Text

Monthly Operating Repts for Feb 1986
	ML20141P048
Person / Time
Site:	Quad Cities
Issue date:	02/28/1986
From:	Kronich C, Tamlyn T; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	TKT-86-24, NUDOCS 8603180488
	Download: ML20141P048 (22)
	v • d • e

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l QUAD-CITIES NUCLEAR POWER STATION i

UNITS I AND 2 l

MONTHLY PERFORMANCE REPORT FEBRUARY 1986 l

COMMONWEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 l

LICENSE NOS. DPR-29 AND DPR-30 i

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TABLE OF CONTENTS I.

Introduction II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure thanges, Tests, Experiments, and Safety Related Maintenance A.

Amendments to Facility License or Technical Specifications l

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 l

B.

Control Rod Drive Scram Timing Data l

VII.

Refueling Information VIII.

Glossary l

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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 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 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 Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 2240 and 2157.

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One February 1-28 Unit One remains shutdown for the End of Cycle Eight Refueling and Maintenance Outage for the entire month of February.

B.

Unit Two February 1-7 Unit Two began the month of February on Economic Generation Control (EGC). On February 1, at 0114 hours0.00132 days 0.0317 hours 1.884921e-4 weeks 4.3377e-5 months , the unit was taken off EGC to perform Turbine surveillances. EGC operation was returned to at 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months . EGC was tripped on February 4, at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months , and load was increased to full power. At 0715 hours0.00828 days 0.199 hours 0.00118 weeks 2.720575e-4 months load was dropped to 795 i

MWe and the unit was returned to ECC.

At 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months EGC was tripped and load was increased to full power.

On February 5, at 0145 hours0.00168 days 0.0403 hours 2.397487e-4 weeks 5.51725e-5 months , load was dropped to 799 MWe and the unit was placed on EGC. At 0620 hours0.00718 days 0.172 hours 0.00103 weeks 2.3591e-4 months the unit was taken off EGC, and load was increased to full power.

Load was dropped to 800 MWe on February 6, at 0225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months , and at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months the unit was placed on EGC.

At 0710 hours0.00822 days 0.197 hours 0.00117 weeks 2.70155e-4 months the unit was taken off EGC and load was increased to full power. At 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months a load drop was initiated at 25 MWe/hr due to GSEP Unusual Event -- HPCI and RCIC Room Cooler Out of Service. The GSEP Event was terminated at l

0325 hours0.00376 days 0.0903 hours 5.373677e-4 weeks 1.236625e-4 months on February 7, and at 590 MWe.

At 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months a normal load i

increase to full power commenced. At 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months 826 MWe was reached, l

February 8-28 On February 8, at 0940 hours0.0109 days 0.261 hours 0.00155 weeks 3.5767e-4 months , a load drop to 698 MWe was initiated to return.ontrol Rod D-3 to service. At 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months a normal increase to l

full power began. At 2140 hours0.0248 days 0.594 hours 0.00354 weeks 8.1427e-4 months the unit was placed on EGC.

On February 10, at 0325 hours0.00376 days 0.0903 hours 5.373677e-4 weeks 1.236625e-4 months , the unit was taken off of ECC for surveillances.

At 0540 hours0.00625 days 0.15 hours 8.928571e-4 weeks 2.0547e-4 months the unit was returned to EGC, until 0645 hours0.00747 days 0.179 hours 0.00107 weeks 2.454225e-4 months , when the unit was brought to full power. On February 12, at 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months , load was dropped to 800 MWe and then placed on EGC.

l On February 14, at 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months , the unit was taken off of EGC for surveillances.

EGC operation was returned at 0055 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months on February 15.

At 1545 hours0.0179 days 0.429 hours 0.00255 weeks 5.878725e-4 months the unit was taken off of EGC, and held load at 800 MWe.

l At 1645 hours0.019 days 0.457 hours 0.00272 weeks 6.259225e-4 months the unit returned to EGC.

On February 17, at 0405 hours0.00469 days 0.113 hours 6.696429e-4 weeks 1.541025e-4 months , the ur.it was taken off of ECC, and load was increased to full power.

On February 18, 0238 hours0.00275 days 0.0661 hours 3.935185e-4 weeks 9.0559e-5 months , the unit was returned to EGC.

On February 19, at 2245 houts, the unit was taken off of ECC, and load was increased to

B.

Unit Two (continued) i l-full power..On February 21, at 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months , a unit shutdown commenced

-for a scheduled Maintenance Outage. On February 22, at 0245' hours, the unit was manually scrammed and remained shutdown for the remainder'of t

l February.

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III.

PLANT OR PROCEDURE CHANGES, TESTS. EXPERIMENTS, AND SAFETY RELATED MAINTENANCE I

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A.

Amendments to Facility License or Technical Specifications On January 14, 1986, the NRC issued Amendment 88 to i

License DPR-30 and Amendment 91 to License DPR-29. These l

amendments establish that prior to entering EGC and once l

per shift while operating ECC, the ECC operating parameters will be reviewed for acceptability.

B.

Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC

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approval for the reporting period.

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C.

Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval i

for the reporting period.

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Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units One and Two i

j during the reporting period. This summary includes the I

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

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UNIT 1

MINTENANCE SLRAIARY t

CAUSE RESULTS & EFFECTS l

W.R.

LER OF ON ACTION TAKEN TO l

IMEER IMEIER COIF 0ENT M LFisiCTION SAFE OPERATION PREVENT EPETITION l

Q47089 Jet Pump Beam Slow progressing The stress corrosion The cracked beam bolt Bolt #13 stress corrosion cracking eventually caused assembly was replaced.

cracking in the a crack in the #13 Jet Surveillances moaitor Jet beam segment of Pump beam bolt. The crack Pump performance, and the I

the Jet Pump was discovered during a assenblies are ultra-assembly.

refueling outage. No affect sonically tested during on operation.

refuel outage.

Q47731 1-1743B Fuel Burned out The monitor failed down-The transistor was Pool Radia-transistor in scale, which gave a Control replaced like for like, tion the monitor.

Room alarm. Channel

'A' The sensor convertor and Monitor was normal.

the indicator trip unit were recalibrated.

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i UNIT __2 MAINTENANCE SIAAAARY l

CAUSE RESULTS & EFFECTS 5.R.

LER OF ON ACTION TAKEN TO i

IRAEER NLAEBER C0F00ENT MALFlalCTION SAFE OPERATION PREVENT REPETITION l

l Q47600 2-1001-16A RHR The breaker While surveillance testing, Adjusted the breaker's Loop

'A' Heat close limit the breaker tripped while close limit actuation, Exchanger By-setting was opening the valve. Normal and cycled the valve pass Valve out of proper operating position is open.

three times.

limits. Breaker tripped pre-maturely.

Q47601 2-1001-37B RHR The breaker While surveillance testing, The open contactor was open contactor the valve opened but would replaced like for like, did not not close. Operating and the valve was completely position is closed.

successfully stroked and close, thus not tined.

completing the close logic, preventing valve

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I IV.~

LICENSEE EVENT REPORTS t

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 l

l in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.

t UNIT ONE Licensee Event i

Report Number Date Title of Occurrence l

l 86-07 2-3-86 1/2 Diesel Generator l

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86-09 2-11-86 Reactor Scram While f

Shutdown From Scram i

Discharge Volene l

High Level 86-10 2-11-86 Group II & Group III t

I Isolations During HFA Relay Replacement I

86-11 2-14-86 Bus 13-1 4KV Under-voltage Relay Out of Tolerance 86-12 2-21-86 1/2 'A' Standby Gas Treatment Auto Start l

Due to Loss of Power to Radiation Monitors

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There were no Licensee Event Reports for Unit Two for the reporting period.

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V.

DATA TABULATIONS 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 l

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l OPERATING DATA REPORT DOCKCT NO.

50-254 UNIT ONE I

DATEMARCH 3 1986 1

COMPLETED BYCAROL L KRONICH i

TELEPHONE (309) 654-2241 OPERATING STATUS 0000 020186

i. Reporting period 2400 022886 Gross hours in reporting period 672 l

2. Currently authorized power level (MWt): 2511 Hox. Depend capacity

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(HWe-Net): 769* Design electrical rating (MWe-Net): 789 i

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

4. Reasons for restriction (if any):

l This Month Yr.to Date Cumulative I

5. Number of hours reactor was critical 0.0 120.0 96781.4 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 I

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7. Hours generator on line 0.0 120.0 93399.5 l

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8. Unit reserve shutdown hourn.

0.0 0.0 909.2 1

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9. Gross thernal energy generated (MWH) 0 240405 195205642 i

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10. Gross electrical energy generated (HWH) 0 80622 63199993

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11. Het electrical energy generotrd(MWH)

-2530 72210 59090743 4

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12. Reactor service factor 0 0 0.5 80.0 l

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13. Reactor avullability factor 0.0 0.5 02.0

14. Unit service factor 0.0 0.5 77.2 J

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15. Unit avo11ob111ty factor 0.0 0.5 77.9 l

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16. Unit capacity factor (Using MDC)

.S 6.6 63.5 1

17. Unit capacity factor (Using Des.HWe)

.5 6.5 61.9 i

18. Unit forced outage rate 0.0 0.0 5.9

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

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20. If shutdown at end of report p e r i o d, e s t ima t e d d a t e o f s t ar t u p

,,3-2j-g6,,,,,,, j y

t 8The IWC not be lower then 7H late dwing periods of high emblent tempere: ore doe to the thersel perfernance of the spret cenet, i

8WWFICIAL C8FAllt IRAGEll ARE UIES IN INil REPORT I

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO DATEtiARCH 3 1906 COMPLETED LtYCAROL L KRONICH TELEPHONEf309) 654-2241 OPERATING STATUS 0000 020106 L. Reporting period 2400 022006 Gross hours in reporting period 672

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 506,0 12,42,6 92510,3 6.

Reactor reserve shutdown hoorn 0.0 0,0 2905,0 7.

Hours generator on line 506.0 1239,2 09536.0 8.

Unit reserve shutdown hours.

0,0 0,0 702.9 9.

Gross thermal energy generated (MWH) 1205019 2942256 189051279

10. Gross electrical energy generated (MWH) 395032 969059 60305041

11. Het electrical energy generated (MWH) 377921 926094 56000353.

12. Reactor service factor 75.4 07,0 77.0

13. Reactor availability factor 75.4 07,0 79.5

14. Unit service factor 75.4 07.5 74,6

15. Unit ovallobility factor 75,4 07.5 75.1

16. Unit capacity foctor (Using MDC) 73,i 05,0 61.5

17. Unit capacity factor (Using Des.MWe) 71 J OM 59.9

10. Unit forced outom rate 0,0

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

20. If shutdown at end of report p e r i o d, e s t ina t e d d a t e o f s t ar t up __1-k36______

Uhe MBC nor te lower then 769 MWe during parteds of high edient tenparatere det to the thernal perfernance of the sprey canel.

PUN 0FFICIAL COMPWY NUMIERS ME UKl IN THIS REPORT l

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEMARCH 3 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 r

MONTH Februarv 1986 1)AY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(HWe-Net) 1.

-3,0 17.

-3.0 2.

-2.9 10.

-3.1 3.

-3,0 19.

-3.0 4.

-3.i 20.

-3.2 5.

-3.2 21.

-3.1 6.

-3.7 22.

-3.5 7.

-3.7 23.

-3.7 8.

-3.7 24.

-3.5 9.

-3.8 25.

-3.4 l

10.

-3.4 26.

-3.4 I

11.

-3.0 27.

-3.3 4

12.

-2.9 20.

-4.3 13.

-3,0 14.

-3.2 15.

-3.0 16.

-3.0 INSTRUCTIONG D this fwn, list the enrega dell mit puer lawl in leia-ilet for each der in the reporting meth.Cupete to the t

neerest whole negemett.

Thees figeres will h esed to plot a graph for each reportine senth, liete that when nesian deperdelle cepetite is eged for the not electrical reting of the snit there met k 6ccesius when the dellt eNrege Soutr level (Iceeds the im line (or tk restricted pouer lewl line),In such ceses,the everage dellt enit puer eetpet sheet should be fwtnoted te esplein the apperent eneaelp 1

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i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEMARCH 3 1986 COMPLETED BYCAROL L KRONICH TELEPHONE (309) 654-2241 i

NONTH Februarv 1986 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net) i.

736 i 17.

791.6 2.

739.8 18.

724.6

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3.

757.4 19.

750.0

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4.

752.0 20.

765.2 5.

747.0 21.

721.0 6.

748.9 22.

.6 7.

774.0 23.

-12.1 l

B.

746.4 24.

-8.3 9.

740.5 25.

-7.3 10.

764.0 26.

-7.3 11.

797.0 27.

-6.9 L2.

763.5 28.

-7.0 13.

738,i l

l 14.

716.8 15.

766.5 j

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717.4 INSTRUCTIONS On this f list the eserega dellt init pesar level in IIIe-tiet for each det in the reporting nenth. Compete to the neerest I negeugtt.

l These figures ulIl he seed to plot a graph for each repwtine month. liste that uhen mainen dependeble cepecite is used for the net electrical retine of the snit there not be 6ccesiens uhen the delly eserege peuer level esteeds the 1981 line ter the restricted peusf level line),In soch cases,the escrege dell unit pesar eetpet sheet shoold be t

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VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments 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 q

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

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requested in-a January 26, 1978, Ilcensing memoranduc (78-24) from D. E.

4 0'Brien to C. Reed, et.'a1., titled."Dresden, Quad-Cities, and Zion

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. Station--NRC Request for' Refueling Information", dated January 18, 1978.

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QTP 300-S32 Revision 1 QUA5-CITIES REFUELING

-naYch" 197o lNFORMATION REQUEST 1.

Unit:

Q1 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

9-14-87 3

Scheduled date for restart following refueling:

3-29-86 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment: YES. A ROUTINE MAPLHGR AMENDMENT HAS BEEN SUBMITTED AS A PREPARATORY CHANGE TO ALLOW A 10 CFR 50.59 REVIEW OF THE RELOAD. TECHNICAL SPECIFICATION CHANGE TO ALLOW HAFNIUM ABSORBER MATERIAL HAS BEEN SUBMITTED.

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

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:

A) USE OF 8 ASEA-ATOM CONTROL BLADES CONTAINING HAFNIUM.

B) CONTINUED USE OF TWO BARRIER LEAD TEST ASSEMBLIES.

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1894 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 0

b.

Planned increase in licensed storage:

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 XPPROVED APR 2 01978 ca. <. c>. !s. rt.

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r-QTP 300-532 Revision 1

--QtlAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

10-13-86 3

Scheduled date for restart following refueling:

1-19-87 4.

Will refueling or resumption of operation thereaf ter 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:

SEPTEMBER 19, 1986, IF REQUIRED.

6.

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

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

NONE PLANNED AT PRESENT TIME.

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

838 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: 2003 WPPROVED APR 2 01978 C). c:. C). !B. Ft.

,-...----,,v.-

r VIII. GLOSSARY The following abbreviations 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 Average Power Range Monitor ATHS Anticipated Transient Without Scram Bolling Water Reactor BWR CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan High-Efficiency Particulate Filter HEPA HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice I1spection Licensee Event Report LER LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation Preconditioning Interim Operating Management Recommendations PCIOMR RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System Reactor Protection System RPS RWM Rod Worth Minimizer Standby Gas Treatment System SDGTS Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System Traversing Incore Probe TIP Technical Support Center TSC

r o

Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 TKT-86-24 March 3, 1986 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washin9 on, D. C.

20555 t

Attention: Document Control Desk Gentlemen:

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 February, 1986.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR OWER STATION T. K. Tamlyn Services Superintendent bb Enclosure W

f i i

- 1

ML20141P048

Text

SUMMARY

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