Text

Monthly Operating Repts for Sept 1991 for Quad Cities Nuclear Station,Units 1 & 2
	ML20079K521
Person / Time
Site:	Quad Cities
Issue date:	09/30/1991
From:	Losekshort C, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GT-91-11, NUDOCS 9110230090
	Download: ML20079K521 (22)
	v • d • e

_ - _ _ _

t GCT-91-11 October 3, 1991 U. S. Nuclear Regulatory Commission ATTH:

Document Control Desk Hastington, D.C. 2055r,

SUBJECT:

Quad Cities Huc1 car Station Units 1 and 2 Honthly Performance Report liRClocke1JioimSQ-25LanL50-255 s

Enclosed for ys information is the Monthly Performance Report covering the e

operation of v.,ad-Cities Nuclear Power Station, Units One and Two, during the

" ith cf upt1991.

atfully, COMONHEA'..TH EDISON COMPANY QUAD-ClllES HUCLEAR POWER STATION

.s

=

O G. C. Tietz G i

Technical Superintendent U 1./CALS/<jak Enclosure D

cc:

A. D. Davis, Regional Administrator T. Taylor, Senior Resident inspector e

i D

y110230090 910930 DR ADOt.K 0500 4

kg/9 i

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k TS 14 y

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 HONTHLY PERFORMANCE REPO.'T SEPTEMBER 1991 COMMONHEAtiN EDISON COMPANY AND IOHA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 h

TS 14 m

d

6 TABLE OF CONTENTS 1.

Introduction II. Summary of Operating Experience A.

Unit One B.

Unit Two III.- Plant or Procedure Changes. T7sts Experiments, and Safety Related Maintenance A.

Amendments to facility License or Technic 61 Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Hafntenance of Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Snutdowns and Power Reductions VI. Unique Reporting Requirements A.- Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data VII.

Ret'ueling Information VIII. Glossary TS 14

I.

1HIR0DUC110N Quad-Cities Nuclear Power Station is composed of two Bolling Hater Reactors, each with a Haximum Dependable Capacity of 769 HHe Net, located in Cordova, 1111nois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Lolling Hater Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction 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 critica11 ties 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 Cynthia A. Loset-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240.

i TS 14 t

11. SVtt%RLOL0EERAllliG_EXEERIEtiCE A.

UntL0ne At the beginning of September Unit One was operating in Economic Generating Control (EGC).

Load drops occurred on the 2nd, 10th, lith, 12th, and 13th at the request of the Chicago load Disaatch.

Load was drop)ed on the 3rd so that a reactor feed pump could le changed over.

On tie 17th load was dropped for a turbine test, on the 25th for turbine and HSIV testing, and also on the 26th for turbine testing.

Load drops also occurred on the 6th for rectreviation pump controller testing and on the 19th due to loss of vc.cuum in the condenser.

B.

Un1LJyo Unit Two was also operating in EGC at the beginning of the month.

Unit Tw, experienced load drops on the 2nd, 5th, 6th, and 12th at the l.

req.est of the Chicago Load Dispatch. On the 19th Unit Two was shutdown per normal procedures due to an inboard MSIV falling closed.

TS 14

III.

EtatiLOR.fROCEDURE CHAtiGESmIESIS._EXPlRIMElilS.

AND SAELILRELAIED_liAlHIERANCE A.

Amendme nt s_to_hC_tlltL Lit en s t_otle c tinis aLS p es i fic at ions There were no Amendments to the facility License or Technical Specifications for the reporting period.

B.

Ea cility_or_fr.o.c e d urelhang e s_Re QUltin g _liRCJpp rov al There were no facility or Procedure changes requiring NRC approval for the reporting period.

C.

Ie s t s_and_Exp erime ntLRe quirin g _tiRCJ p p rov a.1 There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Correst1Yf %1Rienance_oLSn.Cety_Related_Equ.ipment 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 the following: Hork Request Numbers, Licensee Event Report Numbers. Components. Cause of Halfunctions.

Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

TS 14

UNIT 1 MAINTENANCE SUPARY HORK REQUEST SYSTEM EID DESCRIPTION HORK PERFORMEQ Q39468 6700 Counter is inop;rable replace it As Left: Removed front cover to install new with new counter.

counter for breaker, 4 KV Horizontai Magneblast.

Tested breaker and counter worked fine.

092664 9400 Replace carbon trays and test As Found: Second filter housing had water rust canisters on Control Room line and first chamber outer door seal is degraded Eroergency flitration unit.

but still seals. As left: Installed test canister, second chamber (Downstream) on bottom.

Inspected door seals, filter seals and test canister seals. All seals were sealing.

Q94100 0311 Investigate and repair U1 HCV As Found: Disc on removed valve was found to be 34 N2 leak which alarms very dry and hardened. As left: Removed bonnet every shift.

assembly from Instrument block. All 0-Rings were removed and 0-Ring Grooves were cleaned. 0-Rings were lubricated with stitcone Holykote (Graphite Lubrication for valve threads). A new valve was installed in the fell open position and torqued to 50 ft/lb.

090845 1001 Repair seal tite which was As Found: Seal tite was pulled away from motor l

exposed on limitorque motcr housing approximately 1".

As Left: Unscrewed l

both ends of seal tite and refastened valve end l

housing.

seal tite first. Bent the existing conduit back to its original position accroximately 2".

Reattached the other end of seal tite.

Q90989 1053 Replace test fitting on switch.

As Found: Test fitting '<as bac. As left:

Installed new test fitting.

TS 15

UNIT 1 MAINTENANCE

SUMMARY

HORK Pf9 ESI SYSTEM EID DESCRIPTION HORK PERFORMED Q89953 1641 Replace transmitter 1-1641 58 As Found: Recorder and Indicator in transmitter's w/like for like replacement.

loop were indicating normal or plant conditions.

As Left: Hounted tha-new transmitter and re-landed leads on transmitter and the leads on the terminal. Performed 015 54-3 on the transmitter.

Installed new condalt/ plug and new 0-Ring. Did the calibration check on the indicator and recorder as per QIS 54-3.

Readjusted and checked the tolerance between the indicator and recorder it was within.5 ft.

037653 2402 Repair right hand heater element As Found: Found approximately 14 lugs that go to in hot box which has bolt broken the four heaters deteriorating from excessive beat off.

In bot box assembly. Lugs need replacement, wire also brittle, needs replaced. As left: Drilled out broken bolt and tapped hole. Cleaned out catal shavings and replaced hardware and lugs.

I l

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,1 UNIT 2 MAINTEMANCE

SUMMARY

HORK REQ ESI SYSTEM

.EID DESCRIPTION WORK PERFORMED j

Q95045 1705 Investigate and repair U2 28 Main As Found: HV reading 235V on display with HV i

Steam Line high rad monitor Cable connected and disconnected. Operating good failed low.

on bench in shop. As Left: Removed chassis and 4

brought to shop and found nothing unusual with a

chassis. Replaced analog module, high voltage module, and rad monitor. Rad monitor was l

calibrated and functionally tested per QIS 31-3, voltages checked fine 9-10-91.

4 Q95024 5747 Replace U2 HPCI Room cooler fan As Found: Belts were shredded and laying in fan i

belts which are broken.

guard. As left: Removed guard, checked bearings on fan, motor, checked sheaves, replaced belts, 3

adjusted tension and checked alignment.

Reinstalled guard and greased fan bearings.

095199 5207 Investigate and repair U2 5207 As Found: 0-Ring was extruding from filter 1

D/G fuel strainer (2-5207) leaks. housing and cut. As Left: Installed new 0-Ring, tightened evenly and inspected strainer which was i

in good condition.

i 1

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- - - _ = _. - _ _ -

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IV.

LICENSEE.IVENLREPORIS The following is a tabular summary of all Itcensee 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 6.6,0.2 of the Technical Specifications.

UNIL1 Licensee Event Repor.LNumber Date 11tleJL0ccurrence 1

i 91-015 08/27/91 U1 Cable Tunnel flow Switch Out-of-Service for greater than 14 days due to the scope of the work and testing for this (HOD) requiring more than 14 days.91-016 08/30/91 Lines 2-1604-18" and 1-1606-18" outside of design basis.91-017 09/04/91 Control-Room HVAC "B" Train Inop.

91-018-09-14-91 RCIC Inop to repair 125 VDC Ground.

UlflL2 91-10 09/07/91 HPCI Inop due to room cooler belts broke.

91-11 09/18/91 2B Core Spray & RCIC declared Inop because floor drain check valves failed test.

8

(

TS 14'

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4 V.

DATAJAWLAIl0NS i

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 1

9

' TS 14'

APPENDIX C OPERATING DATA MEPORT DOCKET No. $0-254 One UNIT DATE oct ober 3.1991 COMPLETED NY Cynthia A. Losek-Short TELEPHONg 309-654-2241 OPERATING STATUS 0000 090191 2400 093091 g,,,,

Gross HOURe lN ROPORTINO PSRIOD:

M

. CURRENTLY AuTwCRiam0 Power Lev 0L tuwet 2 511 - max. OletNO. CAPACITY tamweed; 769 DSS 60N GLeCTRICAL RATINe tWwthod 789 N/A

1. POWOR L8VOL 70 WMcCH MSBTRICTIO tlP ANY) (Wwehedt 4, REAODNB POR RSSTRICTION llP ANYli THIS MONTH YM19 OATE CUMULAflVS 720.0 2987.0 134468.9

1. NUMSSR OF MOURS REACTOR WAS CRiflCAL............,.

0.0 0.0 3421.9

8. REACTOR Res4RVE SMUTDowN HOURS...................

720.0

?860.3 130??4_6

7. HOUR 0 0tNER AT04 0N LING..........................

0.0 0.0_

900 ?

8. UNIT RestRVE SHUTOOWN HOURS,......................

9. GROSS TManual SNGROY OENER ATIO (WWMI.............1758965.0 6587047.O ?79318487.0

10. GROSS ELECTRICAL GNG AGY 05NER AT80 (WWM)............ 57 3505. 0 2127297.0 _905?!151.0

11. Ntf WLICTRICAL SNGAGY GENERAfl0 (WWHI............. 357400'0- 20?83/8.0 85'n?610.0 100.0 45.6 78.8

12. ' t ACTOR SE RV IC E P ACT OR.......................,...

100.0 45.6 80.0

13. REACTOR AV AlbAtiLITY P ACTOR.....

1 100.0 43.7 76.1

14. UNIT SSRVICE P AC TOR.....................

100.0 41.7 76.8 II. UNif AVAILA#iLITY P ACTOR..

9N*l-40 1 M

18. ' UNIT CAP ACITY F ACTOR IUWac MOC) 95.6 34.?

63.1 g

17. UNIT CAPACITY P ACTOR tuimg 0eogn MWel................

0.0 22.4 5.6

' 14. UNIT PORC50 0UTA48 AATE...................

19. SHUTDOWNS SCHf DULSO OvER NExT 4 MONTHS (TYPt. DATE. ANO OURATION OF EACHl

20. IP SHUT 00wN AT END OF REPORT PERICO. ESTIMATED DATE OP STARTUP:

21, UNITS IN TEST STATUllPRIOR TO COMMERCIAL OPERAT10N1; PORICAST ACHitVED INITI AL CRITICALITY INITIAL E LECTRICITY COMMERClAL OPtRAT1088 1.16 9 s

1, s

APPENDIX C OPER ATING CATA REPORT DOCKET No, 50-265 DO UNIT DATE october 3. 1991 COMPLETED ilY Cynthia A. Losek-Short 309~bb4-2241 TELEPHONg OP8M ATIN4 87ATUS 0000 090191 2400 091001 GRott HOUR $ 1N RSPORTINO P4Rl00 720

1. pl8 PORTING POR600:

2. CUnR4NTLY AUTHOR 1280 POWOR LIVIL IWWih 2611 W AX. 0tPEND. CAP ACITY tmh 769 08860N SLBCTRICAL MATING (Wne.NoiH m

3. POWSR L8 VEL TO WH8CM ROSTRICTED flP ANY) (Wwo Nash N/A

& REASONS POR RESTRDCTION llP ANYll THit M08tTW YM TO DATE CUMULATIVE 437*2 5753 8 133443.0-

l. NUMetR OP HOURS REACTOR WA8 CRITICAL...............

0.0 0.0 298;.&

8. REACTORRt08MyE3 HUT 00WN HOURS................... -

437.2 5706,0 I?7993.0

7. HOUR $ G8NER ATOR ON LINE..........................

0.0 0,0 702.9_

8. UNIT RES8RVE SHUTOOWN HOURS......................

9. GR0es THERMAL ENERGY OtNtR Af t0 (WWMI............. 953664.0 13189549.0 276420870.0 309415.0 4270362.0 8871)$^9.0

10. GROSI ELECTRICAL ENERGY GENER ATIO (WWM)......,,...

297128.0 4129068.0 83959620.0

11. N87 WLICTRICAL IN8RGY GENERATEC (WWMI 60.7 87,8 77.7

12. E ACTOR SE RVICE P ACTOR....................,.

13. REACTOR AV AILAtiLITY P ACTOR.......................

60. 7 87,8 70 s_

60.7_

87.1_

7s_y

14. U NI T I E R V IC I P AC T O R..............................

60.7, 87.1 76.1 -

ll. UNIT AV AIL A tlLITY P ACTOR..........................

52.3 82.0 66 A_

18. UNIT CAPACITY P ACTOR IUeWeg MOC)

SI'3 7

'9

'9-

17. UNIT CAPACITY P ACTOR luwig 0eme MWel.............

18. UNIT FORC8 0 0VT AGE RAT E..................

8.1 39.2 12.;

19. SHUTDOWN 8 SCHG0VLS0 0vtR NtxT 6 WONTH5 tTdt. 0 ATE. ANO DURATION OP E ACMb

20. IP SHUT DOWN AT END OF REPORT PtM:00. ESTIM Af t0 0 ATE OP STARTUP.

21. UNITS IN TEST STATUS (PRIOR 70 COMMEMCI AL QPERATIONl:

PORECAST ACHitVfD INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCI AL QPtRAT604 1.16 9 7.,

n v

APPEN31XB AVERAGE DAILY UNrr POWER LEVEL DOCKET NO. 50-754 UNIT _0" DATE ortnh" t 1991 COMPLETED BY evnthia Losek-Short TELEPHONE 309-654-2?41 MON 1y september DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWeNet)

(MWe-Net) 745 778 g

gy 667 791 g-gg 695 784 3

gg 700 802 4

2, 756 802 5

gg 73N 804 8-22 762 807 y

23 783 807 6

24 0

II5 9

m 70I 797 10 N

779 803 gg y

720 808

~

12 g

72 806 13 29 785 806 14 g

787 gg y

788 16 INSTRUCTIONS On this form, hat the averap daily unit powet level m MWeNet for each day in the reporting month. Compute to the

' Maacst wisone megawatt.

he Agures will be used to plut a staph for ca.h reporung month. Note that when rmumum dependable capacity is u.ed tur the nel clestncal rating ut the unit, there may be owutons when the daily averste power levcl casteds the 100rA lice (or the restricted powet Iciel kne). In such cases, the averanc d.uly unit power output sheet should be fovinoted to capi.ua the apparent anumaly.

l.lM

APPEN3tX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT T*

DATE Ntober 1. j 991 COMPLETED BY.CY" thia 1*sek-Short 4

TELEPHONE 309-6s4-2241 MONTH Sectemb"r j

1 DAY AVERAGE DAILY NWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWehet)

(MWeNet) 6S6 672 1

gy 629 651 3

gg 742 47 3

gg 683

~7 4

20 643

-7 5

gg 688

~7 6

22 706

_7 y

y 701

_7 g

,4 732

-7 g

g 727

-7 10 y

~7 gg 675 27

-7 684 g

12

~7 703 29 g3 701

-7 g

y 701 gg gg 707 16 lNSTRUCTIONS On this form, hst the average daily unit power level in MWeNet for each day in the reporting month, Compute to the nemicst wiione melawatt.

These figutes will be used to plot a graph for ca.h reporung month. Note that when man.imum dependable espacity is und f or the net elevtncal ratt*.3 ut the unit, thete may be owaitons when ths daily average power levci tacetdl the 100A line (or the restrwicd power Ictel Imet in such cases, the average duly urut power output sheet should be i

footnoted to c aplaua the apparent anomaly.

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APPENDIX D UNIT SNL M HS AND POWER REDUCTIONS EDCKET NO.

50-265 COMPLETED B1f Cynthia A. Lesek-Short UNIT NAME Unit 2 October 3, 1991 REPORT MONTH September 1991 TELEPHONE 309-654-2241 j

DATE cc N

UoU 5

a5 5.

Mw a

Q S

LICENSEE

{@

m N

EVENT

$U o"

DURATION M

CORRECTIVE ACTIONS / COMMENTS u

s, NO.

DATE (HOURS)

REPORT NO.

Lead drop per Chicago Load Dispatch 91-24 910902 F

13.5 F

5 I

Load drop per Chicago Load Dispatch 91-25 910905 F

12.5 F

5 Load drop per Chicago Load Dispatch 91-26 910906 F

7.7 F

5 Load drop per Chicago Load Dispatch 91-27 910912 F

7.5 F

5 Unit shutdown due to inboard MSI's' 91-28 910919 F

437.2 A

2 failing closed.

- (fina1)

e

4

~

VI. bHIOULREPORilN Ul[0VIREMMIS r

s The following items are included in this report based on prior conunitments to the conentssion:

A.

Maj n_Sie anLReit eLyalyLOp e ra tion s There were no Main Steam Relief Valve Operations for the reporting period.

B.

ControLRoOIly e_S cram _U ntin 9_D a t aJor_ Unit s _On e._ a n LIwo There was no Control Rod Drive scram timing data for Units One aied Two for the reporting period.

i TS 14

VII. REEUELING_INE0M1A110N The following information about retare reloads ai Quad-Cities Station was requested in a January 26, 1978, 11:ensing memorandum (78-24) from i

D. E. O'Brien to C. Reed, et al., titled "Dre: den. Quad-Cities and Zion Station-.NRC Request for Refueling information", dated January 18, 1478.

i 1

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l; 1[.

OTP 300-132 T

Revision 7 QUAD CITIES REFUEL.ING October 1969 INFOPJ4ATION REQUEST 1.

Unit:--

41 Reload:

11 Cycle: _ 12 2.-

' Scheduled date for next _ refueling shutdown:

9-5-92 l

3.

Scheduled d!:ce for r6 start following refovling:

129-92 e

4..

Will. refueling'or resumption of operation thereafter requiro s Technical N

Specification change or other ligense amendment:

it0T AS YET DETERMINED.

- S.

Scheduled date(s) for submitting proposed licensing actica aad supporttag information:

NOT AS_TET_DET GHINED.

, q

'6..

Impcrtant Itcenstag considerations associatn with refueling e.g., new

or different ] d 'h sten or. Supplier. Vareviewed design or pe,rfors m a Analysis metnods, significe.nt chc.get in tool design, new neerating 3*

procedures:

NONE AT PRESENT TIME.

l

7.

The number of fuel assemblies.

A.

Number of assemblies In Core:

- 774 b.

Number of assemblies in_ spent fuel pool:-

1405

8. -

The present licensed spent fuel pool storage capacity and the site of any. increase in licensed storage capacity that has been requested or is 1

planned in number of fuel' assemblies:

.H.

+

.A.

Licensed storage capacity for spent fuel:

3657 b.

PIknned increase in licensed storage:

0 96 The projected date of the last refueling that can be discharged to the

. spent fuel pool assuming the present licensed capacity:

3 09 APPROVED

< final) 14/0395t 0013 0 M9 O.C.O.S.R.

i d

.QTP 300-532 Revision 2 QUAD CITIES REFUELING Octotier 1989 INFORMATION REQUEST 1.

Unit:

92 Reload:

10 cy;),

13 2.

Scheduled date for next refueling shutdown:

12-28-91 3.

Sche dled Jate for restart following refueling:

3-7-92_

4.

Will refuehng at resumption of operation thereaftet require a Technical Specification change or other license amendment:

NOT AS YET DETERMINED.

5.

M eduled data (s) for submitting preposed licensing action and support!ng inforslation:

Not AS YET DETERMNDe.

L 6.

Important licensing considerations associated with refueling, e.g., new or different fuel desten or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating i

l procedures:

NONE AT PRESENT TIME.

l 7.

The number of fuel assemblies.

l a.

Number of assemblies in core:

724 i

b.

Number of asseinblies in spent fuel pool:

2287 8.

The present licensed spent fuel pool storage capacity and the stre of i

any increase in licensed storage capacity that has been requested or is planned in nunter of fuel assemblies:

l a.

Licensed storage capacity for spent fuel:

3897 b.

Planned increase in licensed storage:

n 1

9.

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

,2009 l

l APPROVED (final) 14/0395t OCT 3 01989 l

Q.C.O.S.R.

l

- ~

1 w,

VIII. Gt05MM 3

i The following abbreviations which may have been used in the Ibnthly Report.

)

are defined below:

j ACAD/CAH - Atmospheric Containment Atmospheric 0110 tion / Containment Atmospheric Monitoring Atnerican Hattonal Standards Institute i

ANSI Average Power Range Monttor

)

APRH Anticipated Transient Without Scram ATHS Dolling Hater Reactor BHR CRD Control Rod Drive Electro-Hydraulic Control System EHC Ernergency Operations facility 1

EOF GSTP Generating Stations Emergency Plan c

liigh-Efficiency Particulate Filter

)

HEPA HPCI High Pressure Coolant Injection System High Radiation Sampling System HRSS Integrated Primary Containment Leak Rate Test IPCLRT Intermediate Range Monitor IRN o

151

- Inservice Inspection Licensee Event Report LfA

!tRT

- Local Leak Rate Test (ow Pressure Coolant Injection Mode of RHRs t.FCI LPRM

- 1.ocal Fower Range Monitor l

HAPLHGR - Maximum Average Planar Linear Heat Generation Rate HCPR

- Hinimum Critical Power Ratio MFLCPR

- Maximum fraction Limiting Critical Power Rat M NPC