Text

Monthly Operating Repts for Apr 1992 for Quad Cities Nuclear Station,Units 1 & 2
	ML20113G875
Person / Time
Site:	Quad Cities
Issue date:	04/30/1992
From:	Michael Benson, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-92-021, GCT-92-21, NUDOCS 9205130100
	Download: ML20113G875 (23)
	v • d • e

' '

Commonwealth Edison ouad Citiss Nuclear Power Station 22710 206 Avenue North i

Corcova, Illinois 61242 Telephone 309/654 2241 GCT-92-021 1

May 1, 1992 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Hashington, D.C. 20555 i

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report BRCJLo31eLBOL_50-254 and 50-265 l

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 April 1992.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION blbl Gerald C. Tietz Technical Superintendent GCT/MB/dak Enclosure cc:

A. B. Davis,_ Regional Administrator T. Taylor, Senior Resident Inspector T8 "

9205130100 920430 I'

hg PDR ADOCK 05000254 i

R PDR t

i

=.,.

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT APRIL 1992 COMMONHEALTH EDIS0N COMPANY AND

'IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS..DPR-29 AND DPR-30 TS 14.

l.

TABLE Of CONTENTS I.

Introduction 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 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 TS 14

I.

IRIRODU_C1108 Quad-Cities Nuclear Power Station is composed of two Bolling Hater Reactor., each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

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

The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction tantractor was United Engtheers & 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 critica11 ties for Units One and Two, respectively were October L

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 Matt Benson and Debra Kelley, telephone number 309-654-2241-extensions 2995 and 2240.

i I

l-78 14

II. SURMARY-0F ORERAI11tG_EXPIRIEllCE A.

UnLt_Qns On April 5. Unit One dropped to 203 MHe for 1B Drywell Equipment Drain Sump Pump. replacement.

Load reductions occurred on April 7, to 320 MHe and April 10, to 278 MHe.

Both of these drops were caused by the 1A

. recirculation pump tripping due to the turbine building 125 VDC 1A main bus trip. Another load reduction to 285 MHE was performed on April 19, for turbine testing.

All other load reductions were requested by Chicago Load Dispatch.

B.

Un11_Two Unit Two continued ucheduled refuel outage.

e T314

III. El.MLDILERQCIDURE_CliMGEL_IISIlmEXPIRIliERT1, MQ_.SAEEILRELATED MAINTENAtiCE I

A.

Amendments to Faci 11ty_l,1cenifLor_IethnicaLSpecificAtlons There were no Amendments to the facility License or Technical Specifications for the reporting period.

B.

facjlity or Prcredure_Changei_ReguitinglRC_Appron1 i

There were no Facility or Procedure changes requiring NRC approval for j

the reporting period.

C.

Iests and Exoeriments Reguiring NRC Acoroval There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety Related Eaulpment

'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, l-Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

L TS 14

UNIT 1 MAINTENANCE

SUMMARY

WORK REOUEST SYSTEM EID DESCRIPTION HQRK PERFORMED Q7398 2400 Repair: bad cam ampilfier card.

Return to vendor for repair.

Removed from 2-2406A, HRQ73834 Q99447 5200 Repair leak in 1. inch' flexible

'As Found:. Found hose with temporary repair.

fuel oil' supply line at south end As Left: Replace hose and tightened connections.

of Diesel Generator.

Q99363 756.

Investigate APRM #3..Has h1 As Left: Installed spare flow control trip ref alarm and will not reset.

module 238X45862 and calibrated.

Left APRM in bypass.

Q99753 1001 Investigate and repair minimum As Left: Install new aux contacts and applying

. flow valve (transmitter diff grease, voltage was applied to both contactors.

press lA RHR) which failed to Readings were the same.

open when A division pumps were discharging through B loop.

Q99482 1462 Repair stripped / leaking tubing Ferrel set fell apart when nut removed. Replaced fitting under CS pump disch press with new length of tubing / fittings. Performed SW on pressure switch IB core functional test to verify operability.

No leaks spray pump discharge.

seen.

Q99470 5206 Repair leak in diesel generator As Found: Nipple loose.

fuel oil piping.

As left: Replaced fuel pump discharge pipe and applied sealant.

TS 15 i

.l I

^

UNIT 2 MAINTENANCE

SUMMARY

HORK REQUEST SYSTEM EID DESCRIP_IIQH HORK PERFORMED Q97165' 20 Repair 2B RHR submarine door.

As Found: Hand would not latch and throw lever was bent. One lug bolt was not touching then hinge.

The upper hinge pin torsional spring assembly was sticking. As Left: Adjusted the door latch handle.

Q99642 220 Repair solenoid reactor head seal -Tightened, adjusted and tested limits.

leak off.

Q99724 902 Tighten or replace loose wire Removed wires from terminal points F3 and F4-and found on the field side of TBC-F4. Installed ring tounges then installed back to terminal points.

Q89476 2301 Repair valve drain pot outlet to Installed new valve trim, stem and plug.

an acceptable range foi alve to Installed new diaphraam in valve operator.

close.

-Q99797 2540 Check operability of and/or Calibrated square root and flow indicator.

repair and calibrate ACAD flow control and/or. loop C of ACAD dilution flow controller.

Q83162 756 Investigate and fix output Fuse F10 blown.

Replaced fuse F10.

voltage from high voltage LRPM 24-25 DET D power supply.

Q85484 756 Investigate and repair LRPM Bock tested under pot.

Broke down at 80 VDC. Bad 24-33C.

detector.

Replaced detector and tested under WRQ93650.

088392 1360 Replace fittings, caps on RCIC As Found: Test fittings stripped out on both the high steam flow switch.

hi and low side of the 11stion manifold. Replaced fittings.

Q95830 5745 Repair U-2 2C RHRSH vault room As Found: Cap screws were broken on cover. 2 cooler cooling coil crack.

sheet metal screws were. missing.

TS 15

.I

UNIT 2 MAINTENANCE

SUMMARY

WORK REOUEST SYSTEM EID DESCRIPTION HORK PERFORMED Q97506 7800 Replace cracked insulation on Replaced transformer and performed EQ spilces and drywell cooling blower 2A BKR taped and reinstalled breaker.

transformer wires H-2, H-3.

Q99278 1011 Rewire U2 RHR 1001-81A pressure As Found: White signal wire had approximately 1/8" of bare wire between insulation and end of transmitter, terminal lug. As Left: Replaced terminal.

Q99287 6700 Replace lug on black connector of As Found: Hire was loose in lug.

cable 28574 in cubicle 10 of bus As Left:

Replaced lug.

23 at terminal.

Q99436 1002 Repair cooling coll leak at upper As Found: 1 loose connection motor bearing cooling line on As Left: Retightened threaded connections.

motor 2C RHR pump.

099491 5746 Repair 2A RHR room cooler fan.

As " od: Thermostat set at 100, switch in auto, fan orf.

As Left: Turned the thermostat down to 78 and the fan came on.

Repeated two more times. Set thernostat back to 100 degrees F.

099634 1601 2-1601-57 operates sporadically.

Greased moving parts of open contactor and a test switch to activate the open and closed conta-tors.

Q97507 7800 Replace 2D drywell cooling Replaced transformer.

breaker transformer.

Q98456 8000 Repair RPS MG breaker.

Obtained new breaker and undervoltage relay and tested it on BTS 500 breaker test rig.

Q98579 2300 Repair U2 HPCI emerg brg oli pump Heater works fine.

Reinstalled heater.

htr bkr.

j 098715 260 Test flow converter APRM 4-6.

Installed new power supply and calibrated it along l

with existing flow converter as per QIP 756-5.

Q99030 2540 Repair SQ Rooter extractor on Square rooter did not have any output. As Left:

controller flow B ACAD vent line Removed square root extractor. Component and to SBGT.

extractor worked properly.

~

t

~

UNIT 2 MAINTENANCE

SUMMARY

HORK RE00EST SYSTEM 11D DESCRIPT10ff HORK PERFORMED Q99030 2540 Repair SQ Rooter B ACAD vent flow. Repiaced with like component and extractor worked.

properly.

Q99030 2540 Repair SQ Rooter B ACAD vent flow Replaced with like component and extract indicator.

Q99030 2540 Repair Transmitter flow ATM Removed Square rooter extractor.

Replaced with containment.

like component and extractor.

i Q99030 2540

-Repair flow element ACAD B vent Removed Square root extractor.

Replaced with like flow.

component and extractor.

Q99030 2540' Repair E/P ACAD vent to SBGT.

Removed Square root extractor.

Replaced with like i

component and extractor.

Q99636 1002 Repair cooling piping for 2C RHR Repaired motor end of suction line flex hose had a pump.

crack all the way across flare at flexible swivel.

Q99302 500 Repair U2 Aux electric room EPA Found breaker operational. Removed deficiency tag.

i 2AB-2.

099169 311 Repair leak in CRD withdrawal As Found: Bushing stripped out.

riser vent valve.

As Left:

Installed new tube adapter and quick disconnect.

0909171 311 Replace quick disconnect on CRD As Found: Quick disconnect leaked.

withdrawal riser vent valve.

As left:

Replaced quick disconnect fitting.

Q99172 311 Replace quick disconnect on CRD As Found: Quick disconnect leaking.

inser; riser vent valve.

As Left:

Replaced quick disconnect fitting.

099174 311 Install quick disconnect CRD As Found: Quick disconnect fitting missing.

i insert riser vent valve.

As Left:

Instesled quick disconnect fitting.

i a

TS 15 1

UNIT 2 MAINTENANCE

SUMMARY

HORK REOUEST SYSTEM EID DESCRIPTION HORK PERFORMED 087288 756 Investigate LPRM 40-09 detector As Found: LPRM bypassed.

and connector.

As left: Returned LPRM to operatio".

Q89018 2303 Inspect / Test switch level U-2 Repaired alarm level switch and replaced gasket.

i HPCI gland seal hotwell pump.

Q96874 2341 Repair wire on HPCI turbine As Found: Splice exposed.

thermocouple cables.

As Left:

Removed old tape. Rewrapped splices.

Q96618 1600 Repair dent in inner sealing rim Used a file and emery cloth to smooth the area.

of drywell hatch X-1.

l l

i I

TS 15

IV.

LICENSELEVEHLREORIS 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 reportabic occurrence reporting requirements as set forth in sections 6.6.0.1 and 6.6.B.2 of the Technical Specifications.

UNill Licensen Event RepottJiumbet Date Iltle_oLORcurrence 92-009 04-01-92 Missed Tech Spec Functional Test requirements.92-010 04-07-92 Lot

of Unit 1 125 VDC Bus TB 1A.92-012 Ot-22-92 Main Chimney Hi Range Noble Gas Monitor Inop 7 days.92-013 01-23-92 Second level undervoltage relays setpoint nonconservative.91-014 04-?4-92 LPCI node of RHR administrative 1y Inop.

9?-015 04-29-92 LPCI & C.S. valve yokes outside design basis.

I UNIll 92-011 04-02-92 Loss or transformer 22 92-012 04-09-92 U2 RHR Sup? ort outside FEAR limits.92-013 04-07-92 Second Level UV setpoint non conservative.92-014 04-16-92 1/2 Diesel Generator Inop to Unit (outside design casis),

TS 14

I

4.

V.

DAIA_IABULAIIONS The following data tabulations are presented in this report:

A.

Operating Data Report 8.

Avstage Daily Unit Power Level C.

Unit Shutdowns and Power Reductions 5

t-i e

t

=

0 TS 14

f..;.

n

,,..i...~,,n,

APPENDIK C OPERAtlNG DATA REPORT DOCKET NO $0-154 UNil Ont DAlt May_01_lS91

)

COMPLL1CD BY MatLDeMon iELEPHONE I3091_fif-2231 i

OPERAllNG $1A1US 0000 040192

1. REPDRf!NG PERIOD:.Z400 043092._ GROS $ HOUR $ IN REPORTING PERIOD: 72D _

i i

2. CURRENTLY AUTHORIZED POWER LEVEL (HWt): 2511 HAX DEPEND. CAPACliY: Ifi9 bi$1GN T1ECTRICAL RATING (HWe-Net)! JS9

3. 40VER LEVEL TO WHICH RESTRICTED (If ANY) (HWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY); _

THl$ HONTH YR T'

, ATE CUHULATIVE

5. NUMDER OF' HOUR $ REACfDd WAS CRITICAL...........

720 1

_ 263h30

_ 139142d0

6. REACTOR RESERVE $HUIDCWN HOUR $....,.............

Q10_

01 3421.9_

7.' HOUR $ GENERATOR ON LINE.........................

710 A

_._2hl2100 134043410

8. UNIT RESERVE SHUID0"N ll0VR$.....................

0,0_

0A 9D9 1

9. GRO$$ THERHAL ENERGY GENERA 1ED (.WH).............

1130900 A

_033Z1 E 2 290301221 A

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

_h6100B A Z0110 L D JL414541210.

11. NET ELECTRICAL ENERGY GENERATED (HWH).

_54312G A

_RQ10150 A

_B0]l2h10 1

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

-1& DD 90161 79.10

13. RCAtt0R AVAILABILITY FACT 0R......................

1DLDQ 9QJl 11111

14. L'H I T $ E RV! C E FAC T OR.............................

_ _lDQ4EQ 89.94 7hIl

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

1 & DD 892.94 77 23 1

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

%D9 90101 E 64

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

_,._ E 61 E 23 61292

18. UNIT FORCCD OUTAGE RATE.........................

0.0-13,06 1 41

.19. SHUTDOWNS SCHEDULED OVER NEXT 6 HDNTHS (TYPE. DATE AND DURATION 0F EACH)

20. IF $HUTDOWN AT END OF REPORT PERIOD, ESi! MATED DATE OF $TARTUP:

21. UNITS IN TE$7 $TATUS (PRIOR TO C M MERCIAL OPERATION):

FORECAST ACHIEVED INiilAL CRITICALITY ~

-INITIAL ELECTRICITY COMMEPCIAL OPERATION to 14 1.16-9

~ - -

.. - ~.. -. - - _. _. _

APPENDIX C OPERATING DATA REPORT DOCKET NO 50-105 UNIT Jyo DATE tia,vj., _1992 COMPLETED BY bdLDetlsoIL_

TELEPHONE L3Q9L654-ZZ41 OPERATING STATUS 0000 040192

1. REPOR11NG PERIOD:.L400 04303L GROSS HOURS IN REPORi!NG PERIOD: _ZZQ

2. CURRENTLY AUTHORIZED POWER LEVEL fMWt): 2S11 i%K. D* PEND. CAPAC11Y: 2.69 DESIGN ELECTRICAL RATING (HWe-Net): 289 j

3. POWER LEVEL TO WHICH RESTRICTEn (Ir ANY) (HWe-Net): N/A

'4.

REASONS IOR RESTRICTION (!r ANY):

S. NUHDER Or HOURS WEACTOR WAS CRITICAL............

0,0__

__Q215

__13340Z,95 i

6. REACTOR RESERVE SHUTDOWN HOURS..................

QA_

0A 2935 A

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

0. 0_

Q,Zf,

,__139010115

8. UNIT RE$ERVE SHUTDOWN HOURS......

4.............

_DA 0 0_.

702 1 1

9. GROS $ THERHAL ENERGY GENERATED (HWH).............

01 125 A Z80004062110

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

DiD_

50.,0,_

J9930Z4DJ

11. NET ELECTRICAL ENERGY GENERATED (HWH)............

-537303.Q_

-JL311210 J45010h3A

12. REACTOR SERVICE FACTOR..........................

0.0 0.01 76.62

13. REACTOR AVAILABILITY FACTOR.....................

QiR_

Dal 78,33

14. L ili SERVI CE FACTOR.............................

0. 0 --- _

LQ1 74.63

15. UNIT AVAILA.91LITY FACTOR........................

0.0 0 01 75193 2

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

-97.04_

-2 sin 63J3

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

-93253_

-24dd 61 53

18. UNIT TORCED OUTAGE RATE.........................

0D_

0.0._

B201 2

19. SHUTDOWN $ SCHEDULED OVER NEXT 6 HONTHS (TYPE. DATEiANDDURATIONOFEACH):

- 20.-If SHUIDOWN AT END OF REPORT PERIOD. EST! HATED DATE OF STARTUP:

21.- UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERAi!0N):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

-4 1.16-9 78 14 y

~

- _ ~ _

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-254 UNIT Qat DATE May _S._J 9.92 COMPLETED BY MalLEenson TELEPHONE 1302)._fiSA-2241 iDNTH AprJ L1992_

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0HER LEVEL (HHe-Net)

(HHe-Net) 1.

787 ll.

7B4 2.

7B9-18.

785 3.

792 19.

652 4.

JB2 20.

7B0_

5.

146 21.

1 82 6.

782 22.

76B.

7.

68.9 23.

153 8.

784 24, 783 9.

766 25.

783 10.

614 26.

751 1 1. ___.

784 27.

783 12.

757 28.

783 13, 784 29.

7 61 14.

783 30.

780 15, 784 31, 16, 783 D.'STRUCTIONS On this form,-list the average daily unit power level in MHe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures will 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'may be occasions when the daily average power level exceeds the 1001, 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.

m 1.16-8 7.

APPENDIX B AVERAGE DAILY UNIi POWER LEVEL DOCKET NO 50-265 UNIT Iwo DATE May_fid992 COMPLETED BY Matt.Jenson TELEPHONE 11091_659-224L HONTH - Apri1.19.9L DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(HHe-Net) 1..

-8 17.

-8 2.

-8 18.

-3 3.

-8 19, 1 l

4.

-8 20.

-8 5.

-8 21.

-8 6.

-8 22.

-8 7.

-8 23.

-8 8.

-8 24.

-8 9.

-8 25.

-8 10.

-8 26.

-8 11.

-8 27.

-8 12.

-8 2 8. __

-8 13.

-8 29.

A 14.

-8 30.

-a

15. _

-8 31.

16.

-8

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

These-. figures will-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 may be occasions when the daily average power level exceeds the 100% line (or.the restr.icted power. level line).

In such cases, the average daily unit power output sheet should be footnoted to explain the l-apparent anomaly.

1' 1.16-8

.. =

\\

D L

D

%O A

^

9 T

C 2

N E

E E

0

.O N

T 1

A M

N E

.O 1

4 D

N U

5 5

1 A

a n

0 9

T y

i 2

E t

2

,6 6

T 5

I w

1 o

gw S

99

%g" 2

l D

( U 7

HR 2

OA 0

UT RI SO

) N C

gg5 Oo D 4

g{fo U

i hha R

N c

E I

P T

O R

R S

E L

T N

PEI U

OVC M

T REE O

D TNN N

O TS T

W N

E H

NA O

E SF 1

F AD

(

NI f

$eh A

DD i

p I

na "8w r

PX i

O l

l W D'

)

E 1

R 9

9 R

2 E

"og*h D

9 "8w UC T

IO NS RC eo fn ut ei ln

. u Oa T

C ut C

E O

t i O

L M

ao R

E P

g n R

P L

E H

E

.e c C

O T

f T

N E

I E

D U

V n

E B

i Y

t AC 2

T M

I a

S O

t c

f t

f h

S 3

h e

/

0 e

d C

9 w

u 0

l f

6 B

e 9

5 e

E 4

d n

e s

N o

T 2

n S

14 1

~.

APPENDIX'D' 1N(1T SNUTDOWKS AND POWER REDUCTIONS DOCKET NO.

50-254 taggy pAMg Unit 1 COMPLETED BY M tthew Benson h

May:6, 1992' REPORT HONTH April 1992 TELEPHONE 309-654-2241 j

DATE i

h.

m

$$O{$

g.

.=

1 M

LICENSEE m8 g8 8

.y l

DURATIOlt E

E EVENT o"

NO.

EATE (NOURS)

REPORT NO.

CORRECTIVE ACTIONS /C099ENTS 92-04 4-05 S.

17.3

'B'

-3' 1B Drywell Equipment Drain Sump Purrp '

Replacement 92-05 4-07-92 F-0.6 A

5 92-10 1A Recire Pump Trip from 125 VDC LA Main Bus Trip 92-06 4-10-92' F

6.5 A-5 92-10 1A Recirc Pump Trip from 125 VDC.

IA Main Bus Trip 1'

92-07 4-12-92 S

3.7 F

5 Reduced Load per Chicago L.D.

i 92-08 4-19-92:

S 7.6 B

5 Turbine Testing l'-

92-09 4-22-92 S

4.6 F.

5 Reduced Load per Chicago L.D.

5 Reduced Lo,d per Chicago L.D.

92-10 4-23-92 S

5.6

.F F

'S Heduced Load per Chicago L.D.

92-11' 4-26-92 S.

3.9 Reduced Load per Chicago L.D 92-12 4-29-92 S

3.3 F

5 l-f l

i j :,

t i (final) l i

._.___.._m.__..

t

- VI.

UN109EJEEORIlNGlE0VIREMENIS The fcilowing items are included iin this report based on prior commitments to the commission:

A.

Hun _SigAnLRelief_VdyL0pentions There were no Main Steam Relief Valve Operations for the reporting period.

B.

ConitoLROLDr11LSII AHLl10LlnLDA.t Lior_UH11 LOSE _1Dd_lWQ There was no Control Rod Drive scram timing data for Units One and Two for the reporting' period, t

T i

Ta te PT v

W-t-we+

v--s'tv-t--

4 VII.

REFUf11NG INFORMATION The following im'ormation about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (70-24) from D. E. O'Brien to C. Reed, et al., titled "presden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

t l

l-1 1

19 14 l

ll.., ~ ~.. -.,

_--,..-..,m...~

,,-_..-_.._,,_,,...._,m,-,,_,,,-....-..r-.,..,

QTP 300-532 Revision 2 CUAD CITIES REFUELING October 1989 INFORMATION REQUEST

.l.

Unit!

Q1 Reload:-

11 Cycle:

12 2.

Scheduled date_for next refueling shutdown:

9-5-92 1.

Scheduled date for restart following refueling:

12-5-92 j

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:

NOT'AS YET DETERMINED.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance-analysis methods, significant changes in fuel design, new operating procedures:

1 NONE AT PRESENT TIME.

7.

The numker of fuel assemblies, a.

Number of assemblie:, in core:

724 b.

Number 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 assemblies:

a.

Licensed storage capacity for spent fuel:

3657 b.

Planned. increase In licensed storagei_

0-9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the.present 1 F ensed capar,ity:

2009 L

APPROViED l

4 (final) 14/0395t OCT 3:01989

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

.,.,.g

.,ei-w

%,ee---w-w

=*vaeiirm-'mWF4""*

4**

-=

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

Unit:

02 Reload:

10 Cycle:

11 2.

Scheduled date for next refueling shutdown:

01/01/92 3.

Scheduled date for restart following refueling:

05/07/92 4.

Hill refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

Yes, as listed below:

1. Remove Table 3.7-2

2. Modification to turbine control volve fast acting solenoid valve.

3. Modification to HPCI turbine exhaust steam line.

4. HPCI/RCIC 24-hour shutdown action provision.

5.

Scheduled date(s) for submitting proposed licensing action and supporting /92 information:

1. 01/15

2. 04/18/91

3. 06/28/91 4, 12/31/91 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.

7.

The number of fuel assemblie:.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2439 8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed stcrage 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:

2009 r

I APPROVED

' ' " _' )

OCT 3,01989 14/0395t l

Q.C.O.S.R.

VIII.