ML20065P608

Monthly Operating Repts for Nov 1990 for Quad Cities,Units 1 & 2

ML20065P608
Person / Time
Site:	Quad Cities
Issue date:	11/30/1990
From:	Hamilton L, Robey R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9012130383
Download: ML20065P608 (21)

Text

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?s RAR 90 86 Deceaber 3,1990 U. S. Nuclear Regulatory Conrnission ATTNt Document Control Desk /

Washington, D. C. 20555

SUBJECT:

Quad Cities Nuclear Station Units i and 2 Monthly Performance Report NRC Docket Nos. 50 254 and 50 265 Enclosed for your information la the Monthly Performance Report covering the operation of Quad Citles Nuclear Power Station, Units One and Two, during the month of Novenber,1990.

Respectfully, COMMONWEALTH EDISON CU PANY QUAD

• CITIES NUCLEAR POWER STATION R. A. Robey

- Technical Superintendent RAR/LFD/ktm

. Enclosure cci A. B. Davis, Regional Adninistrator T. Taylor, Senior Resident inspector 9012130383 901130ADOCK

,PDR PDC 05000254

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QUAD CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT NOVEMBER, 1990 COMMONWEALTH EDISON COMPANY AND IOWA ILLINDIS GAS & ELECTRIC COMPANY NRC DOCKET Nos. 50 254 AND 50 265 LICENSE NOS. OPR 29 AND DPR 30

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TABLE OF CONTENTS

1. Introduction II. Swinary of Operating Experience A. Unit One B. Unit Two 111. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendnents to Facility License or Technical Specifications B. Feellity or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approvat D. Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V. Data Tabulations A. Operating Data Report B. Average Dsity Unit Power Level C. Unit Shutouwns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data VII. Refueling information Vill. Glossary 1-_-__-. - - _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - - - _ _ _ _ . - - _ - _ _ _ - - _ . ..

I. INTRODUCTION Quad Cities Nuclear Power Station is composed of two Bolling Water Reactors, each with a Maximun Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Comnonwealth Edison Company and Iowa Ittinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Conpany Boiling Water Reactors. The Architect / Engineer was Sergent & Lundy, incorporated, and the primary construction contractor was United Engineers &

Constructors. The Mississippi River is the cordenser cooling water source. The plant is subject to license runbers DPR 29 and DPR 30, issued October 1,1971, and March 21, 1972, respectively; pursuant to Docket Nuiters 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. Comnercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.

This report was compiled by Lynne Hamilton and Karen Mc

Dearmon,

telephone number 309 654 2241, extensions 2185 and 2240.

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SUMMARY

OF OPERATING EXPERIENCE A.- Unit One Unit one began the acnth of Novesber operstlng in Economic Generation control (EGC). From November 1 through Novenber 11, }e unit remained in EGC or operated near full power with brief interruptions to perform i n sne survelttances.

On November 11 at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, normat unit shutdown consnenced. At 0248 hours0.00287 days <br />0.0689 hours <br />4.100529e-4 weeks <br />9.4364e-5 months <br /> on Novenber 12, the main tubine was tripped, and at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, Unit one Reactot was manualty scransned to begin the End of Cycle Eleven Refueling Outage. Normal refueling activit(es {

were performed including the removal of the reactor head and steam dryer and core unloading. Core unloading was conpleted on Nomveber 26 at 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br />. Normal refueling activities continued throughout the remainder of the month.

B.- Unit Two

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Unit Two Lyan the month of Novenber operating in Economic Generation Control (ECG).

Normal operettwl: activities were performed for the month of November for Unit Two. The unit remained in ECC or operated near full power with minor interruptions to perform

' routine surveillances. Power levels were adjusted accordingly.

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111. PLANT OR PROCEDURE CHANCES. TESTS. EXPERIMENTS.

AND SAFETY RELATED MA!NTENANCE A. Amerdnents to Facil' tv License or Technical Socelficat f orts Technical Speelfication Amendnent No.127 was lasued on Novenber 6,1990 to f acility Operating License D *R 29 for Quad Cities Nuclear Power Station. This amerdnent revises the Technical Specifica'lona to reflect the use of generically approved fuel type GE 8x8NB by changing the Minimut critical Power Ratio (MCPR) safety limit from 1.07 to 1.06.

B. Facility or Procedure Chances Reoutrina NRC Arcroyal There were no FaclLity or Procedure changes requiring NRC approval for the reporting pcriod.

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

D. Corrective Maintenance of Safety Related Eaulnnent The following represents a tabular sunenary of the major safety related maintenance peforned on Units One and Two during the reporting period. This swynary includes the following:

Work Request Nunbers, Licensee Event Report N'.snbers, Corrponents, Cause of Malfunctions, Results and Ef fects on Safe Operation, and Actlon Taken to Prevent Repetition.

UNIT 1 MAINTENANCE

SUMMARY

i WORK REQUEST . SYSTEM EID DESCRIPTION WORK PERFORMED

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Q87992 7506 Damper, 1/2A SBGT Fan Backdraft As found: Damper counter weight had come loose from damper shaft. The set screws on the counter weight were loose and-the tack weld between the counter weight and the shaft had broken. As left: Removed 7 j

counter weight from shaft, tapped chased -

set screw holes, inspected louvers'for damage and proper operatian, re-installed ,

counter weight, installed manual positioning arm, closed access door and resealed with-I mastik and tape.

Q86931 0756 LPRM 24-09 As found: LPRM. bypassed and spiking high.

As left: checked LPRM card, high voltage

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power supply and TDR detector were good.

Ran I/V curves as per QIP 756-1. Left card in the bypass position.

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' UNIT 2 MAINTENANCE

SUMMARY

WORK REQUEST SYSTEM EID DESCRIPTION WORK PERFORMED Q84822 0756 LPRM 32-25A~ As found: LPRM was spiking. As left:

Exchanged LPRM card with same' type.LPRM' card, for test. Found no' problem with

original LPRM card and exchanged back with test card. Cleaned connectors.

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IV. LICEkSEE EVENT REP 0kTS The following is a tabular sunpery of att 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 1 Licensee Event Report Number tatt Title of Occurrence 90 23

• 10/31/90 Back Leakage through 1A Core Spray Floor Drain 90 27 11/4/90 Failure of CMC Auto Demand Mode 90 28 11/2/90 Spurious Closure of N2 Make up Valve 1*1601 57 90 29 11/15/90 1 220 628 (outboard)

Feedwater Check Valve Failed LLRT 90 30 11/8/90 Recire Piping Outside Seismic Design Analysis 90 31 11/20/90 HPCI Temperature Switch Calibration Found High UNIT 2 90 12 11/24/90 U 2 HPCI INOP Due to F Low Controller Malfunction

• 90 23 report for the previous month of October has been cancelled.

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o V. DATA TABULAfl0NS The following data tabulations are presented in this report A. Operating Data Report

8. Average Daily Unit Power Level C. Unit shutdowns and Power Reductions

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n A:8EGil C 4 f- OPEUT!G DATA AERF?

I h u et No. 50-2M Jr,t t Dre l' - hte Oe:etter (, H 90

, ut;1ste:!) L une Farilten

i. Tele:h m 301-6!4-2241 ~

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l. Fe?: ttr=g Peried 200 !!390 G* css H ;rs is Fe;crt f eriod 2M

2. Carrently Auth:rhed Po*e' Level Wth Mll Max. De:rd. ;apa:ity We-Net" ?i9 Destgr Ele:trical Eating We-Net: lH

3. . Fener Level to bich 6estricted (14 And We-Neth g,i,&

. 4.. Feascr.1 Fce Festrictica (H. auh -

e 315 FCNTH YR 70 CAi! Ci W IIVE S. N aber ci Hs s Feacto Was Critt:4L '267.3 7316.1- 171461 .9 6.'-Reactor Reserve Snatdce H ars '0.0- 0.0 3421.9

-7. Hours Generater On Like. 267i 72hi,7 1273M.3-6,L Lt.itLReserve Su tde c scurs 0,0 0.0 99.1

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9 E 5tosr iteraa!_ Energy Etneratea (hh) 602227.0 170a9079.0 272731440,0

-J0, Bress Electrical Energ(Senerated WM.- 199301,0- 55422?7.0 Bs393554.0

11. het Electrica! Erergy 6e,erated WM- 1Esi47.0 5334705.0- B3160044.)

12. Re ntor Service Facto' 37.1 - 91.3 90.5 13.Jea:torAvailabilityF4: tor .37.1- 91.3 82.6

14. Unit Service Fa: tor !7. 2 90.9 76.0 115,1lnitAvailatilityFa:ter 37,2 90.B 78.5

.16. !! nit Capacity F4:ter (thing E) 134.3- iL6 66.2 I: -

17 Untt Capacitylatice ID5ing Nsign Nel ~33.4 84,4 64.5

?!S,. Unit Forced Outsgr Rate _ 0.0 1.5 L2 4 N b h k k - 4 y kg'a N h .k

20. n swt ne at Enrer re;crt term, tottutes cate < stetut .____

21.- Units in fest Status Pri;r ts Cuiercial Cre*ationh fere:ast A:heved initial Eriticali*y __ .a . ,_

inIttal ElP:tricity . ,__,,,,,

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late Dt:este' 4. iii)

Cerclatet it- Lyene Failt:,n '

ielerc9e Di-154-2241 l U EFAi! G !!Ai!!5 HE_11GiL__

1 ' Ae:OrtingPe*ics24&;,,lllMi__ 6* ss S:;rs ir: Re:ert ,Seried: 7p 2 Currently Authori ed 7:mer Level lNt): M1j,Ms. Depend. Capacity (Se4et): Id http Ele:tri:al Batir; the4tt!: ]M P

3. Fuer Level to ht:5 Festrittre (If hy) @edeth ELA 4, Feasons for.Eestrict!cn.ill anh' Te!5 FCNiH iP TO DUE C W .AfiVE

- 5. Wuer. ci boursleacter Was Critical. 720.0 556Lt  !?4543.2 1 6. Re.::ce Reserve Sutde c N urs- 0.0 0.0 2465.!

17i. Hears Sentratcr On Line 720,0 -5444.5 121543.0

6. -Unit Reserve Snut e c h w s, 0,0 ~ 0.0 702,9.

9. Brest 14rul Erergy Benerated (NM 1676151.0 12102607.0  !!!499224.0 10 Grest Ele:trical Energy Generated (N M 553919.0 .3950M9.0 63!!9593.0- o

!!. Net Ele:trical Energy Generated (n u 537647.0 37??260,0 79276909.0

12. #ea:tdr Servite is:ter! . 100.0 69.4 77.2 cl3, Reatter Availability Fa:ter- 100.0 49.4 79.1 -

14 ;thit 3ervice Fa

!cr !M.J 67.? 75.!

15. D it.A nilability Fa;ter . IN.0 -67.9 75.6.

16.UnitCaca:ityFaiterjusingFD 97,1= 61.A 63.7

.17- Unit Capacity f a:ter U.';tn; :^eii;rhe).

. 94. ! - ' 6 0, 'J . 62.!-

!$... Mit "crced Stage Rate 0,0 - '2,0 7.1. '

-19. 0%teca Etheicled Over.he:tt 6tceths (Tv e, hte, au turatt

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' M. If Put -he at End cf' #e;ert Peri d, ! stinted hte Of 5tarte::: ,__,_ ,_a_

21 !l nits in Test !tatas (Prior te Cea urtial Operatienh Ferecnt A:*ieved Initial Criticality _ _ , ,

lettial Ele:tricit) . , _ _ _ _ _ . . .

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v AFFihMI 1 AVORE Uht UNii F:i!E 1.Ei!L I';ciet k:. 50-2!4 Unit'One Cate De:et:er 3, lii)

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MY AVEF%! MILY P0iER LEVEL M1 AVIU5E DILY 304ER LIVIL We4etL War 4et) .;

1 744. 17 -8 2 -741 15 -B 3 716 19 -3

'4 -773 20 -E 5 .753 - 21 -8 6 -- 747  :: 4 7 :752 23 -E E 735 24 -B 9 731 5 -4 10 719 26 -6

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- Cn this fors,Llist the average daily unit p:ner level ir Nedet icr each day in the re;crting enth.

Ccapte to the nearest whcle me;4=att.

Inese figa es ni!I be used te clet a g a;n i:r ea:h re;;rtir.; scath. N:te that ahea r ui n e de:enja3le -

a;anty is used for tne ret ele:trical ratin; cf ne unit, there say be c:casiers then tne cally avera;e puer le/el ex:eeds the 1007 line (or the restrictej : eer ine! line, b se: cases, the average hily unit;p*er :st;ct sheet s$cel te 'c- tncte: tc ex; lair, the aparent c:uly, 1 lt4

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p-e .j AFffh;D i AVEFAi! MILY 3!T F0W!R LEVEL i

i Oceket he. 50-255-Lnit Two -

ic Late Ce:etter 3, 1990

[ C:ctleted b L pne katilt:$

Tele; @ e 309 654-2241 CNTH N."gVEFIER.

b i DAfAVECASEDAILYF:sERLEWL DAY AVEM3E DAILY ?CaER LEVEL i

_(Bhe-Net) W edet) 1 h 1 763 17 '

714 L -2 76! 15 719 .

-3 743 19 745 4'- s52 ' 20 731 5 767 21 723 6 766 22 726 7 601 23 750 4-B 764 74 .724 i.

9 753 25 704 1'

10 741 26 - '74B

!!' 770 27 741 12- 779 '26 744

!! 740  !? 733 14 75E 30 732 15 767-16 - -755 s

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IN5iPJ0T!0NS On tus Ort, list the antage dail.y unit pder level le Nadet f: ta:h day in the remtir,; snt.t.

Cerpete t:- the nearest $5cle segawatt.'

, Libete ilgures will be uses te plet a graph i sa:n re;ortic; scath, hte that unen m iace de;endatie

! 'capa:ity'is used ict the ret els:trical ratin; ci the u,it, there a eay be cccasicns nherJ the daily average-

- pee r le n! etceeds toe 10 3 line (cr the restri:te! ; cur leve! itt.e!, M such :ases, the average faily l

unit p=er cutpet sheet ecale te f actroted te explain the arcarent arealv.

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VI, UNIOVE REPORilWC RE0blREMEWit the following items are included in this report based on prior commitments to the corrrnission:

A. Main Steam Petief Velve Operations There were no Main Steam Relief Valvo Operations for the reporting period.

B. Control Rod Drive Scram Timino Data for Units one and two There were no Control Rod Drive scram timing data for Units one and two for the reporting period.

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4 Vll. E,[FUEllWG INFORMATION The following Information about future reloads at Quad Cities Station was requested in a January 26, 1978, licensing memorandan (78 24) f rom D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad Cities and Zion Station NRC Request f or Refueling Information", dated January 18, 1978.

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l 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: 11-12-90

3. Scheduled date for restart following refueling: 1-28-91

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

Yes, a proposed change to Technical Specification vill 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 Itcensing action and supporting information:

AUGUST 31, 1990

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

• 144 new fuel bundles have arrived on site and will be stored in the Unit One new fuel storage vault.

1 APPROVED , I (f1na1) 14/0395t 00T 3 01969 I I

Q.C.O.S.R.

QTP 300-S32 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 sup;crting 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 i

l 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: 3897

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 (final) 14/0395t OCT 3 01989 i

O.C.O.S.R. ,

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

. ACAD/ CAM Atmospheric Contalrnent Atmospheric Dilution /Contalrvnent

' Atmospheric Monitoring ANSI

• American National Standards Institute APRM

• Average Power Range Monitor ATWS

• Anticipated Transient Without Scram BWR

• Bolling Water Reactor CRD.

• Control Rod Drive EHC

• Electro Hydraulle Control System EOF

• Emergency Operations Facility CSEP

• Generating Stations Energency Plan HEPA -

• Migh Ef ficiency Particulate filter HPCI- High Pressure Coolant Injection System NRSS

• High Radiation Sampling System

.IPCLRT

• Integrated Primary Containment Leak Rate Test IRM

• Intermediate Range Monttor 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

-MAPLNGR: '* Maxinam Average Planar Linear Heat Generation Rate MCPR

• Minimum Critical Power Ratio MFLCPR

• Maximum Fraction Limiting Critical Power Ratio MPC

• Maxim m Permissible Concentration MSIV .

• Main Steam Isolation valve N!0SH

• National Institute for Occupational Safety and Health PCI'

• Primary Containment Isolation PC10MR

• Preconditloaing Interim Operating Management Reconnendations RBCCW -

• Reactor Building Closed Coo lIng Water System RBM

• Rod Block Monitor RCIC

• Peactor Core Isolation Coollng System RHRS'

• Residual . Heat Removat System

.RPS

• Reactor Protection System.

RWM Rod Worth Mlntmiter

$8GTS

• Standby Cas Treatment System iSBLC

• Stanck>y Liquid Control SDC'

• Shutdown Cooling Mode of RHR$

SDV Scram Discharge Volume SRM

• Source Range Monitor TBCCW-

• Turbine Building Closed Coeling Water System flP

• Traversing incore Prcbe TSC

• Technical Support Center t

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