Text

Monthly Operating Repts for Aug 1992 for Quad-Cities Nuclear Power Station,Units 1 & 2
	ML20104B615
Person / Time
Site:	Quad Cities
Issue date:	08/31/1992
From:	Michael Benson, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-92-37, NUDOCS 9209160024
	Download: ML20104B615 (21)
	v • d • e

.

Comm:nwealth Edison

'4

- Quad Citiss Nuclear Powsr Station -

22710 206 Avenue North '

-_ oordov_a, tilinois 61242

-- Telephone 309/654-2241 GCT-92-37 September 2, 1992 U. S. Nuclear Regulatory Commission

^ ATTN:

Document' Control Desk Hashington, D.C. 20555'-

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2-l

- Monthly Performance Report l

NRC_Dockellosm50-254_anL50-265 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 August 1992.

Respectfully, COMMONWEALTH EDISON COMPANY

' QUAD-CITIES NUCLEAR POWER STATION CruA[ C.$

1 Gerald C. Tietz

-Technical Superintendent-GCT/MB/dak..

-Enclosure cc:

A.-_B. Davis, Regional Administrator.

T. Taylor, Senior; Resident Inspector 160002 2

78 14 9209160024 920831 f

~PDR ADOCK 0D00o254

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T QUAD-CITIES NUCLEAR POWER STATION

-UNITS 1 AND 2 HONTHLY PERFORMANCE REPORT AUGUST 1992 L

COMMONWEALTH EDISON COMPANY AND LIONA-ILLIN0IS GAS & ELECTRIC COMPANY

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

l l

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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-Fequiring 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

)

TS te

l I.

IBIBDECILON Quad-Cities Nuclear Power Station is composed of two Bolling Hater Reactors, each with a Maximum Dependable Capacity of 769 MHe Net, located in 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 Hater Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary l

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 0ctober 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers 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.

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 j

-309-654-2241,. extensions 2995-and 2240.

l>

L L.

L TS 14

c II.-

SUMMARY

OF OPERATING EXPERLERCE A.

Vatt_0n.e -

9 Quad Cities Unit One was in coast down for the month of August in preparation for-the: upcoming refuel outage.

Only one significant load reduction occured in August. On August 15 Unit One took a manual SCRAM when the electro-hydraulic control (EHC) system loss level due to a fluid leak.

Numerous normal load reductions of less than 201 were performed per our Load Dispatcher'but not reported.

B.

Unit Typ Quad Cities Unit Two reduced power to 200 MWe on August 2, 9, and 13 so tnat work could be performed in the Main Steam Isolation Valve (MSIV) room.

Power was also' reduced on August 22, to 650 MWe for a weekly turbine surveillance.

Chicago Load Dispatch requested the following load reductions for Unit Two for the month of August; DA.t1 Load 8-1-92:

470 MWe

'7-6-92 550 MWe 7-7-92 455 MWe 7-8-92 555 MWe 7-11 625 MWe 7-12 -538 MWe 7-14-92 600 MWe 7-15-92 545 MWe.

7-16-92 450 MWe 7-18-92 600 MWe 7-20-92:

550 MWe 7-21-92 550 MWe 7-23-92 600 MWe 7-25-92 600 MWe 7-26-92 550 MWe 7-27-92 475 MWe 7-28-92 470 MWe 7-31-92 500 MWe TS 14 -

III.

P1AtiLOR_P20CEDURE CHANGES. TESISMERIMERIS.

AND_SAf ElYELAIER MAINTERedfCE A.

Agendments_to_ facility Lisense_or_ItchnLcal_Specificailoni There were no Amendments to the facility License or Technical Specifications for the reporting period.

B.

Enlltiy_ot_Pzoc.edre._ChaDsellesul. tin 93RC_ApproyAl There were no Facility or Procedure changes requiring NRC approval for.

the reporting period.

C.

leils and Exnerlaenti_ReguitingRC_Apnoyal There were no Tests or Experiments requiring NRC approval.or the reporting period.

D.

Cor_rective MainteDAnte of Safety Related Egulpment The following represents a tabi'lar summary of the major safety related maintenance performed on Units One and Two during the reporting period.

This semmary includes the following:

Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

T814

UNIT 1 MAINTENANCE

SUMMARY

HORK RE00ESI SYSTEM EID DESCRIPTIQH-HORK PERFORMED 002353 5200 Repair leak on Diesel Generator Removed old union, cleanad threads, sealed mating fuel oil return'line.

surfaces, reinstalled and tightened union.

QO2391-9400 Check refrigerant charge on Installed new filters and adjusted the thermal refrigeration condenser unit expansion valve.

control room HVAC "B" train.

QO2659-6601 Investigate and adjust U1/2 Adjusted the 1/2 Diesel Generator' governor' Diesel Generator and adjust compensation. screw and compensation pointer.

governor for drift.

QO2462 6601 Investigate Unit 1 Diesel Adjusted governor bleed screw and compensation.

Generator.

After adjustment there was no governor drift and the engine speed was stable.

Q02471 5727 Investigate Unit.1 Diesel Cut back burnt wires and crimped two new lugs or Generator vent fan.

one phase inside peckerhead.

Taped all leads.

Fan ran acceptably.

i 002494 6601 Repair fuel oil leak at suction As Found:

Leak found to be cracked thread on to engine driven pump.

nipple. As Left: Repaired and replace nipple.

Replaced pipe reducer.

Q02514 6601 Repair fuel oil leak at discharge Repaired and tested.

Test failed. New work of shaft driven oil pump.

request written (002521).

002521 6601 Repair fuel oil leak at discharge As Found:

Found cracks inside the nipple of the of shaft driven oil pump.

pipe. As Left: Replaced with new fuel oil pump.

Helded new nipple. Replaced fuel oil line.

Retightened one fitting.

TS 15

UNIf 2 MAINTENANCE

SUMMARY

HORK REQUESI SYSTEM EID DESCRIPTION HORK PERFORMED 001126 640 Reprogram LED digital scaling on Reprogrammed recorder PEU #3 to read out in psig reactor level / pressure / steam flow and changed scale for PE!! #3.

recorder.

Q01293 2301 Troubleshoot and repair The pressure and exhaust ports were reversed.

l air-operated steam trap bypass valve operator. A0 2-2301-31 HPCI steam trap bypass.

002047 1002 Tighten or repair 2B RHR pump As Found: Found plug leaking and slightly loose.

I motor bottom motor bearing oil As Left: Tightened pidg.

plug.

QO2365 261 Repair main steam temperature As Found: 2-261-150 switch reads open after being switch.

sprayed with water for a long period of time. As Left: Replaced switch with like for like and stopped water leak.

002412 5745 Investigate D RHR service water Replace both contactor coil leads.

pump room cooler motor.

Q74199 1705 Replace back plate of 28 fuel AS Found: Back plate was broken. As Left:

pool radiation monitor.

Installed new trip unit and set trip points.

Installed sensor convertor.

098851 300 Repair sealtight on U2 CRD module Replace damaged sealtite and documented lifted 50-51.

leads on 700-14.

TS 15

IV. LLCEllSELEYENT 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.B.1 and 6.6.B.2 of the Technical Specifications.

UMLL1 Licensee Event ReporLMumber DAte 1111e_nf__0.tcurence 92-017 08-04-92 Control Room HVAC A/C Comp Inop.92-018 08-13-92 Chlorine Analyzer Failed to Trip.92-019 08-15-92 U-1 Rx Scram Due to EHC Fluid Leak at the #3 Turbine Control Valve 92-021 08-25-92 1/2 DG Inop from Governor instability.

WILL2 Licensee Event Report Number Data Title of Occurente 92-020 06-12-92 "R" Gate Found Open.

Cancelled - investigated under a Radiation

~

Occurence Report.92-020 08-11-92 RCIC Failure to Reach Speed Or Pressure.

l Ts u

V.

DAIA_IABULAll0RS i

The following data tabulations are presented in this-report:

A.

Operating. Data Report.

j B.-

Average Daily Unit Power Level C.

' Unit Shutdowns and Power Reductions 4

TS14

APPENDIX C OPERATING DATA REPORT DOCKET NO $0-254 UNIT Q0 e_____

DATE Septe der 4. 1992__

COMPLETED BY t1A L3enson

]

TELEPHONE L309 L65.4-Z241 OPERATING STATUS 0000 080192

1. REPORTING PERIOD: 2400 Q33192_ GROSS HOURS IN REPORTING PERIOD: 144

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 2511 MAX. DEPEND. CAPACITY: 769 DESIGN ELECTRICAL RATING (MWe-Net): 189_

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWo-Net): tuA

4. REASONS FOR RESTRICTION (If ANY):

THIS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRITICAL...

6f5130

__530L90

__141E93100

6. REAC10R RESERVE SHUTDOWN HOURS.............

_ __Q10_

Q10_.

342119_

7. POURS GENERATOR ON LINE........................

65L30

_5329JD

___1.31360JQ

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

jLQ_

_DJ _

909.2_

9. GR0SS THERMAL ENERGY GENERATED (MWH)........

11h372kdQ 12002251d 22ils91SQ1fA

?O. GROSS ELECTRICAL ENERGY GENERATED (HWH)..........

_36152210_

_3090923A

_9596525910_.

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

_14142310_

_37_4Q4]l,D_

_90.44911910_

12. REACTOR SERVICE FACTOR.

____BL5h 91,92 79J9

13. REACTOR AVAILABILITY FACTOR..............

89.56 91.92 81.31

14. UNIT SERVICE FACTOR...

87,.24

_1L.02 76.97

15. UNIT AVAILABILITY FACTOR.......

87.94 91.02 77.48

16. UNIT CAPACITY FACTOR (Using HDC) 59.kB H3Al fill

17. UNIT CAPACITY FACTOR (Using Design MWe) 58J9 6Q 91 64114

18. UNIT FORCED OUTAGE RATE 1210h 8 99 5.6L 1

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

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

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

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Ta t4 1.16-9

['i' APPENDIX C

' OPERATING DATA REPORT a-DOCKET N0 50-165 UNIT Iyo DATE Seotember dJ3Z._.

- COMPLETED BY Matt Benson TELEPHONE-13ng1_g34 2241 OPERATING STATUS 0000 080192

1. REPORTING PERIOD:.2400 083192 GROSS HOURS IN REPORTING PERIOD:.744

'2. CURRENTLY AUTHORIZED POWER LEVEL (HWt):. 2511 MAX. DEPEND CAPACITY: 269 DESIGN ELECTPICAL RATING (HWe-Net): 289 3.' POWER LEVEL TO WHICH RESTR!sTED (IF ANY) (HWe-Net): N/A-4.-REASONS FOR RESTRICTION (If ANY):

THIS HONTH YR TO DATE CUHULATIVE-

5. NUMBER Of HOURS REACTOR WAS CRITICAL............

'744.QQ 2763255 l'4 2.46425 I

6. REACTOR RESERVE SHUTDOWN HOURS..................

0.0 0.0.

_Z585.,L

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

744 93 2692.55 13211Zd5-2

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

0.0 0.Q_,

702.9

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

-1671345.60 5703616.EQ Z85787502.80

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

542083.0Q 18A3561.00 91773751.00-

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

__51112ZJD 1733546.00 86867721.03 12, REACTOR SERVICE FACT 0R.......................

100.00 41.29 76.90

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

100.0D_

47.20 78.59 14.= UNIT SERVICE FACTOR.............................

100.0L 45.99 74.91

15. UNIT AVAILABILITY FACTOR........................

100.00.

45 32 75.31_

16. UNIT CAPACITY FACTOR (Usi ng HDC)................

__2021L 38.5D 63.76

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

08.03 3ZJ3 62t]f

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

0.0 0.0 7.94

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

20. IF SHUTDOWN AT END.0E REPORT PERIOD. ESTIMATED DATE OF STARTUP:

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

FORECAST ACHIEVED INITIAL CRITICALITY

!~

INITIAL ELELTRICITY l

E COHHERCIAL OPERATION l

1.16-9 T814

- APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 10-254 UNIT One i

DATE Eepigsber 4.1992__ -

COMPLETED BY Matt Benson

-l TELEPHONE 1109L654-2241 MONTH _Aug.usL 1912-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

.(MWe-Net)

(MWe-Net) 1.

525 17.

-8 j

2.

538 18.

4 3.

516 19.

429 4.

556__

20.

549 5.

555 21.

503

~6.

564 22.

501 7.

143 23.

520 8.

553 24, 532 i

9.

547 25.

547 10.

'552 26.

516 11.

'54.6 27.

515

- 12.

- 511__ __

28, 486 13.

526 29.

468 14.

499 30, 504 15..

40-31.

511 16.

-8 INSTRUCTIONS On this-form list the average daily unit power level in MHe-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 j

apparent anomaly.

ra u 1.16-8

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265 UNIT Iwo DATE 5ep.teMer_i_1922_

COMPLETED BY Matt Benson TELEPHONE 1309L55A-2211 MONTH -August 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

644 17.

776 2.

334 18.

732_

3.

646 19.

717 4.

774 20.

694 5,

775 21.

711 6.

535 22.

733 7.

686 23.

736 8.

701 24.

773 t

9 342 25.

750 10.

769 26.

715 11.

749 27.

700 12.

719 28.

616 13.

572 29.

113 14.

73_0

30. _.

73 2 15.

715 31.

703 16.

613 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 electrical rating of the unit, there may be occasions when the daily average powe.- 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 1; UNIT SKUTDOWNS AND POWER REDUCTIONS l DOCKET NO.

50-265 l

l UNIT NAME Two COMPLETED BY Matthew Benson August M2 D#.!E September 4.

1992 REPORT HONTH TELEPHONE 309-654-2241 i

ooh w"

od" hw kw h$

hh LICENSEE m8 g8 EVENT o"

s.,

DURATION

2 ggg NO.

DATE (HOURS)

REPORT NO.

CORRECTIVE ACTIONS / cot 9fENTS 8

92-42 8-01-92 S

7.7 F

5 Load Drop Per Chicago Load Dispatcher 92-43 8-02-92 F

8.6 B

5 MSIV Repairs 92-44 8-06-92 0

6.7 F

5 Load Drop Per Chicago Load Dispatcher l

l 92-45 8--06-92 S

7.1 F

3 l

92-46 8-08-92 S

7.3 F

5 92-47 8-09-92 F

17.0 B

5 MSIV Room Work 92-48 8-11-92 S

4.4 F

5 Load Drop Per Chicago Load Dispatcher 92-49 8-12-92 S

4.9 F

5 92-50 8-13-92 F

8.6 B

5 MSIV Room Maintenance l 92-51 8-14-92 S

5.7 F

5 Load Drop Fer Chicago Load Dispatcher 92-52 8-15-92 S

g 5.8 F

5 l 92-53 8-16-92 S

8.1 F

5 92-54 8-18-92 S

5.5 F

5 l

l 92-55 8-20-92 S

8.3 F

5 92-56 8-21-92 S

6.4 F

5 92-57 8-22-92 S

6.7 F

5 Turbine Weekly Surveillance 92-58 8-23-92 S

2.9 F

5 Load Drop Per Chicago Load Dispatcher l

92-59 8-25-92 S

2.5 F

5 92-60 8-26-92 S

5.0 F

5 92-61 8-27-92 S

7.0 F

5.

92-62 8-28-92 S

6.0 F

5 l 92-63 8-31-92 S

6.9 F

5 l

l (final)

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4 VI. UNIOUE REPORTING _RE0ulREBERIS The following-items are included.In this report based on prior commitments to

.the commission:

A.

liallLS1um_ReiteLValys_0perAtions -

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.

UDit: One Date: 08/18/92

'/ dives Actated No. & Type _oLAcintion 1-203-3A All manual actuations.

1-203-3B l-203-3C 1-203-30 1-203-3E Plant Condition 1:

Rx. pressure: 922 psig.

Ogicription of-Eveats:

Routine surveillance and Post Maintenance following adjustment of 38 pilot. (QCOS 203-3) 8.

Control Rod Drive _ Scram Timing Data for Units One and_lw_o There was no Control Rod Drive scram timing data for Units One and Two for the reporting period.

,TS14

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. 1 4

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VII. RflufLIBG_lBEORtBIIDE The following information about future-reloads at Quad-Cities Station was requested.in a January 26, 1978, licensing memorandum (78-P4) 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, s

[..

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TS 14 2

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OTP 200-532 Nevision 2 QUAD CITIES REFUELING Octocer 1989 INFORMATION REQUEST 1.

Unit:

41 Reload: __

Cycle:

12 11 2.

Scheduled date for next refueling shutdowa:

9-20-92 3.

Scheduled date for restart following refueling:

12-12-92 4.

Will 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 submitting proposed licensing action and supporti n information:

1.

06/30/92 6.

Important licensing considerations associated with refueling, e.g., new or di'ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel des!gn, new operating procedures:

NONE AT PRESENT TIME.

-7.

The number of fuel-assemblies, a.

Number of assemblies in core:

724 b.

Number of assembiles 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 numoer of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

36M 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 capactty:

2009 APPROVED (finan 14/0395t OCT 3 01989 G.C.O.S.R.

{

1 QTP 300-532 I

Revisfon 2

-QUAD CITIES REFUELINf; October 1989 INFORMATION REQUEST 1.

Unit:

02 Reload:

11 12 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 retumption 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 DETERMLNED.

l 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:

2434 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 capactty: 2009 APPROVED

( f 4 "* "

14/0395t OCT 3 01989 Q.C.O.S.R.

Q VIII. GLQSSARY The following aboreviations which may have been used in the Monthly Report.

-are defined below:

ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI

- American National Standards Institute APRM