Text

Monthly Operating Repts for Sept 1992 for Qcs Units 1 & 2.W/
	ML20115A413
Person / Time
Site:	Quad Cities
Issue date:	09/30/1992
From:	Michael Benson, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-92-40, NUDOCS 9210140279
	Download: ML20115A413 (21)
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@ 22710 200 Avenue North CommonweCith Edison i

ound Cities Nuclear Power Station Corcova, !'linois e1242 Telephone 309/654 2241 GCT-92-40 i

October 2, 1992 U. S. Nuclear Regulatory Commission ATIN:

Document Control Desk Hashington, D.C. 20b55

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRCJCheLEoL_.50:15 Land _50.-lO Fnclosed 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 Septembet 1992.

Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR-P0HER STATION

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Gerald C. Tietz Technical Superintendent GCT/MB/dak Enclosdre cc:

A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector yi '

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I-9210140279 920930 PDR ADOCK 05000254 R

PDR

t QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 HONTHLY PERFORMANCE REPORT September '992 COMM0h.iEALTH EDISON COMPANY AND tl I0HA-ILLIN0IS GAS & ELECTRIC COMPANY l

NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 L

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TABLE Of CONTENTS 1.

Introduction II, Summary of Operating Experience A,

Unit One B.

-Unit Two III.

Plant or Procedure Cnanges Tests, Experiments, and Safety Related Ma t r.tenance-A.

Amendments to Facility License or Tecimical 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 t3 n

. A.

I.

IRIRODUCIION Quad-Cities Nuclear Dower Station is composed of two Boiling Hater Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in o

Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois 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 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

'nitial 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 Matt Benson and Debra Kelley, telephone number 309-654-2241, extensions 2995 and 2240.

II II

II. SUliMARLOF_0PERATING EXPERIENCI A.

Un11_One Quad Cities Unit One was taken off line, for Refuel Outage Q1R12, in the early morning of September 20.

A containment valve test was performed on September 4 which required Unit One to reduce power to 300 MWe. -Additional load reductions were performed by the request of Chicago Load Dispatch (CLD) as follows; Date Load Date Load 9-3-92 310 MHe 9-14-92 400 MHe 9-12-92 360 MHe 9-15-92 400 MHe 9-12-92 365 MHe 9-17-92 365 MHe 9-13-92 300 MWe 9-18-92 360 MHe (Ten other load reductions of less than 20% were performed per CLD but not reported.)

B.

Un11_Iwo Quad Cities Unit Two reduced power to 290 MHe on September 10 due to L condenser boot leak.

Ch1La90 Load Dispatch requcsted the following load reductions for Unit Two for the month of September; Date Load atte Load 9-4-92 600 MHe 3-23 92 650 MWe

' 4-92 470 MHe 9-23-92 580 MHe-9-7-92 545 MHe 9-24-92 520.MHe 9-16-92 410 MHe 9-27-92 490 MHe l

9-19-92 640 MHe (four other load reductions of-less than 20% were performed per CLD but-not reported.)

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III. ELANT-OfLE80CIQURE CHANGES. TESIL_EXPJRIMENTSm.

AHQ_ SAFETY RELAlED_tiAINIEtiARCE A._endmeati_to_. eat 11Lty_Licente or Teshnical SagrMica.tlons A.

m Technical Specification Amendment No. 136 wai issued on August 21, 1992 to facility Operating License DPR-29 and Amendment No. 132 to Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2, respectively.

These amendments add an NRC-approved Topical Report to the list of analytical methods for determinina the_

Cycle Specific Limits in the Core Operating L'Imits Report.

Technical Specification Amendment No.137 was issued on August 27, 1992 to Facility Operating License DPR-29 and Anendment No. 133 to fee.111ty Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2,'respectively.

These amendments change an action provision for the High Pressure Coolant Injection and Reactor Cor Isolation Cooling Systems.

B.

Encility or Ptoredure_Cheges_ Requiring _flRC Approval There were no facility or Procedure changes requiring NRC approval for the rcporting period.

C.

Ie.sts_and_EAparimeJLts..Renutr_ing_RRC_Appron1 There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Cottertive liaintenance_of Safety RelatfeLEnulpment The following represer.ts a tabuler summary of the major safety related maintenance performed on Units One arid Two during the reporting peilod.

This summary includes the following:

Work Request Numbers, Licenseg Zvent Report Numbers, Components, Cabse of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent

-Repetition.

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UNIT 1 MAINTENANCE

SUMMARY

HOR'K RE00EST:

SYSTEM EID' DESCRIPTION-HORK PERFORMED 069849 6705 Replace ameter switch and light P6.-tially refurbished cubicle.

Indication sockets.

Q97793 1001 Repair hand wheel on RHRS suction Repaired the locking set screw and tightened the pump valve.

hand wheel lock nut.

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UNIT 2 MAINTENANCE

SUMMARY

WORK REOUEST SYSTEM EID DESCRIPTION

' W)RK PERFORMED 002640 2321 Repair or fermanite' drain from As Found: Elbow blowing steam. As Left:

steam trap-2-2301-1. piping.

Replaced elbow and line adjacent to elbow.

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IV. LICIhSEE EVENT REEORIS 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 the reportable occurrence reporting requirements as set forth in sections 6.6.8.1 and 6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event RenorLNumber DAte T1t1e of_Occurfnte 92-020 09-21-92 Technical Specification Containment Leakage Limit Exceeded..92-022 09-17-92 While transferring 480 Volt Feeds B" CR HVAC failed to autostart,92-023 09-24-92 1B RHR Heat Exchanger failed heat trasfer test (voluntary)92-024 09-23-92 ESF actuation from the 1-1601-23 valve going closed.

UHil 2 Licensee Event Repor_tJ1unce t-

- D.att.e Titie of Occureate 92-022 09-25 2B RHRSH Pump INOP due to plug leaking.

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V.

DAILIABULAIl0RS ihe following data tabulations are presented in this report:

A.

Operating Data Report B.

Average Daily Unit Power t.evel C.

Unit Shutdowns and Power Reductions 4

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APPENDIX C OPERATING DATA REPORT DOCKET NO.50-254 UNIT-One DATE Qsinbar fu_1932___

COMPLETED BY tiittLSinjon iELEPHONE DQ1L654_-2241 OPERATING STATUS 0000 090192

1. REPORTING PERIOD: 2400 03302L GROSS HOURS IN REPORTING PERIOD: 720

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX. DEPENC. CAPACITY: 769 DE$1GN ELECTRICAL RATING (HWe-Net): 789 3, POWER LEVEL TO WHICH RESTRICTED (If ANY) (HHe-Net): P/A

4. REASONS FOR RESTRICTION (IF ANY):

THIS HONTH YR 10 DATE CUMULATIVE

5. HUMBER OF HOURS REACTOR WAS CRITICAL...........

457.1Q 5839.00 142350.10

6. REAC N RESERVE SHUTDOWN HOURS..................

0.0 LL 3421 d*

7. HOURS GENERATOR ON LINE........................

456.70 SMh2Q 138017.3A 0 Q_

9D312._

8. UNIT RESERVE SHUTDOWN HOURS.....................

0.L 1

9. GROSS THERMAL ENERGY GENERATED (HWH).............

734352.0A 12816609.6 296883632.62

10. GROSS ELECTRICAL ENERGY GENERATED (HWH).........

230188.0 4121111.0

_96195447.0

11. NET ELECTRICAL ENERGY GENERATED (MWH).........

21523LL

_39154_4410_

_90664812.0

12. REACTC" SERVICE FAC10R...........................

63.49 30481 79.33

13. REACTOR AVAILABILITY FACT 0R......................

63.49 88101 81.23-

14. UNIT SERVICE FACTOR.............................

63.43 88.00 76.91

15. UNIT AVAILABILITY (ACTOR........................

63.43 BILQQ 77.42

16. UNIT CAPACITY FACTOR (Using MDC)................

38.84 78 23 65.70

17. UNIT CAPACITY FACTOR (Using Design HWe).........

37.85 76.21 u. Q.4

18. UNIT FORCED OUTAGE RATE.........................

0 00 8.34 5 83 2

19. SHUTDOWNS SCHEDULED OVER NEXY 6 MONTHS (TYPE, DLTE. AND DURATION OF EACH):

20. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: _

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Ts u 1.16-9

_m APPENDIX C OPERATING DATA REPORT

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DOCKET NO: 50-265 UNIT Iwo DATE Oct aber 6.1992 COMPLETED RY th11Lft01gn =

TELLPHONE L3021_f54-2241

~ 0PERATING STATUS 0000 090192

1. REPORTING PERIOD: _2400 091021, GROSS HOURS IN REPORTING PERIOD:

720 d

2. CURRENTLY AUTHORIZCD PDWER LEVEL (HWt): 2511 MAX. DEPEND. CAPACITY? 769 DESIGN ELECTRICAL RATING (HWe-Net): 182_

r

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Net): N/A 4, REASONS FOR RESTRICTION (If ANY):

THIS HONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL............

729,0Q 3483 33 13696&il5

6. REACTOR RESERVF SHUTDOWN HOURS..................

0.0 0.0 2985.8

7. HOURS GENERATOR ON LINE.......................

72010A 3412155 133432 45--

8. UNIT RESERVE SHUTDOWN HOURS.....................

0.0 Q2A_

702t1_

9, GROSS THERHAL EN'RGY GENERATED (HWH).........

1738236.00 7441852.80 287525738.80 J

10. GROSS ELECTRICAL ENERGY GENERATED (HWH)..........

_558721.DA 2412282.09 92342412290

11. NET ELECTRICAL ENERGY GENERATED (HWH).....

54'3372.00 2276918.00

,37411093.00

12. REACTOR SERVICE FACT 0R.......................,...

100.00 52 28 77.00

13. REACTOR AVAILABILITY FACT 0R.....................

100.00 52.98 78.68

14. UNIT SERVICE FACTOR.............................

100.00 51.90 75.Q1

15. UNIT AVAI LABI LITY FACTOR........................

100.00.

____.51.90 75 41 6

16. UNIT CAPACITY FACTOR (Using HDC)................

98.14 45.01 51t20 l

17. UNIT CAPACITY FACTOR (Using Design HWe).........

95.65 43.82 62,28

18. UNIT FORCED OUTAGE RATE........................

0.0 0.0 7.90

19. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH):

. 23. If SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORFCAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COHHERCIAL OPERATION 1.16-9 TS 14

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT One DATE October __fu _1932 COMPLETED BY Mitt _i_Eenson TELEPHONE 13091_5M-2241 MONTH _Septe1Dber.1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(MWe-Net) 1.

513 17.

476 2.

505 18, 488 3.

493

19.._.

323 4.

435 20.

-7 5.

52]

21.

-9 6.

483 22.

-8 7.

483 23.

-8 8.

495 2 4. __ __

-8 9.

489 25,

-8 10.

495 26.

-8 11.

tia 27.

-8 12.

413 28.

-8 13.

441_

29.

-8 14. ___

464 30.

-8 15.

474 31.

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421 INSTRUCTIONS On_this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net elet.trical rating of the unit, there may be occasions when the daily average power level exceeds the 1007. line (or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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. APPENDIX B AVERAGE DAILY UNIT POWER LEVEL t

DOCKET NO 50-265 UNIT -Two-DATE RC10ber _6.1992

. COMPLETED BY Matt Benson TELEPHONE 1303)_654-2241 MONTH S.eptember 102 DAY AVERAGE DAIL POWER LEVEL DAY AVERiGE DAILY POWER LEVEL-(MHe-Net)

.(MHe-Net) 1.

750 17.

688 2.

770 18.

776 3.

777

19. _..

770 1.

736_

20.

722 5.

67.3.

21.

782 6.

777 22.

784 7.

709 23.

-766 8.

776 24.

733 9.

-778 25, 738 10.

712 26.

772 11, 670 27.

702 12.

18]

2 8. _...

788 13.

779 29; 787

-14, 784 30.

789

' 15, 782 31.

16, 776 INSTRUCTIONS On this form, list the average daily-unit. power. level in HWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used.to plot a graph for each reporting month.. Note-that when maximum dependable capacity is used for the net. electrical rating of the unit, there may be occasions when the daily average power level exceeds the'1007. line (or the restricted power level;line).

In such cases, the average daily unit power. output sheet should be. footnoted to explain the apparent anomaly.

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l APPENDIX D UNIT SHUTDOWNS AND POWER EDUCTIONS DOCKET NO.

50-254 COMPLETED BY Mathew Benson UNIT NAME Unit One DATE October 6, 1992 REPORT HONTH Faptember 1992 TELEPHONE 309-654-2241 cc N

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REPORT NO.

CORRECTIVE ACTIONS / COMMENTS u

NO.

DATE (HOURS) g Control Valve Testing 92-32 9-03-92 S

6.1 B

5 Control valve Testing 92-33 9-04-92 S

2.8 E

5 Load Drop Per Chicago Load Dispatcher 92-34 9-12-92 S

5.0 F

5 92-35 9-12-92 S

9.1 F

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92-36 9-13-92 S

7.2 F

5 i

92-37 9-14-92 S

6.0 F

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92-38 9-15-92 S

5.4 F

5 92-39 9-17-92 S

3.3 F

5 92-40 9-18-92 S

8.6 F

5 Reactor Shutdown For QlR12 Outage l

92-41 9-19-92 S

262.9 C

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APPENDIX D UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265 UNIT FAffE Unit Tw COMPLETED BY Matt Benson DATE October 6, 1992 REPORT HONTII September 1992 TELEP110NE 309-654-2241 sc E

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DURATION

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DATE (HOURS)

REPORT NO.

CORRECTIVE ACTIONS /fX)MF."ETS g

r 92-64 9-04-92 S

4.4 F

5 Load Drop per Chicago Load Dispatcher 92-65 9-04-92 S

8.0 F

5 92-66 9-07-92 S

6.7 F

5 92-67 9-10-92 F

8.5

'A 5

Condenser Boot Leak 92-68 9-16-92 S

7.9 F

5 Load Drop per Chicago Load Dispatcher 92-69 9 19-92 S

8.0 F

5 92-70 9-23-92 S

2.5 F

S 92-71 9-23-92 S

6.6 F

5 92-72 9-24-92 S

6.0 F

5 4

92-73 9-27-92 S

9.3 F

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VI. UR10VLB1PQRIJhGE0VIREMEllIS The following items are included in this report based on prior commitments to the commission:

A.

tiahJiteutRelleLVAlXeJ)pentbni There were no Main Steam Reliof Valve Operations for the reporting period.

B.

ConhoLRod_Drhft._ Scum Timing _ Data _ Lor _Uniti_Dnft_anLTwo There was no Control Rod Drive scram timing da a for Units One and Two for the reporting period.

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VII. BEDJELIRG_lRFORMATION The following information about future reloads at Quad-Cities Station was j

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

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QTP 300-532

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l Revision 2 Q'JAD CITIES REFUELING October 1989 i

INFORMATION REQUEST 1.

Unit:

41 Reload:

12 Cycle:

12 2.

Scheduled date for next refueling shutdown:

9-20-92*

Actual Shutdown at 0104 hrs, 3.

Scheduled date for restart fnllowing refueling:

12-12-92 4.

Hill refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

1.

Modification to HPCI turbine exhaust steam line-5.

Scheduled date(s) for snt,mitting proposed licensing action aad supporting inforrition-1.

06/30/92 e

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:

159*

In process of core unload, 1970 b.

Number of assemblies in spent in+1 pool:

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 assemulies:

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 b

spent fuel pool assuming the present licensed capacity:

2009 APPROVED i

(final)

OCT 3 01989 14/0395t ;

Q.C.O.S.R.

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-QTP 300-S32~

Revision 2

'QUA0 CITIES' REFUELING-October 1989L INFORMATION~ REQUEST 1.

-Unit:

f2 Reload:

11 0

2=

Cycle:

2.

Scheduled date for next refueling shutdown:

03/06/93 3.

Scheduled date for restart following refueling:

06/05/93 4.

Will refueling or resumption of operation-thereafter require a Technica_1_

Specification change or other license: amendment:

-NOT AS fET DETERMINED.

5.

' Scheduled date(s) for submittin0 proposed licensing action and.

y supporting information:

NOT AS YET DETERMINED.

6.

Irr.portant l' censing considerations associated with refueling, e.g., new-or differer, fuel design-or suppiter, unreviewed. design or performance.

analysis mevods, significant changes in fuel design, neW operating procedures:

NONE AT DRESENT TIME.

7.-

The-number of fuel assemblies.

Number of assemblies in core:

724.-

a.

c b.

Number of assemblies.in spent fuel pool:

2439-3.

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 19.

The projected date of the last refueling that can be discharged to the spent fuel pool' assuming the present licensed capacity: 2009-i L

APPROVED l

( fi"* "

1.4/0395t-OCT 3 01969 t

O.C.O.S.R.

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VIII. GLOSSARY.