Text

Monthly Operating Repts for Feb 1992 for Quad-Cities Nuclear Power Station,Units 1 & 2
	ML20090H312
Person / Time
Site:	Quad Cities
Issue date:	02/29/1992
From:	Kelley D, Losekshort C, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-92-010, GCT-92-10, NUDOCS 9203160029
	Download: ML20090H312 (24)
	v • d • e

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.e lCommonre'alth Edison 1 y

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- Qund Citits Nucitar Power Station '

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,m 22710 206 Avenue North

' Corcova, Illinois 61242

,t Telephone 309/654-2241 s

GCT-92-010.

4 March >2, 1992

.U. S.' Nuclear Regulatory Commission ATTN:-- Document Control Desk Hashington, D.C. 20555 Sl'BJECT: Quad Cities Nuclear Station Units 1 and 2 Monthly' Performance Report i

.tiRC Docket _tios. 50-254 and 50-?&S Enclosed-foryour.information is the Monthly Performance Report covering the Joperation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of February _1992.-

~ Respectfully, y

.+

-COMMONNEALTh.'0ISON COMPANY j

g fQUAD-CITIES'hutLEAR POWER STATION

'i hbf. EAT 3;

KG.LC. Tietz '

Tecnnical Superintendent i

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CCT/CALS/dak.

Enclosure

=cc: '-.Ai-B. Davis, Regional Administrator

.T.: Taylor ( Senior Resident Inspector n

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k QUAD-CITIES NUCLEAR PDHER STATION UNITS 1 /ND 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1992 COMMONWEALTH EDISCN COMPANY AND IOWA-ILLINCIS GAS & ELECTRIC COMPANY NP.C DOCKET N05. 50-254 AND 50-765 LICENSE NOS. DPR-29 AND DPR-30 i

TS 14

4 e

TABLE OF CONTENTS 1.

Introduction II.

Sunnary of Operating Experience A.

Unit One B.

Unit Two 4

III.

Plant or Procedure Changes, Tests, Experiments, and Shfety Rele' Maintenance A.

Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval e

D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee Event Reports V.

Data Tabulations A.

Operating Data Report B.

Average Daily Unit Power f.evel C.

Ilnit 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 l

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A I.

IBIR0000110B Quad-Cities Huclear 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 Ga: & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Bolling Hater Reactors.

The

-Architer,t/ Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was Unitt.d 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 generat'lon of power began on February _18, 1973 for Unit One and March 10,-1973 for unit Two.

Th',s report-was-compiled by Cynthia Losek-Short and DeDra Kelley, telephone number 309-654-2241', extensions 2938 and 2240.

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t II. SUli%RLQf_0EIMIIRLEXEERIERCE A.

URLt_One Unit One began the month of February operating at full load. -The unit operated close to or at full power for ti.e entire month except during February 7 thru February 20th.

The reactor scrammed on February 7th at 0201 hours0.00233 days 0.0558 hours 3.323413e-4 weeks 7.64805e-5 months due to high steam flow indication.

The unit remained off-line for repairs until the reactor went critical on February 18_at 1045 hours0.0121 days 0.29 hours 0.00173 weeks 3.976225e-4 months .

All other load drops that occurred through the month were issued by Chicago Load Dispatch.

B.

Unit Two Unit Two continued's;heduled refuel outage.

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III, PLANT OR PJLOCEDURE_QLANGELlESISmEXEERIMNIL 1

ANDJAEEILRELAIID_1LAIRIENANCI A.

Amendmenti_to_E acility_Lic. east _or-T e c h n i c a l S p e c i fic a t i ora l

Technical Specification Admendment No.134 was issued on February 14, 1992 to Facility Operating Itcense No. DPR-29 and Araendment No. 126 to j

facility-Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2 respectively.

These amendments revise the Technical Specifications to reflect the addition of two new sections:

tne Padiation Protection Program and High Radialton Area.

j B.

Facility or Procedur_e_ChAnstslequjiing_hRCApraV31 There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Ieits_and_ExperJmeats_Resuir_ina NRC Apprqyal There were.no Tests or Experiments requiring NRC approval for the

= reporting period.

D.

Cattac1LY2JialatenaDce of._SafttyleJAtad_ Equipment The following represents a tabular summary of the major safety related maintenance performed en Units One and Two during the reporting period.

This sunnary includes the following:

Work Request Numbers, licensee Event Report Numbers, Co:npenents, Cause of Malfunctions, Results and-Effects on-Safe Operation, and Action Taken to Prevent itepeti tion.

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UNIT 1 MAINTENANCE

SUMMARY

l HQRK REOUESI S1SIEM EID_015CRIEIlQfi HOR < PEREQRMED I

085102 6600 Repair shaft driven oil pump As Found: Gaskets were found to be a littlE leaks.

aged. As Left: Cleaned sealing surfaces and installed new gaskets.

073408 6600 Investigate and repair problems As Left: Removed old relay on 1/2 D.G. and with 1/2 D.G. Relay found during installed new relay.

OtiMS 6600-1 and S1 general l

surveillance.

Q97905 6700 Replace the chipped insulation As Found:

Insulation plate on breaker had a l

plate on phase "C" of Ntri #10 broken corner. As Left: Removed stationary with new one.

arching contact.and then removed the broken insulating plate.

Installed new insulating plate, assembled and installed stationary arching contact.

Q97910 6700 Replace the SBM switch on the 4KV As Found: The SBN switch was not working properly breaker number 69.

due to high contact resistance. As Left: Removed old SBM switch and replaced with new SEM switch.

Tested new SBM with digital fluke.

Q97271 7300 Remove LITl RMS-9 programmer from Programmer was wecng type for the 5pplication and 480V breaker and install a was removed. The LITl RMS-9 was rejected to LST1-RMS-9 programmer.

vendor and a new LST1-RMS-9 was installed in breaker number NO29.

Q95965 0202 Repair reactor recirc pump 1A As Found:

Found neutral wire from indicating suction valve indication on light at MCC was pulled loose. As Left:

Proper 18-19-5 which burns dim.

light indication was achieved after log was landed.

l 091046 0261 Investigate and repair alarm that As Found: Merccid switch didn't trip all the way came up at 138 indication /other when actuated. As Left:

Installed new switch, at 142 indication /both on D/P calibrated it, adjusted trip point to 142.6 psi indication switch main steam line and rising. Performed functional test as per QIS flow not repeating very well.

21-2 and switch worked fine.

TS 15

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j UNIT 1 MAINTENANCE

SUMMARY

+

HORLEE00EST SYSTEM EID DESCRIPTION HQFL.EERFORMED Q97935 0263 Calibrate and test reactor vessel As Found:

Performed loop calibration check on level cor. trol indication switches 1-7.63-59A instrument loop switch 3 on 1-263-59A 1-263-59A and B during level was barely in tolerance and switch 4 was out of recovery.following Reactor Scram.

tolerance. Calibration check on 1-263-598 discovered that the indicator for 1-263-59B was over range on both ends and switch 3 was out of tolerance. As left:

Performed calibration for 1-263-59A and 1-263-59B loops. After all calibrations were completed performed QIS 5610-26-6 and verified instruments worked fine.

Q98221 0901 Replace reset switch IB RBFDS As Found: Old switch appears to be overheited.

which is bad.

As left:

Removed old switch and replaced with new switch. Verified proper operation of switch.

Q93255 1100 Investigate and repair standby As Found: Temperature switch TS-1-1149 was out of 11guld control tar.k temperature its hole. As Left: Calibrated and restored switch.

temperature switch TS-1-il49 and 1-1155 to their proper position.

No adjustment necessary.

Q93255 1100 Investigate and repair standby As found:

Temperature switch TS-1-il49 was out of liquid control tank temperature its hole. As Left: Calibrated and restored switch.

temperature switch-TS-1-1149 and 1-1155 to their proper position.

No adjustment necessary.

093255 1100 Investigate and repair standby As Found:

Temperature switch TS-1-il49 was out of liquid control' tank temperature its hole. As Left: Calibrated'and restored

switch, temperature switch TS-1-ll49 and 1-1155 to their proper position.

No adjustment necessary.

Q96937 1401 Investigate and repair IB core As Found:

1/2" nipple was leaking. As Left:

spray pump seal leak off line Removed old nipple and installed new 5-14"/(1/2")

which leaks at the weld to the carbon steel nipple.

discharge piping.

TS '5

^ UNIT 1 MAINTENANCE

SUMMARY

HQRK RE00EST

. SYSTEM eld.EESCRIPTIQS HORK PERFORHED

~

Q97908 2300 Repair 1-2317 HPCI'stop valve As Left: Disassembled the valve and its which has become uncoupled on the internals. Blue check on main poppet seat failed, actuatorLsideLand is not closing, all other-necessary parts were good except for the main valve seat which had cracking indications.

The crack indications on the main poppet were

- aoproved exceptable per a-G.E. Letter. Assembled valve internals after the main poppet seat was lapped and blue checked okay. Checked stem alignment which looks good with straight edge.

Checked and verified full valve stroke which was 4 1/16" and coupled valve to operator.

Q97732 6700 Replace the. defective secondary As Found:

1) Secondary disconnect was damaged -

disconnect and charging motor on-faulty crimp, resulting in loose termination.on 4KV breaker.

MG5 Pin.

2) Broken brush holder cap on charging motor. As-Left:

1) Removed damaged secondary disconnect'after measuring location.

Performed wire lift and landed (recorded and verified) crimp leads and installed new disconnect.

2) Performed wire lift for charging motor, removed' damaged motor,. Installed new motor. landed leads (recorded and. verified).

Performed passive inspection and ciectrical test on breaker.'

TS 15 L

QMIT 2 MAINTENANCE

SUMMARY

HQRK REQU.ESI SYSTEM EID DESCRIPTICN-WORK PERFORMED Q97252 0902 Repair cracked insulation and bad As Found:. Hiring was showing through insulation lug on wire. contact 14 for'902-32 due to bad crimp. As'Left: He. replaced lugLwith

. panel.

SI #376B40, after verifying 005 and' installing jumper.

098139 6600 Investigate the cause for Unit 2 Tested and recorded tachmeter voltages versus rpms Diesel Generator field failure to on Diesel Generator, which improved after flash.

. adjusting toothed wheel gap in linkage. Replaced contacts CA1 and CA2 and cleaned up wiring on speeds sensing panel. Started diesel for-test run, ran speed up to 800 rpm and adjusted RH2 to pickup vs relay.- The apparent.cause of failure due to setpoint drift on speed-sensing panel components, 083701 6700 Investigate and repair motor Tested 2A Core Spray pump breaker on Bus 23-1 Cub.

breaker Bus 23-1 Cub. 2 auxiliary 2 and it performed all its functions. Apparent switch linkage is not making cause of breaker malfunction was due to dirty proper contact with auxiliary contacts and linkage not being adjusted.

switch while perforaing a core spray logic test.

097807 7800 Repair wire on 1/2A Standby Gas As Found:

Black wire from cable #2f99 was found i

Treatment MCC 29-4 Cub. D2 behind stabs of Cub. D-3 causing a short. As causing short.

Left: Cut and relugged black wire and relanded it on terminal #7.

Also dressed cables.

Q97804 7800 Repair damage to MCC 29-4 cubicle As Found: Afternoon shift found a conductor under D-3 breaker for.2-1001-268 which T1, T2 and T3 terminal block. When 2-1001-26b has blown internal parts.

cubicle was stroked the lead shorted l'1 and T3 together causing both overload relays, overload heaters and open contrdctor to be damaged. As Left:

Replaced open contact on left side, both overload relays, both overload heaters, terminal blocks T1, T2, and T3, and the lug for motor field cable on terminal T1.

Meggered terminal blocks T1, T2, T3, 1, 2, 3, 3A, 4 and 7 to ground and all t

read above 500 mohms or greater.

TS 15

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/

IV. LICENSELEVENI_REEORIS The following is a tabular sumary of alll licensee event reports for

-Quad-Cities Units One~and Iwo occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.8.1 and'6.6.B.2 of the Technical Specifications.

UNIT 1 Licensee Event Report Numbn DAtg.

Tit 1e of Onumne 92-002 02-06-92 HPCI Turbine Stop Valve failed open.92-003 02-06 HPCI Suction Pipe Hanger outside design basis.92-004 02-27'-92 Unit 1 Rx Scram from MSL High Flow.92-005 02-01-92.

RCIC 1301-49 Valve could not open.92-006 02-25-92 Lcss of Main Control Room Annunciators for Unit One following loss of line 0405.

UNIL2

'92-006 01-29-92 Hissed On-Site Review of a Temporary Procedure # 7370.

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V.

DAIA_TMIMIl0NS The foll wing data tabulations are presented in this report:

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.A.

Operating Pata Report B.

. Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions-i l

l1 TS 14 b.'

APPENDIX C OPERATING DATA. REPORT DOCKET NO 51-214 UNIT Qnt

.DATE tiaEittlulg32 COMPLETED BY ' Cynthit_Lnick.Shori TELEPHONE 1309) 654-2241 OPERATING STATUS 0000 020192

1. REPORTING PERIOD: 2400 02299L GROSS HOURS IN REPORTING PERIOD: 696

. 2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 MAX. DEPEND. CAPACITY: Zh2 DESIGH ELECTRICAL RATING (Hde-Net): 789

3. DOWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Net): N/A

~ 4.' REASONS.FOR RESTRICTION (IF.ANY):

THIS HONTH YR TO DATE CUMULATIVE

5. NUNDER OF HOURS REACTOR WAS CRITICAL...........

423.L 1102J_

__UMZad_

g 6, REACTOR RESERVE SHUTDOWN HOURS..................

0.0 0.0 3421.9

__. 400 0_

1148.0

__132329J_

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

L-l.

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

0. q.,

Q,_Q_,

909.Z.

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

_9620.0LO._

_2H0H9918 ZBM19011d_

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

_lL41&Q_

917585J

_92991921,.Q_

l

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

_39fi2&Q_

,_2Q152620 -

_87610944.0 12,' REACTOR SERVICE FACT 0R...........................

(0.82 81 d6 78dl l-

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

60.82 81.06 30J5

..14.' UNIT SERVICE FACTOR.............................

58.05 79.72 75252 L

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

58205

__.._]hZ2 122D3

(

16. UNIT CAPACITY FACTOR (Using HDC)................

57d_

B142 65.38-

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

Si,b3 J115 63 10

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

41.9 20.28

.LB1 l

19. SHUTDOWHS SCHEDULED OVER NEAi 6 HONTHS (TYPE, DATE, AND DURATION OF EACH):

20. IF' SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP>

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

j_

(0 RECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COHHERCIAL OPERATION l

Ts a 1.16-9 i

Al PENDIX C OPERAT),4G DATA REPORT DOCKE1 NO. 5t-265 UNIT h o._

DATL [Mrt11.3.3.J29L_ _ _

00dPLE1ED BY Cy.otMijalek.5hoci 1ELEPH'JNE 1309.ll54-ZZ4L _.

OPERAilnG STAtu$

0000 020192

1. REPORilNG PER100: 1 400 022992. GRS$$ HOUR $ IN REPORitts P[RIOD: Nf1

2. Ct.WfNTLY AUTHORIZtD POWER LEVEL (Mdt,: 251) __

HAL DEPEfD. CAPAC11Y: Jkl.

DEllGN El.F.ClRICAf. RAi!NG (HWe-94et): 709.

3. POWit LEVLL TO WHICH ftESTRICTED (if ANY) (PWe-Net 1: M/A_.

4. PEASONS FOR RESTRICTION (IF ANY):

THl$ HONTH YR TO DATE Cutt!'.A Y lVE

5. NUMBER OF HGOR$ REACTOR WA$ CRITICA!............

.01

_0 25

_.J33402.9h 0.L O tQ

.21ES.

6. REACTOR RESERVE $HV40WN HOUR $....

7. HDUR$ GrNERATOR ON LINE....

_... 02Q 0 25

_ _ 13002Q115 4

8. UH!! RE$tRVE $HUIDOWN HOUR $..................

Oil QA_

19229_

9. GROS $ THERMAL. ENERGY GENERATED (H W............

_0,L

__ llL L 20Ga4062 <0_

P

10. GRus$ ELECTRICAt. ENERGY GEhERATED (ifdH)..........

QJ_.

_ __5LO_

l?9302dua

11. NET ELECTRTCAt. ENERGY GE.'!ERATED (tNH)............

-$315.10_

_.-!@3?.,9 3511434310_.

12. REACTOR SERVICE FACT 0R...........................

__ _010_.

._DiDZ

_21,21

13. REACTOR AVAILABIL11Y FAC10R...............

JJ_

LDZ 79.L 14. l>N I T $( RVI C C F ACMR.............................

QA_

Q.02 1h21.

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

0.10_.

OM EtiJ.

16. UNIT CAPACITY FACTOR (lfsing HDC)

-0JL

_-LR9

___64 M

17. UNIT CAPAC11Y FAC10R (Using Design WWe)

._ _.dd5._

-1.61 62d5 la. UNIT FORCLD OUTAGE RATE.........................

Q10

__.010_

1 109

19. SHU1 DOWNS SCHEDULED OVER hlXT 6 MONTHS (TYPE. DATE, AND DURATION OF EACH):

20 IF $HUTDOWN AT D10 0F R(PORT PERIOD. E$11 HATED DATE OF ST ARTUP: _ April 10.1_J992

21. UNITS IN TE!T $1 AIUS (PRIOR TO COHHERCIAL OPERATI0ld):

10 RECAST ACHIEVED IN111AL CRiflCAl.lTY INITIAL ELCCTRICin COMMERCIAi OPERATIDN.

l.'6-9 1814

APPENDfX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50:214 UNIT Dne DATE tiatih..L_lR92 COMPLETED BY Cynttila_Loich-Shor.t i

TELEPliONE.C1Q9L65a ' L41

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'HONTH _.[1bryary._l992 i

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DAY AVEREAGE~0AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(HWe-Net) n 1.

_.804 17.

- 6 _,.

-2.

803 18.

-6 3.

80 1 _

19.

129 4.

8.09.

20...

701 _ _

4 S.

809 21.

B02 6.

- Bj.1 2 2. _.

772 7.

53 23.

163 8.

- 6 ___.

24.

_225___

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25.

807 I

10.-

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16..,

803 11.

-6 2 7. __._.,

790

.12. -

-6 2 8. __.

_lil 13.

-f 29.

790 14.

- 6_ _ _ _.

30.

15.

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16. INSTRUClIONS On this-form, 11st the averaga daily unit power level in MWe-Net for each day in-the reporting n.onth.

Compute-to the_neuest whole megawatt.

These figures will be used to plot a graph for each reperting month.

Note that when maximum'de)endable capacity is used for the net electrical ruting of the Unit, there may se occasions when the daily average power level exceeds the 100% line-(or the restricted power level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly, u s. '

1.16-8

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO 50-265 UNIT lyo DATE }4Rch_3. 1992 COMPLETED BY Cynth1A_LosdeShor.t TELEPHONE 1302LG54-2241 MONTH _EthrRry._19.21 i

DAY AVEREAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

. HWe-Net)

(HWe-Net)

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13. _.

-6 29.

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-6 30.

15.._.

- 6.

31.

16.

-6

-INSTRUCTIONS =

On this form, list the average daily unit power level in MHe-Net for each day Lin the reporting month. Compute to the nearest whole megawatt.

These figures *111 be used to plot a graph for each reporting month.

Note

-that when maximum dependable capacity is used for the net electrical rating of the unit, there way be occasions when the daily average power level exceeds

- the 1007. line (o* the restricted power level line).

In such cases, the average daily unit p)wer output sheet shou)6 '>e footnoted to explain the j

L apparent anomaly.

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m p, VI. UtilWE _REPORTIRGEWIRDiERIS n

The following items are included in this report based on prior commitments to the commission:

A.-

}iain_1 team RelleLyalve OptcAtlODI Relief valve operations during the reporting period are summarized in the following table.

The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

Unit: One Datt:

February 7. 1992 hlYri. Attila _ted Roul_lyptof_ Actuation 1-203-3B 2

Per CCOP 203-1

..EIAntloadit1001:

Reactor Pressure - 1041 psig & 1018 psig

)

1 011 trip.tlon of Eyenti: Reactor pressure control during scram event of February 7, 1992.

Unit: One DAtt:

February 19, 1992 Yalyej Actuated Nomklyse of Actuation 1-203-3A Post Maintenance 1-203-3B Post Maintenance

-203-3C Post Maintenance-1 1-203-3D Post Maintenance L

1-203-3E Post Maintenanca l-Reactor Pressure - 927 psig EIAtt_CQDdillODs:

Deltt10110A cf_Elent.s: Post Maintenance surveillance following Unit 1 scram and failure of' 3C ERV to actuate when manually operated.

B.

Control RodJriveJcrAmliming3Ata_for_ Units one. and.lxo The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications -4.3.L.1 and 4.3.C.2.

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.

19 14 I

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED OM UMfT L&_2: CONTROL ROD. DRIVES, FROM l-1-92 TO-12-31.-

AVERAGE TIME IN SECONOS AT 7.

MAX. TIME '

INSERTED FROM FULLY WITHDRAWN FOR 907.-

INSERTION DESCRIPTION

' F11MBER 5

20 50 90 Technical Specification 3.3.C.1 &

DATE OF RODS-0.375 QdOO 2.00 3.5 7 sec.

3.3.C.2 (Average Scram Insertion Time)

A 2-19-92 2

0.28 0.67 1.43 2.48

.J-2 Drive Replacement (J-2), Scrain Valve N-7 2.55 2-20-92 1

0.32 0.69 1.45 2.45 N-5 Scrca Valve Work N-5 2.45 i

8 t

i h

1 l

TS 75 I

l

.u

VII. BLEVELING_IliE0RM&IION Yhe following informstion about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled *Oresden Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 14, 1970.

J E

/

's b.

TS14 i

i -

________.__._____i___E_________i_______.______

_ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _.

QTP 300--532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUCST 1.

Unit:

41 Reload:

il Cycle:

12 2.

Scheduled date for next refueling shutdown:

9-5 92 3.

Scheduled date for restart following refueling:

12-5-92 l

4.

Will refueling or resuption of operation thereafter require a Technical Specification ch+nge or otfer license amendment:

NOT AS YET DETERMINED.

5.

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

NOT AS iET DETERMINED.

6.

Important licensing considerations associatPd With refu9 ling, e.g., new or different fuel design or supplier, unrevl wed design or performance analysis methods, significant changes in fuel design, new ope.'ating procedores:

NONE AT PRESENT TIME.

7.

The number of fuel assemblies.

a.

Number of assenblies in core:

724 b.

Numbe of assemblies in spent fuel pool:

1405 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblias:

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:

2009, APPROVED

("8" OCT 5 01989 14/0395t O.C.O.S.R.

QTP 300-S32 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATICH REQUEST 1.

Unit:

92 f.eload:

")

Cycle:

11 2.

Scheduled date for next refueling shutdown:

01/01/92 3.

Scheduled date for restart following refueling.

04/10/92 4.

Will r9 fueling or resumption of operation thereafter require a fechnical Specification change or other license amendt.ent: Yes, as listed below:

1. Remove Table 3.7-2

2. Modification to turbine control valve f ast acting solenoid valve.

3. Modification to llPCI turbine exhaust steam line.

4 IIPCI/RCIC 24-hour shutdown a.: tion provision.

5.

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

supporting /92

1. 01/15

2. 04/18/91

3. 06/28/91 4.

12/31/91 1

6.

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

or different fuel design or supplier, unreviewed design or performance i

analysis methods, significant changes in fuel design, new operailnr1 procedures:

NONE AT PRESENT TIME.

l

-7.

The number of fuel assemblies.

p O

a.

Number of-assemblies in core:

b.

Number of assemblies in spent fuel pool:

3163 l-8.

The present licensed spent fuel pool storage capacity and the size of l-any increase in licensed storage capacity that has beer, requested or is planned in number of fuel assemblies:

l a.

Licensed storage capacity for spent fuel:

3897 l

j b.

Planned increase in licensed storage:

0 1

9.

The projecteo date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

2009 APPROVED OCT 3 01989 14/0395t

-1 O.C.O.S.R.

t VIII. GLOSSAR1 The following abbreviations which may have been used in the Monthly Report, are defined below:

ACAD/ CAM - Atn.ospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring