ML20236C416

Monthly Operating Repts for Feb 1989 for Quad Cities Nuclear Power Station

ML20236C416
Person / Time
Site:	Quad Cities
Issue date:	02/28/1989
From:	Deelsnyder L, Robey R COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
RAR-89-10, NUDOCS 8903220137
Download: ML20236C416 (25)

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' QUAD-CITIES NUCLEA' R.' POWER' STATION

UNITS.1-AND 2-MONTHLY PERFORMANCE REPORT 1

FEBRUARY, 1989-

. COMMONWEALTH <EDIS0N COMPANY AND l

. IOWA-ILLIN0IS GAS &.ELECTRICLCOMPANY NRC. DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 1

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0027H/00612 8903220137 890228 IE S

PDR ADOCK 05000254 11 R

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i 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 Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations 5

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 0027H/0061Z

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-INTRODUCTION!

Quad-Cities Nuclear Power-Station is composed of two Boiling 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 El'ectric 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, l

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 Lynne Deelsnyder and Verna Koselka, telephone number 309-654-2241, extensions 2185 and 2240.

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SUMMARY

'0F OPERATING EXPERIENCE A.

Unit One Unit One b'egan the month of-February operating in Economic Generation At 1612 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.13366e-4 months <br />, Control (EGC). LThe unit remained in EGC until February 3.

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. EGC was tripp'ed and a load : increase to full power was taken. At 1637 hours0.0189 days <br />0.455 hours <br />0.00271 weeks <br />6.228785e-4 months <br />, 1

823 MWe was achieved; Full load was. held.until February 4.

At 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />, power levels were. adjusted.and the unit was placed in EGC.

The unit operated in EGC until February 5 when at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> EGC was tripped due to the 1A Recirculation Pump experiencing sporadic flow oscillations. At-1740 hours, a load increase to-full power was'taken~at the request of the' Chicago Load Dispatcher. At 1842 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.00881e-4 months <br />, 820 MWe was achieved. Full load was held until February 9.

During this period, the 1A Recirculation MG. Set 1-Scoop Tube was-lockedjup.to prevent further flow oscillations. At'2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, l:

a load reduction to 700 MWe was taken with' control rods and recirculation pumps. The 1A Recirculation Scoop' Tube was reset. ~ Power levels were held constant until February 10..At 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, a load increase to full power was taken. At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />, 823 MWe was' achieved.

On February 11, power levels were adjusted and the. unit waslplaced in EGC. The unit remained in EGC or operated near full power with minor interruptions to perform:

weekly surveillance until February 17.

At 0536 hours0.0062 days <br />0.149 hours <br />8.862434e-4 weeks <br />2.03948e-4 months <br />, the unit was taken off EGC and a load increase was taken to 820 MWe.

At 1140 hours0.0132 days <br />0.317 hours <br />0.00188 weeks <br />4.3377e-4 months <br />, a power reduction.to 640 MWe.was taken to change over MG set oil pumps. At 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br />, a load-increase to full power was taken with control-rods and recirculation pumps. On February 18, at 0805 hours0.00932 days <br />0.224 hours <br />0.00133 weeks <br />3.063025e-4 months <br />, the unit was placed.in EGC.- Unit One remained in EGC until February 21.

At 0536 hours0.0062 days <br />0.149 hours <br />8.862434e-4 weeks <br />2.03948e-4 months <br />, EGC was tripped and a load increase to full power was taken with control rods.

Power icvels were held constant while repairs were~made to a control rod-drive that was taken out of service.

On February 23, power levels were adjusted and the unit was placed in EGC at 0218 hours0.00252 days <br />0.0606 hours <br />3.604497e-4 weeks <br />8.2949e-5 months <br />. The unit remained in EGC until February 26.

At 1028 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91154e-4 months <br />, EGC was tripped and a load increase was taken to. full power and held while Traversing In-Core Probe Sets'were performed.

On. February 27, at-2330 hours, power levels were adjusted and the unit was placed in EGC. The unit remained in EGC until February 28.

At 0408 hours0.00472 days <br />0.113 hours <br />6.746032e-4 weeks <br />1.55244e-4 months <br />, a power reduction was taken to 650 MWe to take the 1A Water Cooler'out of service for repairs.

The unit remained at 650 MWe for the rest of the month.

B.

Unit Two i

Unit Two began the month of February operating in Economic Generation-Control $

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- The unit remained in EGC until February 3.

At 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />, EGC was tripped _

j and a load increase to full power was taken. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, a power reduction:

J was taken to 600 MWe to perform control rod drive scram timing. On February 4, j

at 1218 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.63449e-4 months <br />, scram timing was completed. At 2009 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.644245e-4 months <br />, a power reduction-q to 300 MWe was taken for an entry into the drywell to add. oil to the 2B Recir-culation Pump Motor lower lube oil reservoir. At 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> the entry was..

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completed and a load increase to full power was begun with recire.ulation pumps and control rods. At 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />, 824 MWe was achieved.

Full power level was held constant until February 7 when power levels were adjusted and the unit was placed in EGC.

The unit remained in EGC or operated near full power with minor interruptions to perform weekly surveillance until February 14.

At 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br />, EGC was tripped, and the unit was taken to 819 MWe to perform Traversing In-Core Probe Sets.

At 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br />, on February 16, all surveillance were completed and the unit was placed in EGC.

The unit remained in EGC with minor interruptions until February 19.

At 0722 hours0.00836 days <br />0.201 hours <br />0.00119 weeks <br />2.74721e-4 months <br />, EGC was tripped and a load increase to full power was taken and held for the replacement of a Traversing In-Core Probe detector on February 20.

At 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />, a Traversing In-Core Probe set was completed using the newly installed detector and the unit was placed in EGC.

For the remainder of the month, normal operational activities occurred on Unit Two with the unit remaining in EGC or operating near full power with minor interruptions to perform routine surveillance.

kII.PLANTORPROCEDURECHANGES, TESTS, EXPERIMENTS,ANDSAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications Technical Specification Amendment No. 110 was issued on February 6, 1989 to Facility Operating License DPR-30 for Quad Cities Nuclear Power Station Unit 2.

This amendment revises the specified location for drywell temperature indication.

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 Units One and Two during the reporting period. This summary 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.

UNIT 1 MAINTENANCE

SUMMARY

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WORK REQUEST NO.:

Q62124 LER NUMBER: 87-026 COMPONENT:

System 1400 - Piping support on line 1-1404-12" clearance exceeded specs. This failed FSAR criteria.

Shimming was done to reduce gaps.

CAUSE OF MALFUNCTION: The Station was informed by BWRED that line 1-1404-12" piping support clearance exceeded FSAR criteria.

The apparent cause of the event was construction error involving A/E and contractor personnel. The problem involved a discrepancy between drawing M-1610-18, rev. B, and "as-built" conditions.

RESULTS & EFFECTS ON SAFE OPERATION:

The safety of the plant and personnel were not affected during this event. Analysis of stresses revealed that plant was operable even though it exceeded FSAR criteria.

ACTION TAKEN TO PREVENT REPETITION:

Corrective action for ISI support number L404-G-214 on IB core spray discharge line was to shim the excess clearance between the piping lugs and the support's wide flange.

WORK REQUEST No.: Q63018 LER NUMBER: 87-026 COMPONENT: System 1600 - Strut on line 1-1318-6"-LX was removed to meet FSAR compliance.

CAUSE OF MALFUNCTION: The station was informed by BWRED that line supports for 1-1318-6"-LX did not comply with FSAR criteria for allowable stress.

The apparent cause of the event was design error involving A/E personnel.

RESULTS & EFFECTS ON SAFE OPERATION:

The safety of the plant and personnel were not affected during this event. Analysis of the model has shown system operability even though FSAR criteria was not met.

ACTION TAKEN TO PREVENT REPETITION:

Corrective action was to remove the incorrect support to comply with FSAR criteria.

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WORK REQUEST NO.:

Q65731 LER NUMBER: NA COMPONENT:

System 1700 - Reactor Building Vent

'B' channel relay coil was found burned open and a new relay coil was installed.

CAUSE OF MALFUNCTION: A downscale alarm was received for the Reactor Building Vent Channel B radiation monitor.

It was determined that a relay coil failed causing the alarm.

It was suspected to be a random failure, d

RESULTS & EFFECTS ON SAFE OPERATION:

The safety consequences were minimal since the failure was in the conservative direction. All systems performed as intended. A single failure causes only 1/2 of the signal necessary for 1

an ESF actuation.

l ACTION TAKEN TO PREVENT' REPETITION:

A work request was written to replace the relay and the system was returned to normal.

WORK REQUEST No.: Q70425 LER NUMBER: NA l

COMPONENT:

System 1600 - Suppression pool level recorder wandered +/-0.5"

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from sightglass reading. Unit was rezeroed.

1 CAUSE OF MALFUNCTION: The narrow range torus level recorder LR l-1602-7 was l

l reading +2.1" and swaying by +/-0.5".

The cause of the event was a result of oscillations in torus level. A suppression chamber level test indicated that the torus icvel was less than +2".

RESULTS 6 EFFECTS ON SAFE OPERATION:

When the recorder indicated high level, i

the HPCI surveillance was stopped.

Local level indication showed torus level below +2".

Therefore, the safety significance was minimal.

ACTION TAKEN TO PREVENT REPETITION:

A work request was written to calibrate recorder.

Operating personnel were notified to insure they are aware of oscilla-tions in torus level when HPCI is operating.

A procedure change and training requests were submitted for this problem.

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- UNIT 2 MAINTENANCE

SUMMARY

WORK REQUEST No.: Q63817.

LER NUMBER: NA COMPONENT:

System 1600 - Torus /drywell vacuum breaker was inspected tested and: reinstalled. EPN 2-1601-33A.

CAUSE OF MALFUNCTION: While performing QoS: 1600-1, vacuum breaker 2-1601-33A showed dual indication when closed in both Division.1 and II.. A pressure separation' test revealed that the breaker was actually' closed.';True breaker position was not available due'to inaccessibility.

l' RESULTS & EFFECTS'ON SAFE OPERATION:

The safety consequences of this' event-were minimal as the vacuum breakers were shown to'be closed-by:the separation:

test.

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' ACTION ~TAKEN T0-PREVENT REPETITION:

'A work' request;was written to investigate the vacuum breaker problem. A modification M-4-1(2)-88-009 is in progress:

to provide more reliable methods for. position-indication.

WORK REQUEST NO.:.Q63819-LER NUMBER:

NA-i

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System 1600 - Torus /drywell vacuum: breaker was inspected, tested' and-reinstalled. EPN 2-1601-33E.

L CAUSE OF MALFUNCTION: While performing'QOS 1600-1, vacuum brehker 2-1601-33E J

showed only dual indication in Division I.

ALpressure separation test revealed that the-breaker was actually closed.

True breaker position ~was not available due to inaccessibility.

RESULTS & EFFECTS ON SAFE OPERATIOh: The safety consequences of this event.

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were minimal as the vacuum breakers were shown to be closed by the separation-L test.

ACTION TAKEN TO PREVENT REPETITION: A work request was written to'1nvestigate the vacuum breaker problem. A modification M-4-1(2)-88-009 is in' progress H

to.provideLmore reliable methods for position indication.

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WORK REQUEST NO.:

Q63821 fLER NUMBER:

NA.

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COMPONENT: : System 1600 - Torus /dryw' ell vacuum bteaker was inspected, tested and reinstalled. EPN 2-1601-32A.'

CAUSE~0F MALFUNCTION: ;While performing QOS 1600-1, vacuum breaker 2-1601-33E.

showed actual-indication when closed in~both Division-I:and II.

A' pressure separation test revealed that'the breaker was actually' closed. True. breaker position'was'not available due to inaccessibility.

RESULTS'6 EFFECTS ON SAFE OPERATION:.The: safety consequences of this event were minimal as the vacuum breakers were shown to be, closed by the separation test.

l ACTION-TAKEN TO PREVENT REPETITION:

.A. Work Request was written to investigate the vacuum breaker problem.

-A modification M4-1(2)-88-009 is in progress to provide more reliable methods for position indication.

WORK REQUEST NO.: Q64507 LER NUMBER:

88-002 COMPONENT:

System 7200 - Replaced transformer:f,or Unit 2 HPCI room cooler.

CAUst OF MALFUNCTION: The HPCI area room cooler fan' control transformer, at motor control center 29-2, was found charred and.its circuit breaker had tripped. The transformer failure was caused by-a shorted control 3 relay.

It was suspected the relay failure was.a random failure..

RESULTS & EFFECTS ON SAFE OPERATION: The safety consequences of:this event were minimal as HPCI could still have functioned until prolonged' operation caused a room heat-up (without the room cooler) and caused a trip. RCIC and j

Automatic Pressure Relief were also available.

1 ACTION TAKEN TO PREVENT REPETITION: A work request was written to, replace the control transformer at the motor control. center and its associated' control relay.

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LICENSEE EVENT REPORTS l

J There were no Licensee Event' Reports.for Unit One and Two for the month of February.

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V.

DATA TABULATIONS The following data tabulations are presented in this report:

A.

Operating Data Report i

B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions l

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3 APPENOlX C-OPERATING DATA REPORT

-i DOCKET No.

50-254

' l UNIT One j

l OATE % rch 7, 1989 COMPLETED 8Y Lynne Deelsnyder j'

TELEPHONg 309-654-2241 OPSMATING STATUS 0000 020189 672 2400 022889 GROSE MOURS IN REPORTING PEMl00:

1. REPORTING PERIOD:

2511 gax. Ogpggg, capagiyy tagge.Neth 769

2. CURRENTLY AUTHORI280 POWER LEVEL (%Y DESH3N ELECTRICAL MATING VMWs. Net):

N/A

3. POWER LEVEL TO WHICH RESTRICTED llP ANY1 (MWe= Net):

4. REAIONE POR RESTRICTION llP ANY):

THIS MONTH YR TO DATS CulmAAftyE S. NUMEER OF MOURS REACTOR WAE CRv71 CAL............. 672.0 1416.0 118958.2;.

0.0 0.0 3421.9_

8. REACTOR RESERVE EMUTOOWN MOURE...................

1416.0 115075.'2 l

7. MOURE GENERATOR ON LINE......................... 6 7 2. 0

'O.0 0.'O 909.2 E. UNIT RESERVE SMUT 00WN MOURE.....................

9. GROSE THERMAL ENERGY GENERATED (MWH).....,,,...,,.1612190 3346255 245036 3 i

528892 1095122

,79452735

10. GROSE ELECTRICAL ENERGY GENER ATED (MWM).............

507137 1049856 74615130 y

11. NET ELECTRICAL ENERGY GENERATED (MWM)

.. 100.0'

,100.0 80.8

12. 8' EACTOR SERVICE P ACTOR,......................

100.0 100.0 83.I

13. REACTOR AV AILABILITY P ACTOR.....................

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14. UNIT SERVICE P ACTOR............................ 100. 0 100.0 7A 1 1

100.0 78.7

15. UNtf AV AILABI LITY P ACTOR..........................

18. UNIT CAP ACITY P ACTOR tusing MOC1.................... 98.1 96.4 65.9

17. UNIT CAPACITY PACTOR tuimE Design MWel................

95. 6 94.0 64.2 l

f 0.0 0.0 5.3

18. UNIT PORCEO QUTAGE RATE.................

19. SMUT 00WNS SCHEDULE 0 QvtR NEXT E MONTHS (TYPE. DATE. ANO DURATION OF EACMl:

20. IF SMUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STAWS (PRIOR TO COMMERCI AL QPERATIONl:

PORECAST ~ ACHIEVED.

INITI AL CRITICALITY i

j INITIAL ELECTRICITY i

COMMERCIAL OP3RATIced

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i APPENOlX C OPERATING DATA REPORT

- DOCKET NO 50-265 UNIT.' h DATg March 7 1989 COMPLETED SY.l.vnne Deelsnvder ___

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l TELEPHONg 309-654-2241 OMMATING STATUS 0000 020189 672 2400 022889 GRost HOURS IN REPORTING PERICO:

t. REPORTING PERICO:

2. CURRENTLY AUTHORIESO POWER LEVEL (

L: 2511 max. oEPf ka. CAPACITY (MWe Ned. 769 DES 44N ELECTRICAL RATING (MWo.Med:

d ')

N/A

3. POWER LEVEL TO WHICH RESTRICTED (IP ANY1 (MWo.Ned:

4. REAEONE POR RESTRICTION ltp ANYl:

THisMONTN YM TO DATS CUMULAflVS S. NUMSER OF HOURS REACTOR WAE CRITICAL.............. 672. 0 1416.0 112365.9 0.0 c.o 2985.8__

E. REACTOR RESERVE SMUT 00WN HOURE.........,,........

672.0 1416.0 109147.7

7. HOURE GENER ATOR ON LINE..........................

0.0 0.0 702.9

8. UNIT RESERVE SMUTDCWN HOURS,...................,..

9. GROEE THERMAL ENERGt' QENER ATED (MWM)..........,.. 1555200 3275914 234186i87

10. GnosE ELECTRICAL ENERGY OENER ATED (MWM)....,,..... 5.14118 1077350 75010821 493182 1033215 70769792

11. NET ELECTRICAL ENERGY GENERATED (MWN)

... 100.0 100.0 76.7

12. ' E ACTOR SE RVICE P ACTOR......................

..... 100.0 100.0

78. 8 __

13. REACTOR AV AILAEILITY P ACTOM................

14. UNIT SERVICE P ACTOR............................. 100. 0 100.0 74.5

. 100.0 100.0 7s n

15. UNIT AVAILABILITY P ACTOR.......................

18. UNIT CAPACITY P ACTOR IUes McC1.................... 9 5. 4 94.9

62. 8__

17. UNIT CAPACITY P ACTOR (Uune Des 6En MWel................ 93. 0 92.5 61.2 0.0 0.0 8.4

15. UNIT POPCED OUTAGE RATE.................

19. SHUTOOWNS SCHEDULED OVER NEXT E Mot 4THS (TYPS. DATE. AND DURATION OP EACHit -

20. IP SHUT DOWN AT END OF REPORT Pent 00. ESTIMATED DATE OP stARTUP.

21. UNITS IN TEST STATUS { PRIOR TO COMMERCIAL QPERATIONh PORECAST ACHIEVED INiflAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1.16 9

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' APPENDIX B AVERAGE DAILY UNIT POWER LEVEL -

DOCKET NO.

50-254 UNIT one DATE March 1, 1989 COMPLETED BY 'Lvnna Deelsnyder TELEPHONE 309-'654-2241 g

MONTH February, 1989 DAY AVERAGE DAILY POWER LEVEL.

DAY. AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe Net)-

730 1

763

- 37 742 2

765 gg 750 726 3

3, 742 748 4

gg

[

5 769 21 770 g

794 783 22 7

766 758 23 a

792 733 3

g 787 723-g l

1r 738-761 y

11 763 27 765' 12 739

'646 3

13 735 g

762 14 15 769 33 16 790 INSTRUCTIONS On this form, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the' nemiest whole megawatt.

These figures will be used to plot a graph for each reporting month. Nute that when maximum dependable capacity la 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 restrieved power lewt line). In such cases, the average daily unit power output sheet should be fcotnoted to e,uplam the apparent anomaly, 1.164 4

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'1 APPENDlX B AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO.

50-265 r

UNIT -

Two

..1989 DATE. March 1, COMPLETED BY Lynne Deelsnyder TELEPHONE 309-654-2241 MONTH February, 1989 1

DAY' AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL -

(MWe Net)

(MWe Net) 1 754' 721 37 gg 712 j

2

'755 3

743 762 3,

4 521 780 3

21 734

. fl 5

622 8

785 734 22 y

738 750 23 -

751 8

34 741 9

749 720 3

1r 738 N

728 11 753 727 27 12 751 3

734 13 745 3

14 756 y

15 779 31 18 795 INSTRUCTIONS On this form, list the aversy daily unit power level in MWe Net for each day in the reporting month. Compute to the.

neascst whole megawatt.

These figures will be used to plot a graph for cach reporting month. Note that when maximum dependable capacityis used for lhe net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100'4 line (or the restricted power level line). In such cases, the average daily unit power output sheet should be -

-I footnoted to explain the apparent anomaly.

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t VI; UNIQUE REPORTING REQUIREMENTS The following itemsLare included in'this report based on prior' commitments to the commission:

e A.' Main-Steam Relief' Valve Operations-lThere were no Main Steam Rel'ief Valve Operations for the reporting; period.

B.-

Control Rod Drive Scram Timing Data for Units One'and Two The basis for reporting'this: data to the' Nuclear Regulatory Commission

~

are specified:in the surveillance. requirements of Technical Specifications' 4.3.C.1'and 4.3.C.2.

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The.following, table'is a complete summary:of Units One and'Two Control Rod Drive Scram Timing'for the reporting' period. All scram' timing was:

performed with ' Reactor' pressure greater :than 800 PSIG.'

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q 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.

1 0'Brien to C. Reed,'et al., titied "Dresden',-Quad-Cities,)and Zion

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

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QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.

Unit:

01 Reload:

9 Cycle:

10 2.

Scheduled date for next refueling shutdown:

9-9-89' 3; Scheduled date for restart following refueling:

12-11-89 4.

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

NOT AS YET DETERMINE'.

u 5.

Scheduled date(s) for submitting proposed licensing action and sup' porting information:

JUNE 10, 1989 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.

l l

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1773 8.

The present lleensed 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:

l 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 spent fuel pool assuming the present licensed capacity: 2008 34' F> P R () \\/ E [> APR 2 01978 Q.C.O.S.R.

J-_-

L - - -.

1 QTP 300-S32-Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.

Unit:

02 Reload:

9 Cycle:

10 2.

Scheduled date for next refueling shutdown:

2-3-90 3

Scheduled date for restart following refueling:

5-7-90 4.

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

NOT AS YET DETERMINED.

i 5.

Scheduled date(s) for submitting proposed licensing action and supporting I

information:

l NOVEMBER 2, 1990 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.

l I

1

.l 2

7 The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

1475 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: 2008 l

X.P P R O V E D APR 2 01978 Q. C. O. S. R.-

/'

j 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 l

ANSI American National Standards Institute J

-APRM Average' Power Range Monitor ATHS Anticipated Transient Without Scram l

BWR Boiling Water Reactor i

CRD' Control Rod Drive-.

EHC Electro-Hydraulic Control System

(

EOF Emergency Oper'ations Facility GSEP

-. Generating Stations Emergency Plan d

HEPA High-Efficiency Particulate Filter i

HPCI High Pressure Coolant: Injection System i

HRSS:

-- 'High Radiation Sampling System.

IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range. Monitor ISI Inservice Inspection

{

LER Licensee. Event Report 1

LLRT Local-Leak Rate Test i

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 1

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 PCIOMR Preconditioning Interim Operating Management Recommendations-RBCCH Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RHM

' Rod Horth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control.

SDC Shutdown Cooling Mode of RHRS 1

SDV Scram Discharge Volume SRM Source Range Monitor t

TBCCH Turbine Building Closed Cooling Hater System TIP Traversing Incore Probe TSC Technical Support Center 1

0027H/0061Z

N Comm:nw:alth Edis n

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'[

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) ouad Cites Nuclear Power Station

\\ '~' 4] 22710 206 Avenue North i ' em Cordova Illinois 61242-9740 2%/

Telephone 309/654 2241 1

RAR-89-10 March 1, 1989 Director of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Mail Station PI-137 Washington, D. C.

20555 l

1 Enclosed for your information is the Monthly Performance Report l

covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of February, 1989.

Respectfully, l

COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION I

l I

Mow R. A. Robaf Services Superintendent RAR/vmk/eb Enclosure t..

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0027H/0061Z