Text

Monthly Operating Repts for May 1991 for Quad Cities Nuclear Station,Units 1 & 2
	ML20079B275
Person / Time
Site:	Quad Cities
Issue date:	05/31/1991
From:	Losekshort C, Robey R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	RAR-91-23, NUDOCS 9106140182
	Download: ML20079B275 (22)
	v • d • e

1 RAR-91-23 June 3, 1991 U. S. Nuclear Regulatory Commission ATTH: Document Control Desk Hashington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units I and 2 Monthly Performance Report NRC_DocLet_Nosm50-25.LanL5h205 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 1991.

Respectfully, COMMONRCALTH EDIS0N COMPANY QUAD.C11tES NUCLEAR POWER STATION 2A.lO!R.A. Robe)b Technical Superintendent RAR/CALS/dak Enclosure cc:

A. B. Davis, Wegional Administrator T. Taylor, Senior Resident inspector i

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I 9106t401G2 910531

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TS 14

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 HONTHLY PERFORMANCE REPORT 1

l 4

APRIL 1991 l

l COMMONWEALTH EDISON COMPANY

)

1 AND IDWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS 50-254 AND S0-265 LICENSE NOS. DPR-29 AND DPR-30 TS 14

4 TABLE Of CONTENTS 1

1.

Introduction II.

Summary of Operatthg 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 f

VI.

Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Data 1

f VII.

Refueling Information P

VIII.

Glossary

{

TS 14

1.

INIRODUCIl0N Quad-Cities Nuclear Power Station is composed of two Boiling Hater Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Ediso1 i

Company and towa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Bolling 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 OPR-29 and OPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbei s 50-254 and 50-265.

The d6te 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 Cynthia A. Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240.

TS 14

I II.

SUMMARL0f. 0PERAllNG_ EXPERIENCE A.

Unil_One Unit One began the month of May with the performance of start-up testing and scram timing.

The Unit operated at or near full power for the rest of the month except on May 19th and May 22nd thru the end of the month.

The load drop on the 19th was due to FCL determination and the shutdown that occurred from the 22nd to the end of the month was due to a unit main transformer problem.

B.

Unit _Iwo Unit Two began the month of May operating in Economic Generation i

Control (EGC).

The unit remained in EGC for the month except for two power drops occurring Hay 5th and May 27th.

Thase power drops were due to control rod scram timing on the 5th and Chicago Load Olspatch request on the 27th.

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!!!. PLANLORROC L DU R LC HANG E S..J E S IS. _E R E RI M E NIS.

AND_SAEL1LRELATED3AINTENANCE A.

Ame n d me n t s _to_f a c ility_ L i c e n s e _orJ e c hni_c a L S p e c titt at.t ons There were no Amendments to the Facility License or Technical Specifications for the reporting period.

B.

f ac l Li ty_or_P roc e d u te_ Chang e sJe qu ir.i ng jiRC. App rov a l There were no facility or Procedure changes requiring NRC approval for the reporting period.

C.

Ie s t s _and_Expe rJ ment s_Re quir i n g jiRCJpproy.al There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Cottertlye_Halatenante_of_5afe.ty_Related_Equiprent The followirig reptesents a tabuiar 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, Results and Effects on Safe Operation, and Action laken to Prevent Repetition.

TS 14

U1!IT 1 MAINTEMANCE

SUMMARY

l HORK RE00ESI SY_ STEM EID DESCRIPTION lQiK PERFCRMED 091239 7506 Inspect motor for inapprcipriate As Found: Motor winding had grease on drive end mixture cf grease in bearings.

and opposite end had splattering from over greasing. As left: Rotor ar.d end bells were recoved for bearing replacement. Installed new beerings and greased with Chevron SI R-2, reassembled motor and installed it.

084821 7509 Accass hatch for Standby Gas As left: Sealed the hatch gasket with tape.

Treatment has leak, between fan

)

and MO 1/2-7507B investigate and repair.

088226 7541 Clean out transmitter for As left: Cleaned both regulators and replaced 1/2-7541-6B SBGT B Train. Check lower gasket on the flow inlet controller for dirt and oil en nozzle.

1/2-7541-78. For 1/2-7541-6B flow transmitter cleaned and adjusted regulator to 25 PSIG.

Cleaned relay in 1/2-7541-78 and checked ca11 brat 1on.

Q76738 0302 Repair original detector taken As Left: Replaced capacitor en C1 board still did out under 076739.

not work and was then rejected to vendor.

093052 0311 Investigate and repair nitrcgen As Found: The valve stem was loose in the leak by the stem of 1-0302-111 bor.ne t.

As Left: Replaced wtcle valve tonnet valve.

with new assembly.

Q92920 2303 Repair icng bushing in stuffing As Found: The lower bushing has a sheared l

box which has a broken pin.

anti-rotation pin and bushing has been pushed out of stuffing box. As Left: Cleaned gasket surfaces, lapped stuffing box, compressed gasket within the stuffing box. Reassembled bonnet torqued to final 1200 ft 1bs and stuffing box was at a final torque of 50 'Jt 1bs with new pin i

Installed.

j 092901 7504 Replace Cable #29999 from MCC As Left: Pulled new cable from 4212-29A panel to 29 4 to Standby Gas Treatment MCC 29-4.

Meggered new cable anc: relabeled old Panel 2212-29A.

Cable 29999 to 29985. Left old table in cable trays and then lugged and landed new cable 2999:!.

Also, performed cable functional test on new cable.

~

t UNIT 2 MAINTENANCE _

SUMMARY

~

WORK REOUEST SYSTEM EID DESCRIPTION HOR ( PERFORMED 091970 0762 Repair IRM pre-amp originally As left: Rejected to vendor.

from IRM 17 SER #6, 339, 914 (excessive noise at H1 end of amp.)

Q91099 1640 Repair or replace Category I As Found:

Ink wheel dry. As left: Scraped dried recorder 1-1640-2008 which ink off ink wheel and reinked, later determined dcesn't make any mark on chart.

that print head is worn out. The recorder only prints when ink is first applied and is very wet l

i with ink since the print wheel is not striking hard enough. Calibrated and installed new recorder.

I 084272 2402 Return 2-2402A monitor cell to As left: Rejected to vendor.

vendor for repairs.

091890 5401 Repair solenoid valve exhaust As Found: Oiler found leaking when air was port which is blowing air.

returned to service. As left: Replaced oil

[

solenoid valve with new one.

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IV.

LICENSEE _EVENLilEPORTS l

i lhe following is a tabular sununary 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 B.1 and 6.6,0.2 of the Technical Specifications.

UNILI licensee Event RepotLNumber Date 11tle_oL0ccurrence i

91-012 05-07-91 failure of HPCI to initiate during QC05 2300-13.

UNIL2 There were no licensee event reports for Units 2 for this reporting period.

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e V.

DATA _IABMUDNS 4

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 i

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ArrtWDix C OrtsattuG DATA B(Pott Doctet to. 50 754 Unlt One 0ete June 3,1991 Conpleted By Cynthis Losek short TeterAone 309 654 2241 OPERAllWG STATUS M ll91 1.

ReportingPeriod2120 053091 Cross Mours in Report Period: Z22 2.

Currently Authorised Power Level (Wt): U.11 Men. Depend. Cepecity (We Wet): Zij Desl8n Electrical Reting ( We het): Ig2 3.

Power levet to Which Restricted (if Any) (We Wet): l(L4 4 teosons for Restriction (if any):

INil MONTH Yt 10 Daft CleotAllVE 5.

Wader of Hours Beector Wes criticat 505.6 621.2 132103.1 6.

tenctor Reserve Shutdown Hours 0.0 0.0 3421.9 7.

Hours Generator (n Line 505.6 533.5 127902.8 8.

Unit Reserve Shutdown P.ours 0.0 0.0 909.2 9.

Cross Thornet Energy Generated (Wh) 1079784.0 1112856.0 273844296.0

10. Cross tiectrical Energy Generated ( Wh) 353533.0 3%6718.0 88750572.0

11. het Electricot Energy Generated (Wh) 340254.0 321534.0 83495T75.0

12. tenctor Service f acto.-

70.2 17.3 78.8

13. Aesttor AvellebttIty Foctor 70.2 17.3 80.8

14. telt Service f actor 70.2 14.8 76.3

15. Unit Aveliability factor 70.2 14.8 76.8

16. Unit cepecity f actor (using MDC) 61.5 11.6 64.7

17. Unit cepecity f actor (Using Deslen We) 59.9 11.3 63.1

18. Unit forced Cutete Bete 0.0 0.0 5.3

19. Shutdowns SchechJted Over heat 6 Months (Type, Dete, and Duration of tech):

20. If thut Down et End of Report Period, f atimated Date of Start @s

21. Units in fest Status (Prior to Consettlel Operation):

forecast Achieved initlet criticality inittet tiectricity conomercial Operetton 4

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ArilWDir C Wil AllWG DAT A BlKWt1 Docket No. 50 265 Unit Two Date June 3,1991 Corpleted by Cynthis Losek short Teler one 309 654 2241 e

OPitAllWC STATUS 9000_0M191 1.

Reporting Peried 2400 053091 Grosa Moura in Report Period: 720 2.

Currently Authoriled Power Level (MWt): 211,1 Men. Depend. Copecity (We ket): J12 Design flectrical Reting (We het): It!

3.

Power Levet to Which testricted (If Any) (We het): l!/&

4.

Reasons f or teatriction (if any):

1 Mil MONTH TR TO DATE CLMJLAf!YI 5.

Nwter of Hours Reactor Was Critical 720.0 3143.0 128832.2 6 acector Reserve Shutdom Hours 0.0 0.0 2985.8 7.

tiours Generator on Line 720.0 3112.5 ic5399.5 8.

Unit Reserve shutdown Hours 0.0 0.0 702.9 9.

Cross thermal Energy Generated (Mvh) 1748947.0 7346248.0 2705T7569.0

10. Gross tiectrical inergy Generated (MW) 554561.0 2387127.0 86848334.0

11. het Electricot (nergy Generated (Wh) 536538.0 2310146.0 82140698.0

12. Reactor service Factor 100.0 87.3 77.5

13. Reactor Aveltability Factor 100.0 87.3 79.3

14. Unit service factor 100.0 66.5 75.5

15. Unit Avellability Factor 100.0 86.5 75.9

16. Unit C:.pacity Factor (Using E C) 96.9 83.4 64.3

17. Unit cepecity Factor (Using Design We) 94.4 81.3 62.7

18. Unit Forced Outege Rete 0.0 13.2 8.0

19. Shutdowns SchedJted Over Next 6 Months (Type, Date, and Duretton of tech):

20. If Shut Down et End of Report Period, tstimated Date of Starttet

21. Units in f est status (Prior to Contrerclet operation):

Forecast Achieved inittet Criticality Inittet Electricity Comerclet operetton i

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Art!WDik B AVtRAGE DAILY L*lf POWLR LIVIL l

I Docket No. 50 254 Unit one Date Jme 3,1991 Completed by Cynth?e thort fetesone 309 654+2241 MONTH Mill DAY AVERAGE DAltf POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

( we Net) l 1

146 17 792 2

292 18 794 3

4 09 19 455 4

666 20 T36 5

670 21 676 6

673 22 3

7 749 23 7

8 800 24

+7 9

798 25 7

10 798 26 7

11 798 27 7

12 796 28

+7 13 796 29 7

14 796 30

+7 15 794 31 16 793 INSTRUCTIONS

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On this form, list the everage delly mit power level In We Net for each day in the report {ng month.

Compute to the nearest whole segewett.

These figures will be used to plot a graph for sech reportlns month. Note that when menisua deperdable cepecity is used for the net electrical rating of the unit, there may be occasions when the delly evertie power levet onceeds the 100% Line (or the restricted power level line), in such cases, the everage deity mit power output sheet should be footnoted to e9tein the apperent enomety.

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4 APPtholu 8 AVERAGE DAILY UNil POWit LEVil Docket No. 50 265 Unit two Date brw 3,1991 Cwpteted By Cynthie thort f et yhore 309 654 2241 MONIN Afell DAY AVIRAGE DAILT POWin LEVil DAY AVitAGE DAILY POWER LIVIL (We Net)

( We Net) 1 75 2 17 745 2

744 18 T30 3

732 19 719 4

707 20 764 5

648 21 T.*0 6

754 22 TSO 7

740 23 773 8

738 24 766 9

754 25 731 10 754 26 T30 11 T32 27 688 12 735 28 760 13 774 29 763 14 772 30 750 15 771 31 16 764 IN$1RUCilDNS On this form, list the everage dally unit power level in We Wet f or each day in the reporting month.

Corgnate to the nearest whole regewett.

These figures will be used to plot e Ofeph for each reporting month. Note that when meninst deperdable cepetity la used for the net electrical reting of the unit, there may be occasions when the delly everage power levet eacteds the 100% tine (or the restricted power tevel line), in such cases, the everage deity unit power output sheet should be footnoted to esplein the apparent enomety.

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l VI. UN10V LRER0811NG RE0VIREMEHIS The following items are included in this report based on prior commitments to the commtsslon:

A.

Main _ Steam _RelleLYalve Operations There were no Main Steam Relief Valve Operations for the reporting period.

B.

ControLRoLDrh e_S t raHLllmingJat Llor._Valt 3_00 e_an dJ wo 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 PSIC.

TS 14

4 RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1-91 TO 12/31/91 AVERAGE TIME IN SECONDS AT %

MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%

INSERTION DESCRIMION NUMBER 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 (Averace Scram Insertion Time) i 1-30-91 1

0.28 0.63 1.37 2.45 H-7 U2 scram timing for accumulator replacement (2.45) on H-7 1-30-91 1

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

Sequence A&B, Cycle 12 (Paritial) 5-2-91 177 0.29 0.67 1.44 2.55 R-10 UI Start Up Scram Timing Begin Cycle 12 (3.27) 5-5-91 E9 0.31 0.68 1.43 2.51 B-4 U2 Scram Timing For Sequence A (2.84) 5-6-91 1

0.26 0.62 1.40 2 52 E-12 Ul Scram Timing for *=Ts on Scram Light l

(2.52) 4 4

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4 VII.

REEVEllflG.!NE0 RIM 110ti The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. 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

OTP 300-532 Revision 2 QUAD CITIES RETUELING October 1989 INFORMATION REQUEST

{

l.

Unit:

41 Reload:

11 Cycle:

12 2.

Scheduled date for next refueling shutdown:

9-5-92 3.

Scheduled date for restart following refueling:

12-5-92 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 Ilconsing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or puformance 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:

1405 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 3

spent fuel pool assuming the present Ilcensed capacity:

2009 APPROVED i

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OCT301969 14/0395t '

C).C.O.S.R.

QTP 300-532 t

Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

10 Cycle:

11 2.

Scheduled date for next refueling shutdown:

12-28-91 3.

Scheduled date for restart following refueling:

3-7-92 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:

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:

2287 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:

2009 APPROVED (final) l 14/0395t DCT30t969 l

Q.C.O.S.R.

I L

f s.

C s,

VIII.