Text

Monthly Operating Repts for Feb 1982
	ML20041F387
Person / Time
Site:	Quad Cities
Issue date:	03/02/1982
From:	Weinfurter E; COMMONWEALTH EDISON CO., IOWA-ILLINOIS GAS & ELECTRIC
To:	;
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ML20041F371	List: ML20041F369; ML20041F387;
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	NUDOCS 8203160451
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, _ _ - - . - , - - . - _ --__ _ _ , .

I I

l QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT FEBRUARY 1982 COMMONWEALTH EDISON COMPANY AND l

IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l

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8203160451 ' B20301 pDR ADOCK 05000254 PDR R

e I

TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant of 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. Glossa ry

1 >

I. 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 Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. 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 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit 1 and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Erich Weinfurter, telephone number 309-654-2241, extensions 127 and 194.

II.

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE February I-8: The unit started the month holding maximum attainable l load. On February 6, at 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , a load drop was initiated at 100 MWe/ hour to 600 MWe for weekly Turbine tests and to change control rod pattern. At 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months load was increased 5 MWe/ hour to 813 MWe, which was obtained February 8 at 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months .

February 9-17: The unit was holding load at 810 MWe on February 9 and 10, and 800 MWe on February 11 thrcugh 13 On February 14 a load drop commenced at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months at 100 MWe/ hour to 700 MWe for weekly Turbine tests and to change control rod pattern. The unit started to pick up load at 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months ; I hour at 50 MWe/ hour then 5 MWe/ hour to maximum attainable load of 805 MWe by 1620 hours0.0188 days 0.45 hours 0.00268 weeks 6.1641e-4 months . On February 16 and 17 maximum attainable load was 790 MWe.

February 18-22: On February 18 at 1455 hours0.0168 days 0.404 hours 0.00241 weeks 5.536275e-4 months , the unit scrammed when construction personnel inadvertently vibrated an instrument rack, which caused a Reactor trip. The unit was critical by 2001 hours0.0232 days 0.556 hours 0.00331 weeks 7.613805e-4 months and the generator was on line at 120 MWe by 2255 hours0.0261 days 0.626 hours 0.00373 weeks 8.580275e-4 months . The unit started to pick up load to 500 MWe over the next four hours. On February 19, at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months , load was increased to 600 MWe at 100 MWe/ hour, then 50 MWe/ hour to 700 MWe. At 2220 hours0.0257 days 0.617 hours 0.00367 weeks 8.4471e-4 months load was increased at 5 MWe/ hour until 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months when a load drop to 600 MWe was initiated to perform the weekly Turbine tests. A preconditioning ramp, which included holding load for xenon build-up, began at 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months on February 20.

A maximum attainable .oad of 786 MWe was achieved at 2I00 hours.

February 23-28: A load drop to 650 MWe was initiated on February 28 at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months to perform weekly Turbine tests. Upon completion at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months , load was increased at 50 MWe/ hour for one hour, 25 MWe/ hour for one hour, then at 5 MWe/ hour to maximum attainable load.

B. UNIT TWO February 1-27: Continuing with shutdown for the repair of Reactor Water Clean-up Line which began January 15, 1982.

February 28: On February 28, the Reactor became critical at 0311 hours0.0036 days 0.0864 hours 5.142196e-4 weeks 1.183355e-4 months .

The generator was put on line at 1335 hours0.0155 days 0.371 hours 0.00221 weeks 5.079675e-4 months at 75 MWe. Load was then increased to 400 MWe in the next five hours. The unit ended the reporting period holding at 400 MWe to build-up xenon in the core.

III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications There were no amendments to Facility License or Technical Specifications for the reporting period.

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 requiring 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 Halfunctions, Results and Ef fects on Safe Operation, and Action Taken to Prevent Repetition.

UNIT OtlE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Qi7471 82-2/03L 1/2 Diesel Insulation paper in The switch would not The insulation in the Generator the emergency start actuate, thus the switch was replaced &

1/2-6601 relay was binding on Diesel would not the Diesel was tested.

the switch actuator, start. The Unit 1&

2 Diesels were ope rable.

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9

UNIT TWO MAINTENANCE

SUMMARY

L CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MAI. FUNCTION SAFE OPERATION PREVENT REPETITION Q16528 CRD D-6 A leaking 0-ring Water was dripping The flange 0-ring was was found on the from the flange replaced. ;

CRD housing flange. during the vessel !

pres <, ore test. ;

~

Q14413 SBGT Trains The inspection door Air was blowing back The latch was adjusted i 1/2-7506 A & B latch was. loose on into the Reactor and no air leaks were ,

the "A" Train. Guilding. found.

i Ql6615 APRM Channel.5 The trip module :lo APRit downscale Repaired the quad trip was faulty. light prior to module in chassis &

Unit 2 startup. tested.

Q16648 RHR to Radwaste Torque switch was Breaker keeps Installed new motor-Valve 2-1001-20 installed tripping. -

& repaired the torque i incorrectly. switch.

Q17th8 Steam Drain The torque switch The valve would not The torque switch was I isolation was faul ty. operate from the replaced & the valve 2-220-1 Control Room. was tested.

Q17388 2C RHR Pump The pump seal was Water was leaking The mechanical seal worn. '

through the mechanical was rebuilt and the seal. The pump was pump was tested. ,

still operable.

l Q17372 MSL Drain Valve The' torque switch The valve will not open The torque switch was 2-220-2 was' faul ty, from the Control Room. replaced and.the valve was stroked.

Q16529 CRD C-8 Leaky 0-ring was The flange was found Replaced the 0-ring in found on CRD leaking during the the flange.

housing flange. ~ vessel pressure test.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Ql6657 MSL Drain Valve The pressure seal The seal was leaking Installed new pressure 2-220-1 ring was worn and steam into the seal ring; and Local steam cut. Containment. Leak Rate Tested.

Ql6952 APRM Flow The flow transmitter The flow reference Adjusted the gain of Reference 2 & I was out of calibra- was of f normal . prop amp.

2-260-10B tion.

Q14855 81-18/03L Torus Spray The valve seating The valve failed the The valve seat and disc Bypass surfaces were Local Leak Rate Test. were lapped.

2-1001-36B dirty.

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IV. 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 occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 82-2/03L 2-2-82 1/2 Diesel Generator Trip 82-3/03L 2-5-82 Suppression Pool Level vs. Drywell DP out of specifications UNIT TWO 82-3/0lT 2-23-82 Leak at CR0 upper flange at withdrawal line (42-07)

Interference area 82-3/03L 2-24-82 RCIC high Delta-P--switch 1360-1B+

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

A. Operating Data Report li . Average Daily Unit Power Level

'C. Unit Shutdowns and Power Reductions s

s

\, 9 s

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_ * .. . , . _ _ _ _ . . . _ _ . ...._g..m_.__ . _ _ _ . _ _ _ _ , . . _ _ . _ . _ . , , _ _ . _ . . _ . , _ _ _ . _ _ , _ . , . . , _ . . . , , , , , , _ , . _ _ , , . _ , _

OPERATING DATA REPORT

,. .. . _. .. _: . . . .2 . . _ . - - . . . . - . -- _ . . - - _ _ . _ . _ _ _ _ . . . _ . - .-

1

,~~~ DOCKET NO. 50-254 7.' _

- __ _ '.',.:_____... ._ . _ _ _ _._ UNIT ONE . . . _ _ _ _ _ _

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DATEMurch 02 1982 *

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COMPLETED BYErich Weinforter

_ - . - . . _ . . - -_ . _ . . _._ _ _. i _ ._..~TELEP.H0HE309-654-2241x192 _.._, _

OPER ATING ST ATUS

-.?- -- - . . 0000 020182-. . _ . _ . . _ . - . . - _ _ _

1.'(lepo ting,psrlod 2400 02288.2 Gross hours in reporting period 672 s 2.. Currently-.outhorized-power.. level (MWt)t 2511_ Max. Depend capacity __ _ _ _ _

(MWe-Net): 769* Design electrical rating (MWe-Net): 789 7

3. P c'peh i le ve'l.Lt o.which restr.ict ed (if any ) (MWe- Ne t )L HA __ ___.._ _ _ _ _ _ _ ._

4. Reo$ons for restriction (if any):

..---._..-.y This-Month Yr to Date Cunulative-t 5.. Number.of. hours. reactor was critical. 666'.9 1405.6, 73504.7 i .

6. Reactor reserve shutdown hours 0.0 0 ._0_ 0 3421.9

_ - - ._ . - _ . _ _ _ _ - . _ . - . . . --_--- .u- - -- _. - - _ _ - _ _ _ _ _

7. Hours generator on line 664.01 - 1399.9 '67531.4

8. Unit reserve shutdown. hours.- 0.0 0.0 909.2 _

9. Gross thernal energy generated (MWH) 1576V78 3320321 138378680

10. Gross electrical energy generated (MWH) 516242 1091884 44620817 11'.. Net electrical. energy generated (MWH)_._ 479171 1015610 415996?4_-_

_ 12. Reactor service factor 99.2 99.3 82.0

' ^

13. Reactor avo1N.ibility factor 99.2 W. 3 86.0

. 14. Unit service Foctor- 1 . - . 98.8. 96.9. 78.6_ _

l l 15. Unit avo11obility factor 98.8 98.9 79.6

~ ~ ~ ~

16.sunit capacity'[ actor (Using MDCI 92.7 95.3 62 3

17. Uniticapacity. factor _(Using. Des.MWe) 90.4 90.9. 61. 3 _ .

18. Unit forced outage rate 1.2 1.1 7.0

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

20. If shutdown at end of report-penlod,estinated date of..stortup _______________

8The ROC ney be lever then 769 IWe dering perleds of high onblent tenperatere doe to the thernal perfernance of the sprey canal.

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OPERATING LATA REPORT DOCKET NO. 50-265

_ . _ _ . . _ _ _ . _ . _ . _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ UNIT TWO . _ . _ _

DATEMorch 02 1982 COMPLETED BYErich Weinfurter

_ . . . _ . - . . _ _ . _ _ _ _ _ . _ _ _ _ ____.____ TELEPHONE 309-654-2241xi92 _._ _

OPERATING STATUS

_ ~___._ 0000 020182 _ . - _ ._ ___ _ _ _ . _ . _ _ _ . . . _

i. Reporting period 2400 022882 Gross hours in reporting periodt 672

_ 2. Cu rren t ly _au t h or iz ed _ p ower_ le vel ,( MW t ).: . 2511_ Max.. Dep end. cop aci t y _.__._._._ _ . _

(MWe-Net): 7694 Design electrical rating (HWe-Net): 789

. 3... P ower _ le vel ..t o which._ rest r ic t ed ( if_ an y.).(MWe--Ne t ).11HA__ ____ __ _

l 4. Reasons for restriction (if any):

This Month Yr.to Date Cunulative

-- .5._ Number _of hours _ reactor _was_critico1 _ 20.8_. 362.9 _ 65214.7

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator an line 10.4 346.9. 62588.1-

8. Unit r e se r w e .sh u t d o wn _ h o u r s .._____. . _._ 0. 0 _ 0.0_ 702.9.__,

9. Gross thernal energy generated (MWH) 8621 ,

627714 128514797

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10. Gross electrical energy generated (MWH) 2798 199375 ' iOVOSii5

r. . 11'. Net; electrical energy generated (MWH)__.. -3 45.Q. _ 180160 _ 38304744_ _

L2. Reactor service factor 3.1 25.6 76.7 p _ _ _ _ _ _ __ _ . . . _ _ _ . _ _ . _ _ _ _ _ _ _ _ ._ _ . . _ . _

l 13. Reactor availability factor 3.1 25.6 80.2'

=-14. Unit service foctor-_ _ _ - -. . i.5 24.5 73. 6 _ _

15. Unit avo11ob111ty factor 1.5 24.5 74.4

16. Unit capacity factor (Using MDC) .6 16.5 58.6-

17. Unit capaci t y _ f ac t or... (Using .. Des . MWe ) . .6 16.1 _ 57 i _ _ _

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18. Unit forced outage rate 98.5 75.5 9.8

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

20;If shutdown.atm end of_ report period,estinated dott. of.stortup __,,___________.._

The IIBC not be lower then 769 Inte dering perleds of high edlent temperatore det to the ther.est perfernance of the sprey cenel.

,. , ,4 e. . ...e.c, _ ,, ,_ ~ _ -.-,..*s.m. ,%--.- -. .- . . - .- ..,.-.._..,..-m . . . . - - - - - . . . . - . _ _ . . , . . _ _ , ,

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254

_ __ _ _ _ _ _ _ __. _ _ DATEMorch 02 1982 _ __ ___

COMPLETED BYErich Weinfurter HONTH Febrourv 1982 _ _ . _ _ _ _ _ __ _ _ _ . _ . _ __ . . _ . . _ _ .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Het) . _ . _ _ _ _ _ _ . _ _ ___ _ _ . __ _

_ ______ ( M W e - N e t) . ._ . _ . _.. ___ _ _

i. 754.1 17, 726.8

2. 754.3 18, 445.4

3. 756.5 _ _ _ ._

.___ _ .. 19.. 597.5 _ . . _ _ _ _ _

4. 750.5 20. 605.4

.6._ 617.5 __.__.___._ _ 22, 7P6.6

7. 701.6 23. 741.6 9.. - 752.6 __ ._ _ _..__ _ .. _ 2 5 ._ 740.3 _ . . . .

10. 753.1 26. 745.1

12. 739.8 __ . .. _...28. . 697.8 . _ _ _

13. 748.3

.15, 748.8 _ __ _ _._ _ . . _ _ _

16. 733.5 On this farn, list the average daily snit power level in leie-Net for each day in the reporting nenth. Compete to the nearest uhele negouett.

-- - These figeres will be used to plot a graph for each reperting nenth. Note that uhen posinon dependable copocitt is - --

used for the net electrical rating of the salt thtre ney be occasions when the deily average power level exceeds the 111% line (or the restricted power level line),.In sech cases,the average daily snit peuer setpet sheet should be festnoted to esplein the opperent onently

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 DATEMarch 02 1982 . . . _

COMPLETED BYErich Weinfurter

. MONTH Februarv 1982 __ _ _ _ __ _ _ _ _ _ _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

.MWe-Net)..

( _ . _ _

(MWe-Net) _ _ _ _ _ _ _ .

1. -8,5 17. -8.8

3. -0.3 _ ._ 19._ -8.0 ._ _

4. -8.0 20. -8.0

6. -9.3 _ _.22. . -B.0 __

7. -9.2 23. -8.6

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

.9. -9.4 . _ _ _ . _ _ 2.5._ -7.9 ___

l. 0 . -9.3 26. -0.4

.1. 2 . . -9.3 _ . _ . . . 28.. 100.7 _ . . _ _

13. -9.6 15 . . -9.3 _ _ _ _ _ _ _ . . _ ._ . . _ _ . .

16. -9.2 INSTRUCTIONS On this fern, list tha overage daily vilt ;"*r level in MWe-Net for each day in the reporting nenth.Conpete to the nearest uhele negewett.

These figeres will be esed to plot a graph for each reporting nonth. Note that when r.mna dependable Copecite is E ._ . _

esed for the net electrical rating of the snit there ney be occasions when the daily e$.rege pouer level exceeds the- .

1981 line (er the restricted power level line).,In such cases,the average daily enit power setpet sheet should be festnoted to explain the apperent onently

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

n P"1 M M M M M M M M M I""1 r""~l !"""*1 n n (~ ' n ~~ ~ ;

(3 O i APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. 050_254 March 1978 UNIT NAME Quad-Citles Unit On COMPLETED BY E. Weinfurter DATE tiarch 1, 1982 309-654-2241*

REPORT MONTH February 1932 TELEPHONE ext. 194 m 5 -

m z Eb z 5 Ee S @ "

LICENSEE pg gg NO.

C '

DURATION $

it 3{ $ EVENT m8 g3 ,

DATE (HOURS) y5g REPORT NO. 3 CORRECTIVE ACTIONS / COMMENTS R

82-4 820206 0.0 B 5 RB C0HROD Reduced load for weekly Turbine tests and to change control rod pattern 82-5 820214 0.0 B 5 RB C0llR0D Reduced load for weekly Turbine tests and to change control rod pattern 82-6 820218 F 8.0 H 3 IA I!!STRU Unit scram on Reactor liigh Pressure dt.e to construction nersonnel working around an instrument rack shaking instrument 82-7 820228 0.0 B 5 RB C0llROD e R'duced load for weekly Turbine tests and to change control rod pattern-(finaf) 4 -

n E=1 M M M M n n n n n l'"""1 t=='] n n n , , , ,, ,

(h ( '

5 APPENDIX D .qTP 300-S13 050-265 UNIT SilVTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.

March 1978 U. NIT NAME Quad-Cities Unit Tw COMPLETED BY E. Weinfurter DATE M rch 1, 1982 309-654-2241, REPORT MONTH February 1982 TELEPHONE ext. 194 w 8 s m

m = Eb x 5

n. e 8 @$ LICENSEE ww zw C DURATION $ #h* EVENT mS" ES NO. DATE u-(HOURS) " y5 REPORT NO.

h" CORRECTIVE ACTIONS / COMMENTS 82-3 820115 F 661.6 A 2 LER/R0 CG PIPEXX Continuation of shutdown t,o repai r crack in 32-1/01T ,

Reactor Water Clean-up Line (finai)

', i VI. UNIQUE REPORTING REQUIREMENTS _

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

A. MAIN STEAM RELIEF VALVE OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND T40 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.

The following table is a complete summary of Units One and Two Control Rcd Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.

I I

4

)

, ,. ., , , , . . . - - - - , . , . - - , -.~c -, - -., . - . , - - ,,. ,, , - ,,

'. 4 RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1&2 CONTROL ROD DRIVES, FROM I-I-82 TO 12-31-82 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90% '

insertion DESCRIPTION-NUMBER 5 20 50 90 Technical Specification 3.3.C.I &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram insertion Time) 2-27 2 0.24 0.46 0.935 1.635 1.67 Unit 2 Cold Scram Time (M-2) L-2 (42-07) Withdrawal Line Repair M-2 (46-07) Inspected Rod drives not replaced e

i i

VII. REFUELING INFORMATION The following information about future reloads ac 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 "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

l

! l I

" ~

_. QTP 300-S32 3 ,.

Revision 1 i-QUAD-CITIES REFUELING M:rch 1978 C ,

I trFORMATION REQUEST 3 *

~

c 1. Unit: 1 Reload: 6 Cycle: 7 a 2. Scheduled date for next refueling shutdown: Sept 12, 1982 j s

w l

3 Scheduled date for restart following refueling: Dec 4, 1902 -

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

? YES e

5 Scheduled date(s) for submitting proposed licensing acticn and supporting

{ . Information:

d. ~ JULY 26, 1982 P

j* 6. Important licensing considerations associated with refueling, e.g., new or

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

A :-

N 'If1PLEltENTATl0N OF TH'E ODYN TRANSIENT ANALYSIS CODE AND RESULTS (tiCPR SCRAM TlHE DEPENDENCE)

,~ .

?- 7 The number of fuel assemblies, f' a. Number of assemblies in core: 224 new/724 total k after the

b. Number of assemblies in spent fuel pool: outage 1940

(

l

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: 2920

b. Planned increase in licensed storage: 4636 new/7556 total 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/04 4PPROVED v LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2 01978 Q.c.o.S.R.

, QTP 300-S32 g ~~ ~ ,

R2 vision 1

{

QUAD-CITIES REFUELING March 1978 INF'MMATION REQUEST u~ 1. Unit: 2 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: Feb 27,1983 i

~

3 Scheduled date for restart following refueling: April 23, 1983 -

r

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

I' N0 u

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

" Information:

N0t4E r

$~

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

' different fuel design or supplier, unreviewed design or performance analysis y e/ methods, significant changes in fuel design, new operating procedures:

NONE t,

L 3-7 The number of fuel assemblies.

l'

a. Nurcher of assemblies in core: 192 new/724 total 3 after the

b. Number of assemblies in spent fuel pool: outage 2132 I"

[ 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: ,

b a. Licensed storage capacity for spent fuel: 2920

b. Planned increase in licensed storage: 4636 new/7556 total 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/8

LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 WPPROVED m.

1- APR 2 01978

,_ Q. c. o. S. R.

ages e th=9 h 6 p e w egumspe ese g amme ** w m>6 989 **** * ' '

.- .m -- -

-%.w..-e--e m- ammy ..mw===.. e-e