Text

Monthly Operating Repts for Apr 1991 for Quad Cities Nuclear Station Units 1 & 2
	ML20073L421
Person / Time
Site:	Quad Cities
Issue date:	04/30/1991
From:	Robey R, Short C; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RAR-91-19, NUDOCS 9105130345
	Download: ML20073L421 (23)
	v • d • e

..

. 6,'

g-RAR-91 19 May 3, 1991 U. S. Nuclear Regulatory Commission ATTN:

Document Contr ol Desk Washington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report IBC_DochttJioidQ-254_uid_.50:215 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nucitar Power Station, Units One and Two, during the month of April 1991.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR f'0HER STATION 01 R.A.Rcbe&y Technical Superintsndent RAR/CALS/dak Enc 1csure cc:

A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector i

9105130345 910430

{'DR ADOCK 05000254 POR TS 14 rE2.4 ll:

4 QUAD-CITIES NUCLEAR P0HER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT APRIL 1991 COMMONHEALTH EDISON COMPANY i

AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 i

l l

LICENSE N05. DPR-29 AND DPR-30 1:

l TS 14

l TABLE Of CONTENTS 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 f

VIII. Glossary

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i 1.

INIR000CIl0N i

i Quad-Cities Nuclear Power Station is composed of two Boiling Hater j

Reactors, each with a Maximum Dependable Capacity of 769 MHe Net, located in l

Cordova, Illinois.

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

The Nuclear Steam Supply 1

l Systems are General Electric Company Bolling Hater Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary coistruction contractor was United Engineers & Constructors.

The Mississippi River is the condenser cooling water source.

The plant is subject to license numbers DPR-29 and OPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Do:ket 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. Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240.

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i II.

SUMMARLOLOPIRallBLEXEERLfJfCE l

A.

Unit _One Unit One began the month of April with the continuation of the refuel outage.

Preliminary testing of the Unit continued throughout the month. On April 26th at 1537 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.848285e-4 months <br /> Unit One Generator went on-line signifying the end of Refuel Outage QlRil.

The unit was shutdown on

?

April 27th due to problems with RCIC.

On April 29th the unit was made i

critical and the generator was brought on-line the following day.

Load l

was held at 156 MWe for scram timing for the rest of the month.

l l

B.

UnLt_lwo i

Unit Two began the month of April operating in Economic Generation i

Control (EGC).

The unit remained in EGC for the month with the only interruption being on April 5th. On the-5th of April Unit-power was dropped to 240 Megawatt Electric (MHe) for a Primary Containment leak inspection.

The unit was returned to full power on the same day.

On the 7th of April Unit Two was shutdown due to Technical Specification LCO 3.9.A.3.

The unit was made critical on April 19th, but was shutdown due to problems with the turbine stop valves on April 20th.

following repairs to the turbine stop valves, the unit was made critical and generator went on-line on April 23rd.

Full power was achieved on April 24th and normal operations continued for the rest of April.

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l III.

EL6HT OfLEROCEDURE CHANGESm.IESIS.lXEER11iENIL AND SAFETY RELATED MAINTENANCE 1

1 i'

A.

6mendmants.to facility License or Technical Specifications There were no Amendments to the facility License or Technical Specifications for the reporting period.

i B.

Eacility or Protsdure Changes Rtguirina NRC Aoproyal 4

There were no facility or Procedure changes requiring NRC approval for

~

the reporting period.

C.

191t. Land _ Experiments Requirina NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

J D.

Correttive.Jialatenance of Safety _RelAtsLEnulpment 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:

Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Halfunctions, i

Results and Effects on Safe Operation, and Action Taken to Prevent i

Repetition.

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l UNIT 1 MAINTENANCE SUMHARY WORK REOUEST SYSTEM EID DESCRIPTION HORK PERFORMED Q87342 0912 Investigate and repair alarm for As Found: Two batteries on 84520-529 circuit Category I.

board were bad. As Left:

Removed old batteries and replaced them with new batteries.

091209 5727 Repair 1/2 DG vent fan.

As Found: Unable to get vent fan to run from either unit feed. As left: Removed HGA Relay using QCEM 700-14 replace with new relay.

Q91295 0020 Repair gasket on Bottom HPCI As Found: The rubber piece for the o'oor sweep was inner South door is halfway out and was missing a couple of screws.

loose-protruding from keeper.

As Left: Installed new door sweep and raised it 1/4" on the one end.

Q76624 0261 Replace missing washer on As Found: Hashers were gone from locking screws setpoint locking screw on low due to partially stripped threads in case. As side switch.

Left:

Removed DPIS and modified old face plate.

Installed new DPIS body only to DPV on rack.

Q91212 2599 Inspect ACAD valve 1-2599-58 As Found: Diaphragm was excessively worn. As when stroked seems to have a Left: Replaced diaphragm and stem seal.

slow response time.

Q91236 8193 Breaker (19-3 E-4) tripped 2X's As Found:

Looked like L2 on breaker got hot, coil investigate further.

on main contractor is cracked in several places.

As Left: M111ohmed motor all reading read.245 meggered and millohred breaker which read ck.

Replace old breaker with new breaker.

l TS 15 l

t s

UNIT 2 MAINTENANCE

SUMMARY

WORK REOUEST SS TEB EID DESCRIPTION HORK PERFORMED i

086091 1053 Replace test fittings on press As Found:

The 1/2" male pipe thread 90 degrees to l

switches 2-1053E and 2-1053F 1/4" tubing SS fittings had galled threads. As which were bad.

Left:

Replaced with like for like fittings using safety-related pipe seal and after installation 4

checked for leaks.

Q88613 2401 Upgrade the 2B CAM heat trace As Found: Heat trace cable unable to maintain output for 280 degrees DW CAM specified temperature. As left: OAD tested new inlet temperature as designed.

heat trace per ECTP #8 Doc. 11.

The CAN Heat i

Trace circuit #7 on Line #2-24018-1/2 was replaced.

i f

TS 15

IV.

1.lCENSEElVENI_ REP _0RTS ihe following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6,0.1 and 5.6.B.2 of the Technical Specifications.

UNH_l Licensee Event Repott_Mumber Eale Llile_of__0ccuttence l

91-009 04/26/91 RCIC Inoperable 91-010 04/27/91 Plant Shutdown due to RCIC INOP Ref. T.S 3.5.E.4.91-011 04/29/91 RCIC oscillation during performance of QCOS 1300-7 RCIC manual Initiation test UMLL2 l

91-005 04/16/91 Unit 2 Shutdown per T.S. 3.9.A,3 Unusual Event 91-006 04/20/91 HPCI INOP TS 14

i V.

DAILIADULAILONS The following data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power 1.evel C.

Unit Shutdowns and Power Reductions v

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APPENDlX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT. U"'

DATE May 3, 1991 COMPLETED BY Cynthia Short 309-654-2241 TELEPHONE 4

MONTH A m t.

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

0 0

2 18 0

0 3

39 4

0 0

20 5

0 21 0

i 6

0 0

22 7

0 0

23 8

0 0

24 9

0 0

3 10-0 26 26 11 0

27 0

12 0

28 0

13 0

29 0

14 0

106 y

15 n

31 16 0

INSTRUCTIONS On this form, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the neaiest whole megawatt.

These figures will be used to plot a graph for caeh reporting month. Note that when maximum dependable capacity is l

used f or she net cleetncal rating of the unit, there may be occasions when the daily average power level exceeds the 1004 line (or the restrwred power level hne). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

1,16-8 l

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AP1*ENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-26s UNIT Two DATE M V 3' 1991 i

COMPLETED BY cynthia st. ort l

TELEPHONE 309-654-2241 APRIL MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) g 764 jy 0

819 0

2 18 818 0

3 g,

774 0

4 20 638 5

21 0

806 0

6 22 61 43 y

23 0

618 8

24 0

821 g

25 813 10 26 0

755 11 27 763 l

12 0

28 0

776 i

13 29 I

785 i

14 0

30 I

15 0

31 16 INSTRUCTIONS l

On this form, list the average daily unit power level in MWe Net for each day m the reporting rnonth. Compute to the neassst whole megawatt.

These figures will be used to plut a graph for cash reporung month. Note that when max.imum dependable capacity is used for the net cleetncal rating of the unit, there may be oscasions when the dsily average power level exceeds the j

100'# kne (or the restruted power level hnc). In such cases, the average daily umt power output sheet should be footnoted to explau4 the apparent anumaly.

1.164 i

APPENDIX C OPERATING DATA REPORT DOCKET NO 60-754 U""

UNif OATE M Y 1 1991 Cynthia Losek-Short COMPLETED liY l

309-654-2241 TELEPHONil OPEIll ATING 8TATUS 0000 04019]

No un MT GRogg H3URE IN RRPORTING PER1001

l. REPORTING PERIOD:

760

2. CURRENTLY AUTHORIZ80 POWIR LEVEL IWWil' 2 51 I W A X. O tPI NO. CA# ACITY (WW,.Neth

/M Ot310N ELECTRICAL RATING IWWpNeth NA

3. POWGR LEVEL TO WHICH RESTRICTIO llP ANY) OdweNeil:

A REASONS POR RSSTRICTION llP ANYit THIE W0iiTH VRT00 Aft CUWULATIVE I15.6 l1%.ft 131347,{

l. NUW8tR OP HOURE MEACTOR WA8 CRITICAL...............

0.0

_0g 1421.4 S. R EACTOR R SSSRVE SHUTDOWN HOURS...................

27.9 27.9 127397.2

7. WOURt QtN ER ATOR ON LINE...............

0.0 0.0 909.2

8. UNIT MtstRVE $ HUT 00wN HOURS...........

33072.0 33072.0 272764512.0

9. GRollTHERMAL ENEROY QENERATED IWWHI 3185.0 3185.0 88197010,p

10. GRC&8 ILECTRICAL ENtRGY CINER ATED IWWHI...........

11. htT FLECTRICAL ENERGY CINERATE0 lWWHI.............. -l726.0_ -18720.0 gli55521.0 16.1 4.0 78.8

12. F E A CT O R S E R V IC E P ACTOR,................,,,,.

16.1 4.0 80.0

13. R E ACTOR AV AI LA BILITY P ACTOR......................

3.9 1.0 76.3 14 UNIT S ERVIC E P ACT OR........................

3.9 1.0 76.8

15. UNIT AV AIL A tlLITY P ACTOR......................,

-0.3

-0.8 64.8 it. UNIT CAPACITY P ACTOR IUmag WDC)

.3

-0.8 63.1

17. UNIT CAPACITY P ACTOR IUW Denspi Wml.................

0.0 0.0 5.1 l

18. U NI T P O RCB 0 0VT Ac t RAf t,,,.,.......,..

19. SMUTOOWN$ $CH40VL50 0VER NixT 6 MONTH $ lTYPt. DATE. AND OURATION OP E ACHh M. IP $ HUT 00WN AT END OF REPORT PERIOD ESTIMAtto DATE OP STARTUP.

21. UNITS IN TEST ST ATUS IPRIOR TO COMMERCI AL OPtRAT10NI; PORECAST ACHitVID INITI AL CRITICAllTY INITIAL ELtCTRICITY COMMERCIAL CPIRATION 1.16 9

APPENDIX C OPERATING DATA REPORT 00CKET NO 90-26; UNIT Two DATE M"Y h 1991 COMPLETED ilY Cvnt hin 1 onei-simrt 309-654-2241 TF LEPHONE Ort R ATINQ 874TUS 3 00 040191 2400 043091 720

t. MSPORTINO PSRIOD:

Gross HOUR 8 tN MEPORTINO PER100:

2Sll M AX. 0EPt NO. CAP ACITY (WW, Nott; 760

2. CURRENTLY AUTHORittD POWER LEVEL (Q#t' N

DESIGN f LECTMICAL RATING tWWeNeth UA 1 POWSR LIVIL 70 evHICH RESTRICTED tiP ANY) lWweNeth

4. RtA40NG POR RESTRICTION UP ANYh THitMONTH YR TO DAf t CVWULAflVE 337.5 2423.0 12811'9

5. NUW98R QP HOURS REACTOR WAS CRITIC AL...............

2%5.8

4. R EACTOR RlllRV E SHUTOOWN HOURS...................

7. HOUR $ 0 t N E R ATOR ON LIN E...................

0.0 0.0 W.9

8. U NI T R t t t R V E S H UT 00WN HOURS......................

1.0 M r.M622.0

9. GROSS THERMAL ENERQY QENERAf tD IMWHI

.0 1832566.0 86293773.0

10. Gross ELECTRICAL ENERGY CINER Af t0 (MWHI...........

.0 816g60.0

11. NET FLECTRICAL ENERQY GENERAf tD (MWH1 46.9 84.1 77 12 " t ACTOR $t RVIC E P ACTOR..................

46.9 84.1

' 9 ' '9

13. R E ACTOR AV AILAtiLITY P ACTOR.....................

45.0 83.1 75.4 14 UNIT S E RVIC E P ACT OR........................

45.0 83.1 75.8

15. UNIT AV AILABILITY P ACTOR.........,,.

41.8 80.1 64,1

18. UNIT CAPACnTY P ACTOR tUmas MDCI......

40.7 78.1 6?,$

17. UNIT CAP ACITY P ACTOM tuung o een Mwel..

54.1 16.5 8. 13

18. uni f P CMC E D OUT AG E RAT E..........................

19. SHUTDOWNS SCHEDULIO QVtm Ntxt 6 MONTHS IT4Pt. DATE. ANO DURATION CF EACHit N. IP $ HUT 00WN AT CND OF REPORT PERT 00. ESTIMATED DAf t OP STARTUP.

21. UNITS IN TEST STATUS IPRIOR TO COMMERCI AL OPERATIONI; P ORECt.5T aCHt2Vic INITI AL CRITIC ALITY INITI AL t LLCTRICITV COMMERCt AL OPE RATION l.16

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VI.

VH10VLRCPOR11NG_REQV!RLMENTS The following items are included in this report based on prior commitments to the commission:

A.

Hein Steam Relief Velve 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.

Unit: One Date:

April 26, 1991 l

Valves Actuated Nodhpe_oLAc tVallon 1-203-3A 1 Hanual 1-203-3B 1 Hanual 1-203-3C 1 Hanual 1-203-3D 1 Hanual 1-203-3L 1 Hanual Plant. Condi tions :

Reactor Pressure - 924 PSIG Description _ollvents:

Post Maintenance and Routine Survelliance Semi-annual, Manual Operation of Electromatic Relief Valves (OC05 203-3),

Tech Spec:

Ref. 3.5/4.5.D.1.a Unit:

Two Date:

April 7, 1991 Velves_ Actuated HomLlyptoLAtluation 2-203-3A 1 Pan"=1 2-203-3D 2-203-3C W

2-203-3D 2-203-3E i

P.lon t. Condi tions :

Reactor Pressure.

o Descdption. 0L Eyents :

Routine Surveil u y

,nual. (k ual Operation of flectromatic Relief Valves (OC05 ?03-3),

Tech Spec:

Ref. 3.5/4.5.D,1.a i

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I B.

ControLRod_DrlyeltnaLIlming_Datalor_UnitL0ne and_Iwo The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period.

All scram timing was performed with reactor pressure greater than 800 PSIG.

1 l

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i TS 14 nv+v---

- r -+ w nnn,.

.--nm-

- ~ -

I I

i i-RESULTS OF SCRAM TIMING MEASUREMENTS j

PERFORMED ON UNIT 1 & 2 CONTROL 1

ROD DRIVES, FROM 1-1-91 TO 12/31/91 i

?,

I' AVERAGE TIME IN SECONDS AT %

MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIPTION NUMBER S

20 1

50 1

90 Technical Specification 3.3.C.1 &

DATE OF RODS 0.375 0.900 2.00 1

3.5 7 sec.

3.3.C.2 (Average Scram Insertion Time) 1-30-91 1

0.28 0.63 1.37 2.45 H-7 U2 scram tining for accumulator replacement (2.45) on H-7 I

1-30-91 1

0.30 0.72 1.53 2.67 F-6 U2 scram timing for accumulator replacement (2.67) en F-6 4-30-91 22/177 0.29 0.67 1.46 2.57 H-11 U1, Hot Scran Timing during Start Up (3.0)

Sequence ASB. Cycle 12 (Paritial) 1 1

i 4

2, 1

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Vll.

R[f ULLil4G INf 0RtiM10N l

The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. I. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

TS 14

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J

l QTP 300-532 Revision 2 OUAD CITIES REFUEllNG October 1989 JNFORMATION REQUEST 1.

Unit:

01 Reload:

10 II Cycle:

2.

Scheduled date for next refueling shutdown:

11-12-90 3.

Scheduled date for restart following refueling:

04-24-91 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amen ment Yes a proposed change to Technical Speci icat on has been made to relax the Minimum Critical Power hatto (MCPR) saiety limit.

This proposal is based on the thit one Reload 11 Cycle 12 fuel leading.

and has received approval.

~

S.

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

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:

1681 8.

The present licensed spent fuel pool storage capacity and the stre of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies; Licensed storage capacity for spent fuel:

3657 a.

b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can i;e discharged to the spent fuel pool assuming the present licensed capacity:

2009 APPROVED i

14/0395t N Q.C.O.S.R.

4 QTP 300-532 Revision 2 QUAD CITIES REFUEllNG October 1989 INFORMATION REQUEST 1.

Unit:

Q2 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 DETERM1NED.

S.

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

l 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 8.

The present licensed spent fuel pool storage capacity and the size of any increase in Ilcensed storage capacity that has been requested or is i

planned in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 3