYSTEM- EID DESCRIPTION - . WORK PERFORMED-- ' '""

- Q86037- 1201 Limitorque Reactor. Water Cleanup .. AsLfound condition: Motorwas.goingto.lockrotor-current [.

'Recirc Pump Suction Valve  : and not being taken~out by torque.. Lowered torque switch. -

setting-from 2.75 to 1.75 and motor'went to lock rotor.

. for about l second:before torque switch' opened.. Appears sr. ng' pack has-s grease Ic,.k; As'left conditions- Milli-Ohm readings 51 to 523.8 ohns, A1 to AZ 8 ches, S2 to''

F1 1490 ohms.- Mechanical Maintenance installed new spring pack and'upon gressing i'11ed LS compt'up with-grease. Removed:TS and LS-finger block and sealtite.

for' control wiring to clean.

Q84441 5745 Cooler, Room; 2C RHR Service Installed temporary plug.in cracked tube, reassembled -

Water Pump Cubicle cooler.

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, , ./ IV. LICENSEE EVENT REPORTS -

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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 7

C- .the reportable Securrence reporting ~ requirements _as set forth in sections-

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!  % .90-1$j 7/07/90 Reactor = Building Corner N~ Room Floor Drain Check I, , - Valve Stuck Open . .

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4 DATA TABULATIONS i

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7  ; The fo! wing ce tabulations are presented in this report:

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mw oy C AFFEN!!X C CFEAAtl G HTA REFDR1 I>::let No. 5>2/4 Utit One fate Au, cst 2. 1990 C:ttletedI'y L nne hatilten Telephone 109-154-2241 l

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1. Ae;ortingPerted[4,20,,91H92,___ 6tess H:urs in te;crt Ferled: 244 (

2. Carrently Authorized Fcaer Level ;Mth UR Pat. Iepend. Ca: :ity (Ne-Net): 18 Lesign Ele:trical Fating (Fue het): IL9

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3. Fener Level to Rich F.estricted (if Any) (Me-Neth E!]

4. Felsens For Aestriction (!f any):

THIS MCNTH fR 10 DATE CU"JLATIVE

5. kuster of fiours Restter Was Critical 744.0 4972.6 129136.4

6. Featter Reserve Stutdown brs 0.0 0.0 3421.9

- 7. Hours Screrator On Line - 744.0 4148.1 125035.7

8. Unit Reserve Shutdown M rs 0.0 0.0 909.2

9. Bress thersal Energy Bestrated (K W 16t!729.0 11604949.0 2672i7309.0 10, 6tess Electrical Energy Generated (N h> 538376.0 3790567.0 36632144.0

11. Net Electrical Etergy Generated (Nn) 52117F.0 3632309.0 61472695.0

12. Fea:ter Service Facter 100.0 97.E 20.5

13. Featter Availability Fa:ter 100.0 97.E E2.6

14. Unit Service Facter 100.0 97.3 77.9

15. Unit Availability Fatter 100.0 97.3 75.5

16. Ur:it Ca:acity Fatter (Using MDC) 91.1 92.9 66.0

17. Unit _Capa:ity Facter (Usin; Desi;n Me) SB.E 90.5 (4.4 ISiUnitFercedCutageRate 0.0 1.4 5.3

19. Shutdom9s 5:teduled Over heat 6 honths (Tyre. Iate, and Duratten of Ea:h):

20 ~1f Shut 0:wn at End of Report feriod, Esticated Date el Startunt

'21. Units in Test Status (Frier to Ccsaercial Operattor.): Fere:ast Achieved Initial Criticality Initial Electricity Cessercial 0;eration _ ._ - _.

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Gross Hours'in Report Period 744 '

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ye f W  ;!! t Neberfoi Hoursleactor- Was Critical- 1 744.0 2807.2"* =122191.6. Lt 'h IS

1. 1 6.0ReactorRiserveEntdownhours- . 0.0 ;, 'O.01 .~2995.87 Xl

?-L7.jkurs'6eneratbrDnLinsV "?44.0 2759.4f 116857.9h t9. / Unit.' Reserve Shutacadouts < 0. 0 ' ' O.O , f702.9.

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10l6rcas' Electrical Enegy:6enerated (Mh) d!4154.0 T 2437.0- 1926648.0; 21665732.0 T 'E 1117 Net Electrl ital Esergy Generates thh) hf

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100.0 54.2 : .75.3 A _ , 016fUnitJCapacity FactorjUsing MDC) _. .

89.4,  ; 46'6 i . 63. 3 ' _ f Ll7 Unit. Capacity Fastor Jsing Design Me) 66.1 45.7 '61.71

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APPEISIX'D .

UNIT SMTFD0tilf5 AND FOWER REDUCTIONS DOCMET NO. 50-254 .

tRilT NAME Unit One COMPUTED BY Lynne Hamilton -

DATE Aue:ust 2, 1990 REPORT MONTN July. 1990 TELEPHONE 309-654-2241 -

ac

$o8 *" h w" 5 o hw E g8 -Q LICENSEE e@ $go

., ?tJRATION 3 g EVENT E" 8" NO. DATE iHOURS) REPORT NO. CORRECTIVE ACTICIIS/COISBNTS 90-7 900707 F 0.0 H 5 Power Reduction Taken at the Request of the Chicago Load Dispatcher 90-8 900715 F 0.0 A 5 VALEXX Power Reduction Taken So Scram Function I

Was Not Required Du? to Control Valve No. I Failing to Fast Close the Final 10% While Performing Turbine Control Valve Fast-Clost:re Scram Instrumentation Functional Test.

4 A

(final)

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APPENDIX D ,-

UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-265 UNIT NAME Unit Two COMPLETED BY Lynne Hamilton DATE August 2, 1990 REPORT MONTH July, 1990 TELEPHONE 309-654-2241 -

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$oO $

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E gE LICENSEE EVENT E

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NO. DATE g"g REPORT NO. " CORRECTIVE ACTIONS /C0tWENTS (HOURS) g 90-7 900706 F 0.0 H 5 Power Reduction Taken at the Request of Chicago Load Dispatcher. Further Reduction to Retest Main Turbine Stop Valve _No. 3 Following Stop Valve Surveillance 90-8 900714 F 0.0 A 5 ,

VALVEX Power Reduction Taken for Entry into MSIV Room to Inspect RCIC Check Valve e

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(A. ; j The'following iteLa are included: In this yeport based on prior commitments '

4 to the commissiont' .

/A. Main Steam Relief Valve Operations There were no. Main Steam'Reilsf. Valve' Operations for the. reporting period.

L B .' Control Rod Drive Scram Timing Data for-Unita One and'Two.- . ., ,,

.e- ,

n;; . - There was'no Control Rod Drive Scram. Timing Data for Units One and Two-  ;

b 'for'the-reporting period. _

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. VII. REFUELING INFORMATION- l

+

l The following;information about future. reloads at Quad-Clties Station'was j requested in.a' January 26,1978,1icensing memorandum (78-24)~ from D. E.

j' 0'Brien to C;. Reed, Jet al.. . titled "Dresden,' Quad-Cities,- and. Zion g Station--NRC Request.for Refueling Information", dated January 18 1978.-

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.0027H/00612  :

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QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 198g 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 Specification change or other license amendment:

Yes, a proposed change to Technical Specification w;11 be made to relax the Minimum Critical Power Ratio (MCPR) safety limit. This proposal is based on the Unit one Reload 11 Cycle 12 fuel loading.

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

AUGUST 31, 1990 s

l 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, onreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: ,

NONE AT PRESENT TIME.

l

7. The number o? 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 l.

• Tventy-four new fuel bundles have arrived on site and vill be stored in the Unit one new fuel storage vault.

l .

APPROVED ,

(finai) 14/0395t DCT 3 01969 C).C.O.S.R.

. x , ..

QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1949 INFORMATION REQUEST

1. Unit: 02 Reloed: 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 thereaf ter require a Technical Specification change or other license amendment:

NOT AS YET DETERMINED.

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

NOT AS YET DETERMINED.

6. Important Ilcensing 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

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: 3807

b. Planned increase in licensed storage: 0

9. The projected date of the last refueling that can be dischargea to the spent fuel pool assuming the present licensec capacity: 200E APPROVED ,

(final) la/0395t DCI 3 0 f969 O.C.O.S.R.

[.

e 1 -

[

i 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 I APRM - Average Power Range Monitor ATHS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD -

Control Rod Drive t EHC - Electro-Hydraulic Control System l' EOF - Emergency Operations facility GSEP - Generating Sta' ions 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 Inject 1on 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 Velve NIOSH -

National Institute for Occupational Safety and Health PCI - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCH. - Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor p RCIC - Reactor Core Isolation Cooling System .

RHRS -

Residual Heat Removal System RPS - Reactor Protection System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV -

Scram Discharge Volume SRM -

Source Range Monitor

.TBCCW -

Turbine Building Closed Cooling Water System TIP -

Traversing Incore Probe TSC - Technical Support Center

-0027H/0061Z

,