Text

Monthly Operating Repts for June 1982
	ML20054M693
Person / Time
Site:	Quad Cities
Issue date:	07/02/1982
From:	Weinfurter E; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20054M691	List: ML20054M690; ML20054M693;
References
	NUDOCS 8207140234
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QUAD-CITIES NUCLEAR POWER STATION UNITL 1 AND 2 MONTHLY PERFORMANCF REPORT JUNE 1982 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 i

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PDR ADOCK 05000254 R PDR t

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. Glossary

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 veneral 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.

Canmercial 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 192.

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SUMMARY

OF OPERATING EXPELIENCE , 't i

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A. UNIT ONE ', "

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- 1 June 1-4: The unit began the month increasing load after an end of' May maintenance outage. The unit is still derated due to end of

cycle fuel depletion /coastdown. On June 2 the Load Dispatcher requested a load reduction of 100 MWe due to low system demand. ,9 June 5-8: On June 5, the unit dropped load to 320 MWe to work on a Turbine control valve scram skitch. At 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months , on June 6, load was further reduced and the Tusine was tripped toi complete work on the control valve. The Reactor was maintained 'in b Hot Standby condition.

The Generator was put back cm line at 1514 hourV on June 6, and the unit continued pickinc up load to '637 MWe. 'is

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June 9-12: On both June 9 and 10 the 'mit load was redeced to 300 MWe to work on the RCIC Sys tem tes, table check valve. '

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June 13-30: Due to low ,sysG m' demand, Unit One was requested on nine occasions to reduce load, f rom Midr.ight to approximately 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months .

At all other times the uni,t was maintained at an average load of 550 MWe. i , i i / ,

B. UNIT TWO (

Unit Two starte6 he nnr derated-tc/ ddHWaduetoh'ighvibrationin the 2A Reci rculation + pump, Motor G,:<yerator Set. On Jun'e 6,'at 0315 hours0.00365 days 0.0875 hours 5.208333e-4 weeks 1.198575e-4 months , the unit dropped foad,100 MWe/ hour t6 700 MWe to perform weekly Turbine tests. The unit in' crease'd , load norma \ly to 789 MWe by .1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months , June 6.

, 1 June 8-11: On June Ea at 173c %} urs, ,the uni.t orbppsd load 200 MWe/ hour to 680 MWe due to Coraiensate Deminerdilrop problems. After several hours, the unit resulned a load increase to 775 MWe. -

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June 12-21: On June 12, at 0012 hourd;.the 2A Recirculation pump Motor-Generat[or Secc was tested t'o deterrflae the 'cause for the high vibrattor, ;t.was exhibiting. Thl's drcep$d load to 420 MWe. The Recirculation pumE was 'rlstarted and ? ped was increased as required to complete the t,est. On June 20 the urik decrea' sed load to 700.MWe to perform weekly Turbing tests. The unit thent increased load normally. On June 21 the Load,Disisatcher requested the unit to reduce load to 670 MWe due to low system demand. ..t ;

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June 22-28: On June 22, at(0526 hdors, the/ unit'scranrned on a low keactor water level' slopal . This was caup'ed by h loss of

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Feedwater pumpt Thy unitells cri.dic'al'on Jude 24 at 1445 ' power hoursto one and' was Reac'tcr on line at 120 MWe by 2302 fda'rs. Tha." unit increased, load normally to'750

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O B. UNIT TWO (Continued)

June 29-30: At 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , on June 29, the unit reduced load to 600 MWe due to Condensate Demineralizer problems. The problem was resolved and the unit was at 725 MWe by 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months . At 1115 hours0.0129 days 0.31 hours 0.00184 weeks 4.242575e-4 months the unit continued increasing load until a limiting condenser back-pressure was reached at 760 MWe. The high backpressures are a result p of high circulating water temperatures.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications On April 28, 1982, Amendments 76 and 70 were issued to Licenses DPR-29 and DPR-30, respectively. These amendments revise the requirements and methods used to inspect and test safety related shock suppressors (snubbers). They.also update the Technical Specifica-tion Table listing the safety related shock suppressors (snubbers).

On May 27, 1982, Amendments 78 and 72 were issued to Licenses DPR-29 and DPR-30, respectively. These amendments extend operation with Unit One and Unit Two "A" loops of Containment Cooling Mode of RHR crosstled to July 1, 1982. This revises the June 1, 1982, date contained in Amendments 75 and 68 to DPR-29 and DPR-30, respectively.

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 Equipnent l The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period. The headings indicated in this summary include: Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects l on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION

Q19642 RHR Pump A & B The fluid reservoir The snubber was in- The reservoir was i Snubber pt. 12 was leaking. ope rabl e. replaced and filled with fluid.

Q19643 RHR Pump A-5 B The fluid. reservoir The snubber was still The reservoir was Snubber pt. 11 was leaking. ope rabl e, replaced and filled i with fluid.

Ql5542 Electromatic Steam cutting was Steam was leaking The pilot valve was Relief Valve .found on the valve through the pilot replaced and the relief Pilots 1-203-38 seat. valve. The relief valve was tested valve was still satisfactorily.

ope rabl e.

QI9420 1/2 Diesel The motor was faul ty. The cooling water pump The motor was replaced Generator Cooling was inoperable. Unit I and tested satisfactorily.

Water Pump and 2 Diesels were j 1/2-3903 operable.

t Q19636 CRD F-06 Water was seeping There was a small leak The CRD was replaced.

-through to the CRD into the Drywell.

position probe.

QI9660 Rupture Disc The rupture disc was The safety valve was The rupture disc was i 1-203-4A Safety to rn . still operable. replaced.

Valve Q19662 82-10/03L 1/2 Diesel The motor was loose The pump motor was The motor base was Generator Cool ing on its mounting pad. experiencing extremely regrouted and the shaft Water Pump high vibration. coupling was re-aligned.

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UNIT ONE MAINTtNANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER _ 0F ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q19663 1-1001-7A RHR The torque switch The. valve only opens A new torque switch Suction Valve contacts were dirty. a little, then stops. was installed.

RHRS was still operable.

Q19669 CRD 46-15 The piston seals Water was ' leaking into ' The Accumulator was Accumulator . we re wo rn . the air side of the replaced.

Accumulator. Scram function was unaf fected.

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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 Q18152 LPRM 48-25C The connector was The LPRM was reading The connector was faulty. downscale. replaced and proper operation veri fied.

Q19326 SRM 21 The drive bearings SRM 21 was pegged The bearing in the 2-757 were worn. downscale. drive mechanism was replaced.

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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.I. ' and 6.6.B.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 82-11/0lT 6-5-82 #4CV Fast Closure Solenoid Failure to Actuate R2-12/01T 6-22-82 1/2 Diesel Generator Trip 82-13/03L 6-21-82 Unit 1 Diesel Generator Cooling Water Pump Failure UNIT TWO 82-09/03L 6-22-82 3C RV Failure to Open

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

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions 1

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v OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATEJulv 02 1982 COMPLETED BYErich Weinfurter TELEPHONE 309-654-2241xi92 '

OPERATING STATUS ' ~

0000 060182

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1. Reporting period 2400 063082 Gross hours in reporting period: 720

2. Currently authorized power level (MWt): '2511 Hox'. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

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

4. Reasons for restriction (if any):

This Month Yr.to Date Cumulative

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'720'0.

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5. Number of hours reactor'was critical" . ~4224.4f 73323.5

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 706.9 -4168.9 70300.4

'U. Unit reserve shutdown hours.

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0 . 0_ 0 .~ 0 ~ 909.2

9. Gross thernal energy generated (MWH) 1160934 8776601 143834960 LO. Gross electrical energy generated (MWH) 369796 2858018 46306951

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ti. Net electrical energy generated (MWH) '334133 2628073 ~ 43212157 L2. Reactor service factor 100.0 97.3 82.5

13. Reactor avo11ob111ty factor 100.0 97.3 86.4

14. Unit service factor 98.2 96'0 79.i_

l 15. Unit avo11obility factor 98.2 96.0 , 80.1 L6. Unit copocity factor (Using MDC) 6'0.3 78.7 63.2 L7. Unit capacity factor (Using Des.MWe) 58,8 76.7 61.6

10. Unit forced outage rate _ i.8 2.1 6.8

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

20. If shutdown'ot end of report period, estimated date of star tup ____NA _______,_

l tihe IGC not k lever then 769 leie dering perleds of high enblent tenperatere due to th'tkrnel perfernance of the sprey comel.

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OPERATING DATA REPORT DOCKET HO. 50-265 UNIT TWO DATEJulv 02 1982 COMPLETED BYErich Weinfurter TELEP HONE 309-654-2241'xi92 OPERATING STATUS 0000 060182~

1. Reporting period 2400 063082 Gross hours in reporting period 720

2. Currently auth~orized' power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

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

4. Reasons for restriction (if any): ,

This Month Yr.to Date- Cumulative

'662.7

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5. Nunber of' hours reactor was critical '3183.0 68034.8

6. Reactor reserve shutdown hours 0.0 0.0 2985~8

7. Hours generator on line 654.4 3141.9 65383.1

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8.~ Unit reserve shutdown' hours. 0.0 0 . 0. ~ 702.9"'

9. Gross thernal energy generated (MWH) 1517095 '7315642 135202725

10. Gross electrical energy generated (MWH) 482882 2355889 43062129

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ii. Het electrico1 energy generoted(MWH) 461060 2241920~ 4036'6504

12. Reactor service factor 92.0 73.3 77.4

13. Heoctor ovallobility_ factor 92.0 73.3 80.7

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14. Unit service factor 90.9- 72.3 74.3~

15. Unit avo11ob111ty factor 90.9 72.3 75 i-

16. Unit capacity factor (Using MDC) 83.3. 67.1 59.7

17. Unit capacity factor (Using Des.MWe) 81.2 65.4 58.2

18. Unit forced outage rate 9i 26.7 9.5

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

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20. If shutdown at end of report period,estinated date of startup ____$^________

The MC ney be lower then 769 Ilie during periods of high enblent temperatore due to the thernal perfernance of the serer canel.

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APPENDIX B AVER AGE DAILY . UNIT POWER. LEVEL . _ . .

DOCKET NO. 50-254 UNIT ONE DATEJulv 02 1982 COMPLETED BYErich Weinfurter _

TELEPHONE 309-654-2241xi92

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MONTH June 1982 '

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 536.2 17. 462.2 _ _

2. 516.7 18. 487.7 3, 525.2 19. 479.1 ,

4. 530.0 2_0. 485.8 _ . . _

5. 439.7 21. 451.0

6. 140.6 22. ~455.8

7. 548.9 23. 485.8

8. 524.6 24. 462.2-

9. 383.7 25. 451.7 LO. 410.9 26, 475.6 _

ii. 538.9 27, 269.9

12. 490.7 28. 468.'2

13. 499.i 29. 464.9 14, 479.0 30. 462.3

15. 505.1 l 1

16. 490.2 INSTRUCTIONS On this forn, list the enrege dellt enit peser leul in ille-Met for each der in the reporting nenth Compete to the neerest dele negemett.

Then figeres ulIl be esed to plot a graph for each reporting nonth. Note that when malnen dependeble copecitt is esed for the ut electrical re.fing of the seit there not be occasions den the deilt enrege pesar leul exceeds the iHI line (or the restricted puer level line).'In such cases,the seerege daily snit power setpet sheet shoold k festeeted to esplein the apperent enenely-s

a APPENDIX.B AVE _ RAGE DAILY UNIT POWER LEVEL _. _ _

DOCKET NO. 50-265-UNIT- 'TWO

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'DATEJulv 02 i982~ ~

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COMPLETED BYErich Weinfurter ___

TELEPHONE 309-654-2241xi92

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MONTH J un e' 'i982 ,

DAY AVERAGE DAli.Y POWER LEVEL' '

. DAY AVERAGE DAILY POWER LEVEL.

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(MWe-Net)' (NWe-Net) ~

i. 724.2 _i7. 743.2 _ _ _

2. 741.8 18. 742.0'

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3. 741.5 19.'~ ~ 720.5'

4. 751.3 _ _ ___._20. 712.5 _,

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5. 739.8 21. -723.0

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'6. 739',5 '~22.

7. 742.5 _

23. -10.2

8. 731.5 24. -7.5-

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9. 749.3 '25. ~~459.0 ~~

10. 723.3 _

26. 618.7 __

11. 747.0 27. 728'6

12. 531.6 28. 704.8

13. 694.7 29. 675.2 _ _ _ _

14. 727.4 30. - 711.5

15. 726.3

16. 736.5 INSTRUCTIONS On this fwn, list the seerage delly init peser level in ille-tiet for each det la the reporting nenth.Ceapete to the neerest uhele asteett.

These tigeres win be esed to slet a grgph for each reporting senth, liete that uhen peninen dependable cepecity is used for the net electrical reling of tne salt there ney be eccesiens when the dell, eierega pesar level exceses the 199111ae (or the restricted peuer level line),In sech cases,the seerege daily snit poser setpet sheet sheeld be

- feetnoted to emplein the apparent enomly

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APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revisioi 5 DOCKET NO. 050-254 March 1978 UNIT NAME Quad-Cities Unit On COMPLETED BY E. Veinfurter 309-654-2241, DATE July 6, 1982 REPORT MONTH JUNE 1982 TELEPHONE ext. 192 u- o s E h o LICENSEE hg ag C DURATION g ga* EVENT *3 go )

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NO. DATE (HOURS) y5y REPORT NO. 3 CORRECTIVE ACTIONS / COMMENTS I

82-21 820602 S 0,0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-22 820605 F 0.0 A 5 HB VALVEX Reduce load below 45% power to work on control valve l 82-23 820606 F 13.1 A 9 HB VALVEX Unit in Hot Standby to complete work on control valve 82-24 820609 F 0.0 A 5 SF XXXXXX Reduced load to complete work on RCIC System 82-25 820610 F 0.0 A 5 SF XXXXXX Reduced load to complete work on RCIC System 82-26 820613 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-27 820616 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-28 820616 ' S 0.0 F , 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due

. to low system demand r

(final)

n P M M M M M M F "! M C"1 C""! M C"") m n C" ' (~ i 7"

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(% i APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. 050-254 March 1978 UNIT NAME Quad-Cities Unit one COMPLETED BY E. weinfurter DATE July 6, 1982 REPORT fl0NTil JUNE 1982 TELEPHONE x 92 w 5 s

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b" LICENSEE mo gg 4oA DURATION 6 EVENT b

n. o NO. DATE (HOURS) "

h$3R REPORT NO. h" CORRECTIVE ACTIONS / COMMENTS 82-29 820618 5 0,.0

F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due '

" l- to low system demand 82-30 820621 5 0.0 F 5 EA ,ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand o

82-31 820622 S 0.0 F 5- EA ZZZZZZ Load reduction requested by Load Dispatcher due to low-system demand 82-32 820624 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-33 820625 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-34 820627 5 00 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand (final)

F"'1 P M M M P"*. M M M M f"'1 M C'~J I'"? M M I' f~ T *

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

March 1978 UNIT NAME Quad-Cities Unit Two COMPLETED BY E. Veinfurter 309-654-2241, DATE July 6. 1982 REPORT HONTH JUNE 1932 TELEPHONE ext. 192 o

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DATE (HOURS) yIy REPORT NO. 8 CORRECTIVE ACTIONS / COMMENTS R

82-23 820606 5 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests 82-24 820608 F 0.0 B 5 HG DEtil N A Reduced load due to Condensate Demineralizer p roblems 82-25 820612 S 0.0 B 5 CB CKTBRK Reduced load by tripping field breaker on 2A Recirc Motor-Generator Set for test 82-26 820620 S 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests 82-27 820621 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 82-28 820622 F 65.6 G 3 CH CKTBRK Reactor scram on low water ' level due to loss of power to Reactor Feed pump when the wrong fuses were removed from the switchgear 82-29 820629 F 0.0 B 5 HG DEMINX Reduced load due to Condensate Demineralizer problems (final)

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VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the conmission:

A. MAIN STEAM RELIEF VALVE OPERATIONS 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.

VALVES NO. & TYPE PLANT DESCRIPTION-UNIT DATE ACTUATED ACTUATIONS CONDITIONS OF EVENTS RX PRESS 2 6-22-82 2-203-3A 6 Automatic 1095 Open to control 2-203-3B 1 Manual 1090 Reactor pressure 2-203-3C Failed to Open 1095 after loss of 2-203-3D 1 Manual 1090 of f-si te power, 2-203-3E 1 Manual 1095 scram, and loss of Turbine EHC &

bypass valve 2-203-3B i Manual 1020 2-203-3D 1 Manual 1020 2-203-3E I Manual 1060 RX PRESS 2 6-25-82 2-203-3C 1 Manual 400 Post-Maintenance (replace valve) 2 6-25-82 2-203-3A 1 Manual 400 Post-Maintenance 2-203-3B 1 Manual (replaced gaskets) 2-203-3D 1 Manual 2-203-3E 1 Manual B. CONTROL R0D DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There was no Control Rod Drive Scram Timing for the reporting period.

VII. REFUELINC 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. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities, and Zion Station--NRC Request for Refueling Information",

dated January 18, 1978.

F QTP 300-S32 ri ~~

l Rsvision 1 h ,* I QUAD-CITIES REFUELING March 1978 I

ki' INFORMATION REQUEST l,j r ,

b l. Unit: 1 Reload: 6 Cycle: 7 l

m 2. Scheduled date for next refueling shutdown: Sept 12, 1982 I

L. I 3 Scheduled date for restart following refueling: Dec 4, 1982 l

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

1 YES I

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

. Information:

o ' JULY 26, 1982 l

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

[ ,' ' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

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ItiPLEl1ENTATl0N OF THE ODYN TRANSIENT ANALYSIS CODE AND RESULTS (itCPR SCRAM Til4E DEPENDENCE) :

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e 7 The number of fuel assemblies.

a. Number of assemblies in core: 224 new/724 total

- after the

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

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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 - 3/84- */ t Fa p Ft () \/ E [>

V LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 APR 2.01978

, CD.c:.C).55.Ft.

N .me 6 m n. .,, ,. g & c- a + e o

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I QTP 300-S32 W~* QUAD-CITIES REFUELING R vision 1 March 1978

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INFORMATION REQUEST l~~

u 1. Unit: 2 Reload: 6 Cycle: 7 l

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

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

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

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

. Information:

NONE

6. Important licensing considerations associated with refueling, e.g., new or f, ' different fuel design or supplier, unreviewed design or performance analysis

/ methods, significant changes in fuel design, new operating procedures:

),'^' .

UONE l

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7 The nuraber of fuel assemblies. -

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

b. Number of assemblies in spent fuci pool: outage 2132 Y

y 8. The present licensed spent fuel p~ool storage capacity and the size of any increase in IIcensed storage capacity that has been requested or is planned in number of fuel assembites:

a. Licensed storage capacity for spent fuel: 2920

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

V LOSS OF FULL CORE DISCHARGE CAPABILITY - 3/84 LOSS OF RELOAD CORE DISCHARGE CAPABILITY - 2/86 WPPROVED APR 2.01978 Q. c. O. S. R.

,,,e _ . , . . , ~~ - & e e.o

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 ANSI -

American National Standards Institute APRM -

Average Power Range Monitor ATWS -

Anticipated Transient Without Scram BWR -

Boiling Water Reactor CRD -

Control Rod Drive EHC -

Electro-Hydraulic Control System EOF -

&nergency Operations Facility GS EP -