ML20042A739

Monthly Operating Repts for Aug 1981

ML20042A739
Person / Time
Site:	Quad Cities
Issue date:	09/01/1981
From:	Tubbs R COMMONWEALTH EDISON CO.
To:
Shared Package
ML20042A732	List: ML20042A731 ML20042A739
References
NUDOCS 8203230730
Download: ML20042A739 (11)

Text

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT AUGUST 1981

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COMMONWEALTH EDISON COMPANY AND l0WA-ILLIN0IS GAS & ELECTRIC COMPANY NRC D0CKET N05. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30

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8203230730 810901

{DRADOCK 05000254 PDR

TABLE OF CONTENTS 1.

Intesduction ll. ' Summary of Operating Experience"

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A.

Unit One B.

Unit Two Ill. Plant of Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.

Amendments to Facility License or Technical Specifications B.

Fac 811 ty 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 Vll.

Refueling Information Vill.

Glossa ry pe

1.

INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe

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net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and towa-1111nois 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 & Contructors.

The condenser cooling method is a closed cycle spray canal, and 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 I and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Uni t I and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Robert Tubbs, telephone number 309-654-2241, extensions 245 and 174.

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

UNIT ONE AU' gust 1-7: The Unit began the reporting period holding a load of 250 MWe, while the search for the source of condenser inleakage continued.

At 1415, a dry gland steam loop seal was discovered and filled, allowing a satisfactory vacuum.

Load was dropped to 90 MWe, to put the off gas recombiner on line.

it was then increased at various rates until it was held at 750 MWe on August 4.

It was then dropped back to 729 MWe to comply with the load for a "C" and "D" heater out of service.

The heaters were restored to service on August 5 and load increased to 750 MWe.

August 6-9: The Reactor scrammed at 0803 on August 6.

The scram was initiated by_a short in the EHC cabinet which caused a Turbine trip.

During the outage the Drywell was deinerted and oil added to the IB Recirculation Pump motor lower bearing.

The Unit was placed back on line at 1655 and load was increased at various rates until a load of 799 MWe was held on August 9 August 10-17:

Load was held at maximum achievable level during this period, except on August 14 and 15 Load was dropped for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to 700 MWe to repair the ci rcui try on number 2 control valve.

Load was then raised back to maximum cn August 15 August 18-19: At 0218, the IB Recirculation Pump motor tube oil low alarm was received and load was dropped to 400 MWe for an hour. The leaking sight glass was replaced this time and load was increased.

On August 19, while the Instrument Mechanics were testing the Reactor Low Level scram switches, a spurious trip occurred on one channel while they were performing the test on the other, resulting in a Reactor scram.

The Unit was put back on line that day and load brought up to 500 MWe for a xenon soak.

August 20-22:

Load was increased on August 20 and 21 at various rates.

Early on August 22, load was held for 20 minutes, while an unexplained increase on the Main Chimney Effluent was investigated. Af ter it was determined that the rise was not due to the load increase, load increase was resumed.

Load was held at 796 MWe at 1500.

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August 23-28:

Load was reduced, due to minimum load conditions, briefly on August 23 Load was then held at the maximum achievable through August 28.

August 29-31:

On August 29, load was dropped to 550 MWe, to enable the l

plant to go on full river operation, and lower the suppression pool l

tempe ra tu re.

Load was held, at this level, until 0745 on August 30, when the Load Dispatcher requested that the Unit return to maximum load.

Maximum load was reached at 1100 on August 31 and the Unit ended the

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reporting period in this condition.

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B.

UNIT TWO August 1-19:

Unit Two began the reporting period holding maximura attainable load.

Load was' held at the maximum over these 19 days except for a drop to 385 MWe on August 2 for li hours due to minimum load conditions.

Due to End of Fuel Cycle Coastdown the maximum load

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dropped f rom 590 to 530 MWe over this period.

August 20-28:

On Augusc 20, load was dropped briefly to 400 MWe when i t was thought that a Drywell ent ry would have to be made.

However, when it was discovered that the entry was not requi red, the Uni t was I

brought back to its maximum attainable load, and remained in that condition through August 28.

August 29-31:

On August 29, load was dropped to 270 MWe to enable the plant to go on full river operation, and lower the suppression pool j

temperature.

Load was held, at this Icvel, until 0800 on August 30, when the Lead Dispatcher requested that the Unit return to maximum load.

Maximum load was achieved at 1400 and was held through the end of the reporting period.

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Ill.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERlHENTS, AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications

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There were no Amendments to Facility License or Technical Speci fications for the reporting period.

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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 and Experiments Requi ring NRC Approval for the reporting period.

D.

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

The headings indicated in this summary include: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENP.NCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13733 1-1705-D The moni tor was out The other 3 rroni tors Calibrated & per-

"D" Main Steam of calibration.

were fully operable formed ST 31 Line Rad and capable of per-Monitor forming as designed.

Q13970 1-305-117 Failed to The rod was still Rebuilt valve with Scram Solenoid operate on scram able to scram during valve kit.

Valve for CRD signal.

full core scram F-12 (22-47) because the back up scram solenoids were op e rab l e.

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6 UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION There were no Corrective Maintenance items for Unit Two for the reporting period.

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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 occurren~ce reporting requirements as set i

forth in sections 6.6.B. I. and 6.6.B.2. of the Technical Speci fications.

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UNIT ONE Th-re were no Licensee Event Reports for the reporting period.

UNIT TWO Licensee Event Report Number Date Title of Occurrence 81-15/03L 8-23-81 2-1601-32C Drywell/

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Suppression Chamber Vacuum Breaker not fully closed e

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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 a

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U" ERAT]NG I' Al /s P U' DR 1 DOCKET i>0.

__ _5fi;fj UNIT Of1F D A T E 5 c p_t e nh o r i 19Pi COMPLETED ItYR ohc r t C l ubh -

TELEPHONE 709-654-22'iXi?4 OPEl:6 TING STATUS 0000 080101

i. Peporting perlod:240n nO3101 Gross hours in reporting period:

744

":. Corrently authorized power level (MWt)- 2511 Max. Depend capucity (MWe-fJe t ) : 7694 Design elettrical rating (NWe-Net): 709 3.

Power 3cvel to which r stricted(if any)(MWe-Net): NA 4.

Reasons for r e s t r i c t.i o n (if any):

This Month Yr,to Date Cunulative S.

Number of hours reactor was critical 731.7 5489.4 66295.7 6.

Reactor reserve shutdown hours Od 0.0 3425.9 7.

Hours aener at or on line 724,9 5463.4 63347.2 3.

Unit reserve shutdown hours.

0.0 n.0 909.2 9.

Gross thernal energy generated (MWH) 1579091 123n2697_

128544745

10. Gross electrical energy centrated(MWH) 509292 an00421 45387328

11. Net electrical energy generated (MWH) 471077 3724029 38502108

1. 2. Rcactor service factor 98.4 95.9 01.2

13. Reactor uvallability factor 98.4 95.9 85.4 Unit - service factor 97.4 93.7 77.6

1. 5. Un i t avallobility factor 97.4 93.7 70.7 1S. Unit capacity factor (Using MDC) 82.3 83.1 A $.5

17. Unit capacity factor (Usina Des.MWe) 80.2 Bi. fi 59.9 1D. Unit forced outaae rate 2.6 2.0 7.4 iV. Shutdowns t,cheduled over next 6 r.onths (1 ppe,Da te,and Duration of each):

{

NA

20. If shutdown at end cf report period,cstinated date of startup IIhe RK P19 be Icwtr than 769 t'.We durig periods of high u-ll:t.t te gerature dte tc the therel ;erfcrettte ef t*ne scrcv congl.

OPER ATi t1G D AT A Pl:PU"T 1,nCl. ET NO.

50-2fS Uf11 T _.

I t.10 DATEN atenber i 1901 20:1PLETED DYRohert C Tub.be T EL'EPl!ONE3 0 9-I-54-224 i X i 74 OPElMTING STATUS 0000 000101

1. Reporting period:2400 083$81_ Gross hours in reporting period:

744

2. Currently authorized power level ( M L' t ) : 2511 Mux. Depend copocity (MWe-Net): 7694 Design electrical rating (MWe-Net): 709 3.

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

Reasons for restriction (if any):

a This Month Yr.to Date Cunulotive.:

'i. Hunber of hours reactor was critical 744.0 5735.6 64568.4 6.

Reactor reserve shutdoun hours 0.0 0.0 2985,8 7.

H.) ors generator on line 744,0 5709.0 61991.0 3.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross toernal energy aenerated(MWH) 1294650 12321861 127522269 in. Gross electrical energy c e n e r a t e d ( MWil) 190990 3976471 40598022 1i Net elec trical enerov a e n e r a t e d ( MUli) 367620 3674702 70031654 2.

R:octor service factor 100.0 98.4 90.0

'. R &.c t o r ovnilobilitu fuctor 10".0 90.4 07.7 14 Unit ucrvice factor 100,0 07.e

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Unit avullability factor 100.0 97.9 7' 7

o Unit conocitv fuctor (Using MDC) 64J

02. D.

61 _.j'.

17. Unit capacitv factor (Using..' s. M ll e )

62 1 79.0 5 9. 'T

10. Unit forced outuge rate 0.0

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19. Shutdouns Scheduled over next 6 nonths (Type,Date,and Durotion each):

1, NA

20. If shutdown at and of report period,estinated date of startup

- 1 tihe RC ny be lever then 769 Pe dtrir; perieds of bigh c aicnt tcgercture he Vo Vhe thern:1 perf ere.cnct of the s;rcy cor,el.

API'F;1D1y 1(

AVEP/WE D AIL Y UNII POWER I LVE l-DOCKET NO, 50-254 Utill

')NE D AT E U c p t e rsb o r-1 1901

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COtirLETED DYRnher 1 C T i' b b e.

TELEP Hf)NE3 0 9-654-224 i X 174 MONTH A tm o s t 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER L EVEL (MWe-Ne t )

(MWe-Ne t )

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2 0h3 17, 731.0 2.

494.2 18, 610.0 3.

622.4 19.

237.n ll.

678.4 20.

475.4 5.

680.8 21.

612.3 6.

309.8 22.

713.8

'7.

502.3 23.

715.2 8

637.2 24.

714.7 9.

725.0 25, 737.0

10. _ _ _

740.9 26.

737.2 11, 741.1 27.

'/36.3 12.

743.3_

28.

736.4 13.

743.3 29.

55 8 14.

701.5 30.

604.5 i '5.

733,0 31.

721.?

16.

737.9 INSTRUCTIONS Cn tMs forn, list the average d3aly Unit power level in N't-Net fcr ec:5 dcy in the re:erting stnth.Cespute to the ne rest kh:le reawatt.

These figures will be estd to olet a crc;h f ar (cch repartir.o nnth. Note that when rani vr. dectrh51e cct':tity is used fcr the riet electrital rating of'the unit,there n:9 be scccsacn; khin the d;ily tvert e pcwcr level excit:t ttt 1

1003 line (or the restricted pcwer level line).In such cases,tne c6ertgt d2ily init pc er catput sheet should bc featncted to typlain the ep;; rent onen:ly e o

API'E.lDI X If AVLil AGE D AILY UNIT POWEP L E 'J E L DOCI'ET NO.

50-PAC tNIT TPO i !?Di D AT E[}e r t e mb e t-

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COMPLElED DYP oher t C Tubbn Tri.E Pil0NE3 0 9-65 4-PP41 X 17 4 fiDNTH A o q in 1 iYJti DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER Ll: VEL (MWe-Net)

(MWe-Net) 1.

556.2 17.

4?$.9 2.

407,0 18.

498.5 3.

551.0 19.

500.3 4.

533J 20.

484.4 5.

527.4 21.

505.7 6.

533,i 22.

495.0 53LJ 23, 490.i 9.

521.6 24.

468.3 9.

515.0 25, 403.3

10. _

515.1 26, 40i.4 11.

514.6 27, 400.2 12.

512.0 20.

470,4 13.

509.3 29, 263.1 14, 500.6 30, 403.5

1. 5.

511.0 31.

401.6 16.

502.5 INGTRUCTIONS On this firm,1:st the overs;e daily unit power level in Ne-Net for ec:b dcy in the reptriinc etr.th.Cmute to the nesrest whole neccwitt.

These fictres will be used to plot a arcph for each rescrtim: rentn Nate that when reticum dipendble cepctity is used for~ the net electrical roting of'the snit,there r2y te itcts.ons den the daily cvert:e pcwer level exceeds thi 1001 line (or the restricted power level line).In sv:h cases,the everc;e daily unit power dutput sheet sh:vid te 1,

footnoted to explain the c;perent enemely

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APPENDIX D QTP 300-S13 50-254 UNIT SHUTDOWNS AND POWER REDUCTIONS RWisIon 5 DOCKET NO.

March 1978 UNIT NAME COMPLETED BY Robert Tubbs 309-654-2241, DATE September 1, 1981 REPORT MONTH AUGUST 1981 TELEPHONE ext. 174 o

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?o DURATION 3{3a-EVENT y8 Q:8 (HOURS) yIy REPORT NO.

NO.

DATE u-g CORRECTIVE ACTIONS / COMMENTS R

81-19 810801 F

0.0 A

5 HD ZZZZZZ Load held at 250 MWe to search for source of condenser inleakage 31-20 810806 F

8.9

'H 3

HA INSTRIJ Reactor scram caused by spurious EHC ground and resultant Turbine trip 81-21 810818 F

0.0 A

5 CB MOTORX Load reduction to add oil to IB Recirculation Pump Motor Lower Bearing 81-22 810819 F

10.6 H

3 IA INSTRU Reactor scram on low water level caused by spurious signal during calibration of other scram channel 81-23 810829 5

0.0 F

5 SA ZZZZZZ Load reduction to allow full river operation to reduce the suppression pool temperature l

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1 APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.60-765 March 1978 UNIT NAME Quad-Cities Unit Tw COMPLETED BY Robert Tubbs ac-o34-zz41, DATE September 1, 1981 REPORT MONTH AUGUST 1981 TELEPHONE ext. 174 4

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yo DURATION EVENT

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(HOURS) y5g REPORT NO.

NO.

DATE u-8 CORRECTIVE ACTIONS / COMMENTS R

81-16 810829 S

0.0 F

5 SA ZZZZZZ Load reduction tc allow full river operation to reduce the suppression pool temperature e

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VI.

UNIQUE REPORTING REQUIREMENTS The following items are inciuded in this report based on prior commi tments to the commission:

A.

Main Steam Relief Valve Operations

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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 were no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

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REFUELING INFORMATION The following information about future seloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) f rom D. E. O' Brien to C. Re'ed, et al., ti t led "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",

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dated January 18, 1978.

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3 QTP 300-532 Revision 1 QUAD-C! TIES REFUELING Harch,1978

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INFORMATION REQUEST

! ycle:

7 1.

Unit:

1 Reload:

6 C

i 9-12-82 (Shutdown EOC6) 2.

Scheduled date for next refueling shutdown:

j 3

Scheduled date for restart folicwing refueling:

12-5-82 (Startup Boc7) 4.

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

No, Plan 10C/R50.59 reloads for future cycles of quad Cities Unit 1.

The review will be conducted in August, 1982.

5 Scheduled date(s) for submitting proposed Jicensing action and supporting.

Information: August, 1982 for 10CFR50 59 related changes r-90 days prior to-t shutdown.

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Important licensing consideratiens associated witb ' refueling, e.g., new or

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

s New fuel designs:

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The number of fuct assemblies.

j a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

820 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 pjanned (

in number of fuel assemblies:

Licensed storage capacity for spent fuel:

1460 s

a.

b.

Planned increase in licensed storage:

None 9

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

• fuel pool assuming the present licensed capacity: September, 1985 T

I' (end of batch discharge capability)

WPPROVED

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APR 2 01978._m C). C1 C). S. R.

QYP 300-S32 Revision 1 QUAD-C! TIES REFUELING Harch 1978 i

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INFORMATION REQUEST 1.

Unit:

2 Reloadt 5

_ Cycle:

6 2.

Scheduled date 'for next refueling shutdown:

8-30-81 (Shutdown EoCS) 3 Scheduled date fer restar't following refueling:

12-20-81 (S ta rtem _ soc 6) 4.

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

No, Plan 10CFR50 59 Reloads for future cycles of quad Cities Unit 2.

The review will be conducted by early August, 1981.

t 5.

Scheduled date(s) for submitting proposed licensing action and supporting In forma tion: Early August, 1981 for 10CFR50.59 related changes es90 days prior to shutdown.

6.

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

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

New Fuel Design:

'1.

Barrier Fuel i

2.

Control Ceil Core l

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7 The number of fuei-a.ssemblies.

a.

Number of assemblici in core:

774 a

b.

Number of assembliev in spent fuei poolg 672 L

8.

The present licensed spent fuel pool storage capacity and the size of any Increase in licensed storage capacityt that has been requested or is planned

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in number of fuel assemblies:

a.

Licensed storage capacity for spent fuci:

1460 b.

Planned increase in licensed storage:

None 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the pr'esent licensed capacity:

September, 1984 t

(End of batch discharge capability)

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. A' P P R O V E D

- APR 2 01978 (3.c:.c).55.Ft.

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

ACAD/ CAM Atmospheric Containment Atnospheric Dilution / Containment

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Atmospheric Monitoring ANSI American National Standards Institute Average Power Rar.ge Monitor APRM ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor Inservice inspection 151 LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant injection Mode of RHRS LPRM Local Power Range Moni tor 2

MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio PPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PC10MR Precondi tioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation C9pling System RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Worti> Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Costrol SDC Shutdown Cooling Mode of RHRS SDV Scram Dis' charge Volume SRM Source Ra,nge Monitor TBCCW Turbine Building Closed Cooling Water System TlP Traveling incore Probe TSC Technical' Support Center t

t 1

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