ML20084M509

Monthly Operating Repts for Apr 1984

ML20084M509
Person / Time
Site:	Quad Cities
Issue date:	04/30/1984
From:	Kalivianakis N, Kimler D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-84-146, NUDOCS 8405150401
Download: ML20084M509 (20)

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 i

MONTHLY PEREDRMANCE REPORT APRIL 1984 COfMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254. AND 50-265 LICENSE NOS, DP."-29 AND DPR-30 r

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8405150401'840430 PDR ADOCK 05000254 R

PDR

o TABLE OF CONTENTS I,

. Introduction II, Summary of Operating Experience

'A.

Unit One B.

Unit Two

III, Plant or Procedure Changes, Tests, ExperLnents, and Safety Related Maintenance A,

Amendments to Facility License or Technical Specifications B. - Facility or Procedure Changes Requiring NRC Approval C.

Tests and,Experknents 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 i

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I, INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling

-Water Reactors, each with a Maximum Dependable Capacity of 769 MWe 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 Bolling 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, i

1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor critica11tles 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 coup 11ed by Becky Brown and Dave Kimler, telephone number 309-654-2241, extensions 127 and 192.

g' 11.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One Unit One remained shutdown througnout the month for End of Cycle Seven Refueling and Maintenance.

B.- Unit Two April 1-21: Unit Two began the month dropping load to 700 MWe for weekly Turbine tests. At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> the unit began a normal load increase to full power. At 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />, on April 8, load was again dropped to 700 MWe for Turbine tests. At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> the unit began a normal load increase to full power. At 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, on April 15, load was dropped to 700 MWe for Turbine tests. At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> the unit began a normal load increase to full power. At 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, on April 17, the unit dropped load to 700 MWe in preparation for a Feedwater Regulating Valve changeover due to a failed 2B Feedwater Regulating Valve. At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, on April 18, the unit began a normal load increase to full power.

April 22-30: At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, on April 22, load was dropped to 700 MWe to perform weekly Turbine tests. At 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> the unit began a normal load increase to full power. At 2l00 hours, on April 26, the unit began dropping load for shutdown procedures. The unit was being shutdown for a scheduled Maintenance Outage. At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, on April 27, the Turbine was tripp'ed. At 0523 hours0.00605 days <br />0.145 hours <br />8.647487e-4 weeks <br />1.990015e-4 months <br /> the mode switch was placed in SHUTDOWN and a full Reactor scram was initiated.

The unit was in Cold Shutdown at 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br /> on April 27 l

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'A' III.

PIANT OR PROCEDURE CHANGES, TESTS,' EXPERIMENTS, AND SAFETY RE1ATED MAINTENANCE A.

Amendments to Facility License or Technical Specifica-tions On February 24, 1984, the NRC issued Amendment 87 to License DPR-29 and Amendnent 82 to License DPR-30.

These Amendments establish requirenents for restora-tion of Main Steam Relief Valve Position Indication prior to startup of a unit that has been in a Cold Shutdown state for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> dura t ion.

B.

Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Unit One and Unit Two during the reporting period.

This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Hal functions, Results and Effects on Safe Operations, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER' 0F ON ACT1014 TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q33590 Diesel Generator Motor was imbalanced. The unit was in a Rotor was balanced.

Cooling Water refuel ing outage, Pump Motor 1-3903 and the 1/2 Diesel Generator was operable.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

-W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION.

SAFE OPERATION PREVENT REPETITION Q33610 ATWS Reactor The malfunction was The failure of the This problem was Low-Low Level the failure of contacts T1 and M1 contacts detected during ATWS Trip Relay T1 and M1 of relay disabled the Div. ll Analog Trip System KID to consistently Low-Low Level Reactor Functional Test, make a proper Recirculation Pump Qls 68-2.

The connection. The root trips. The Div. I malfunctioning relay cause of the failure trips were tested was replaced.like-could not be satisfactorily, for-like. This is determined.

therefore, the considered an isolated consequences of the event and no further occurrence were corrective action is mininal.

deemed necessary.

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.o IV, LICENSEE EVENT REPORTS 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.

UNIT ONE

' Licensee Event Report Number Date Title of Occurrence 84-5 4-14-84 Linear Indications on Recirculation System Welds UNIT TWO There were no Licensee Event Reports for the reporting period for Unit Two.

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DATA TABUIATIONS 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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s' OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEMAY 4 1984 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 040184 L.

Reporting period 2400 043084 Gross hours in reporting period 719 2.

Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA 4.

Reasons for restriction (if any):

This Month Yr.to Date Cunulative

5. Nunber of hours reactor was critical 0.0 1562.1 85117,7 6.

Reacter reserve shutdown hours 0,0 0.0 3421,9 7.

Hours generator on line 0,0 1561,2 81909.1 8.

Unit reserve shutdown hours.

0,0 0,0 909.2 9.

Gross thermal energy generated (MWH) 0 3659732 168766438

10. Gross electrical energy generated (MWH) 0 1213148 54471764

11. Het electrical energy generated (MWH)

-577 1152373 50758340 L2. Reactor service factor 0,0 53.8 81.1

13. Reactor ovallobility factor 0,0 53,8 84.4

14. Unit service factor 0,0 53,8 78.0

15. Unit ovallobility factor 0,0 53,8 78,9

16. Unit capacity factor (Using MDC)

,1 51,6 62.9 w

L7. Unit capacity factor (Using Des.MWe)

,1 50.3 61.3

18. Unit forced outage rate 0.0 0,0 6,1

19. Shutdowns scheduled over next 6 months (Type, Dote,and Duration of each):

20. If shutdown at end of report period,estinated date o f s t or t u p _]-10;jh____c

• The MDC nay be lower than 769 MWe during perleds of high anblent tenperatere due

___ m C'n thernal perfn of the spray canel.

i OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEMAY 4 1984 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241x192 OPERATING STATUS 0000 040184

1. Reporting period:2400 043084 Gross hours in reporting period:

719

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA 4.

Reasons for restriction (if any):

This Month Yr.to Date Cumulative 5.

Number of hours reactor was critical 628.4 1617.9 79535.4 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 628.0 1532.3 76742.1

8. Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thermal energy generated (MWH) 1550038 3527321 158909409

10. Gross electrical energy generated (MWH) 506848 1148581 50584361

11. Het electrical energy generated (MWH) 482542 1090854 47424914

12. Reactor service factor 87.4 55.7 76.5

13. Reactor availability factor 87.4 55.7 79.3

14. Unit service factor 87.3 52.8 73.8

15. Unit ovallobility factor 87.3 52.8 74.4

16. Unit copocity factor (Using MDC) 87.3 48.9.

59.3

17. Unit capacity factor (using Des.MWe) 85.1 47.6 57.8

18. Unit forced outage rate 0.0 6.6 8.6

19. Shutdowns scheduled over next 6 nonths (Type,Date,ond Duration of each):

20. If shutdown at end of report period, estimated date o f s t ar t u p

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• The MDC not be lower than 769 MWe during periods of high anbient temperature due to the thernal perfernance of the sprea canal.

$lRWFICIAL COlFAlff ISBERS ARE USD IN THIS REPORT APPENDIN B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEMAY 4 1984 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241xi92

HONTH Aor 11 1984

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

(MWe-Net) 1.-

-3,0 17.

-4.8 2.

-2.8 18.

-4.9 3.

-3.0 19.

-4.7 4.

-3,0 20.

-5.1 l

5.

-3.1-21.

-5.0

-6.

-3.1 22.

-4.8 7.

-3.0 23.

-5.7 8.

-3.0 24.

-6.3

-3.3 25.

-6.2

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10.

-4.7 26.

-5.4 11 ~..

-4.8 27.

-4.0 12.

-4.8 28.

-3.9 29.

-3.0 13.

' -4.9 L4.

-4.8 30.

-4.6 15.

-4.6 16..

-5.0

-INSTRUCTIONS

'On this forn, list the overage daily sait power level in leie-Net for each day in the reporting nenth Compete to the neerest uhelt negewett.

These figures will be esed to plot a graph for each reperting nenth. Note that when no inen dependable capacity is used for the net electrical rating of the unit there ney be occasions when the daily average puer level cxceeds the 111111ae (or the restricted pwer level line),In such cases,the average daily enit power setpet sheet sheeld be festseted to explain the apparent enenely -

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1. REFFICIAL COlFAIN lluMIERS ARE USED IN THIS REPORT -

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 u

UNIT TWO DATEMAY 4 1984 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241x192 MONTH April 1984

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

(MWe-Net)

L.

722.3 17.

738.7 2.

781.8 18, 758.9

.3..

783.9 19.

781.0 4.

773.2 20, 792.5-5.

-787.8 21, 787.3

'6.

786 i 22, 750.2

- 7.

778.3 23.

780.6

.8.

766.5 24.

786.9

'9.

777.4 25.

777.0 LO.

785.7 26.

76*/.4 ii.

781.8 27, 54.0 s

12, 776.2 28.-

-6.6 513.

776.7 29.

-6.2 14. -

780.2 30.

-6.4 15.

769.2 16.-

778.8 INSTRUCTIONS i

On this forn, list the everage, daily snit power level in ille-tiet for each day in the reperting nenth Compete to the c r est uhele negemett.

These figeres will be esed to plot a graph for each reporting nenth, liete that when notinen dependable copecity is eggf for the net electrical rating of the sait there ney be occasions when the daily overage power level exceeds the

- isu line (or the restricted power level line),In suh cases,tne everage daily snit peuer setput sheet should be

.festnoted to esplein the apperent onenely

M M

M M

M M

M EWE W'E W

M M

El M

M M

M M

M ID/5A APPENDIX D QTP 300-S13 UNIT SillrIDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. J0-2c;4 August 1982 UNIT NAME _ Quad-Cities Unit _1 COMPLETED BY J. Kimier DATE Jay 4.1984 REPORT HONTil APRIL 1184 TELEPil0NE 309-654-2241 N

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EVENT o"

DURATION d

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u NO.

DATE (IlOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS oo I

84-14 840306 s

719 C

1 RC FUELXX Unit One remains shutdown for End of Cycle Seven Refueling and Maintenance APPROVED AUG 1 G 1982

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o ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCK'ET NO. _E50-26c; August 1982 UNIT NAME _ Quad-Cities _2 COMPLETED BY _p. Kimler DATE May 4. 1984 REPORT HONTil APRIL 1984 TEl.EPIIONE 309-654-2241 5

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DURATION d

EVENT gu a

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No.

DATE (IIOURS)

REPORT NO.

CORRECTIVE ACTIONS /CONMENTS ca 84-13 840401 S

0.0 B

5 HA TURBIN Reduced load for weekly Turbine tests 84-14 840408 5

0.0 B

5 HA TURBIN Reduced load for weekly Turbine tests 84-15 840415 5

0.0 B

5 HA TURBIN Reduced load for weekly Turbine tests 85-16 840417 F

0.0 A

5 CH VALVEX Reduced load due to failed Feedwater Regulating Valve 85-17 840422 S

0.0 B

5 HA TURBIN Reduced load for weekly Turbine tests 85-18 840427 S

91.0 B

1 HF VALVEX Shutdown for repair of 2A Circulating Water Pump Discharge Valve APPROVED AUG 1 G 1982

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VI.

UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior comml'tments to the commission:

A.

MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B.

CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

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VII, REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D E, 0.'Brien to C, Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

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'1 QTP 300-S32 Rnvision I h.

I QUAD-CITIES REFUELING tiarch 1978 e

INFORMATION REQUEST 1.

Unit:

Q1 Reload:

7 Cycle:

8 Refueling Outage 2.

Scheduled date for next refueling shutdown:

Currently in Progress 3

Scheduled date for restart following refueling:

7-30-84 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: Yes.

Preparatory Technical Specification changes have been submitted to include MAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.

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

Technical Specification change has been submitted February 21, 1984.

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:

1)

All new fuel assemblies will be GE78-type (barrier clad, extended exposure design).

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A generic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

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3)

Four Barrier Lead Test Assemblies will be re-inserted to gather i

information on the effects of extended exposures.

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7 The number of fuel assemblies.

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a.

Number of assemblies in core:

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b.

Number of assemblies in spent fuel pool:

2454 o

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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:

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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 f

spent fuel pool assuming the present licensed capacity: 2003

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WPPROVED e APR 2 01978 3

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Rsvision 1 I

QUAD-CITIES REFUELING tlarch 1978

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INFORMATION REQUEST t'

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Unit:

Q2 Reload:

7 Cycle:

8 s

2.

Scheduled date for next refueling shutdown:

3-18-85 l

3 Scheduled date for restart following refueling:

5-26-85 f'

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Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

E Not as yet determined.

a.

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

January 18, 1985, if licensing action required.

!T 6.

Important licensing considerations associated with refueling, e.g., new or y'

' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

A 1)

All new fuel assemblies will be GE7B-type (barrier clad, extended c.

exposure design).

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A generic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

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The number of fuel assemblies.

a.

Number of assemblies in core:

724 c

b.

Number of assemblies in spent fuel pool:

412 i

8.

The present licensed spent fuel pool storage capacity and the size of any

.n 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:

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

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spent fuel pool assuming the present licensed capacity: 2003

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WPPROVED APR 2 01973 Q.C.C.S.R.

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VIII, GLDSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:

ACAD/ CAM Atmospheric Containnent Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute Average Power Range Monitor APRM ATWS Anticipated Transient Without Scram BWR Bolling Water Reactor Control Rod Drive CRD Electro-Hydraulic Control System EHC Bnergency Operations Facility EOF GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System Integrated Primary Containment Isak Rate Test IPCIRT IRM Intermediate Range Monitor Inservice Inspection IS L Licensee Event Report LER Local Leak Rate Test LLRT Low Pressure Coolant Injection Mode of RHRS LPCI LPRM Local Power Range Monitor Maximum Average Planar Linear Heat Generation Rate MAPLHGR MCPR Minimum Critical Power Ratio MFLCPR Maximun Fraction Lhniting Critical Power Ratio MPC Maximum Permissible Concentration Main Steam Isolation Valve MS IV NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCI Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Water System RBCCW RBM Rod Block Monitor Reactor Core Isolation Cooling System RCIC RHRS Residual Heat Removal System Reactor Protection System RPS Rod Worth Minimizer RRM Standby Gas Treatment System SBGTS SBLE Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center t

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N Commonw alth Edison O

) Outd CitiIs Nuct:ar Poveer Station m ? 22710 206 Avenue North e#

Cordova, Illinois 61242 Telephone 309/654-2241 s

NJK-84-146 May 1, 1984 Director, Of fice of Inspection & Enforcenent United States Nuclear Regulatory Commission Washington, D C,

20555 Attention: Document Control Desk Centlemen:

Enclosed for your information is the Monthly Perfonnance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of April 1984.

Very truly yours, t

COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION l

.f N

J, Kallvianakis l.

Station Superintendent I

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i Enclosu re i-f

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