Text

Monthly Operating Repts for June 1984
	ML20093E530
Person / Time
Site:	Quad Cities
Issue date:	06/30/1984
From:	Kalivianakis N, Kimler D; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NJK-84-206, NUDOCS 8407180008
	Download: ML20093E530 (24)
	v • d • e

F QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT F JUNE 1984 CGIMONWEALTH EDISON COMPANY AND 10WA-1LLIN0lS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 f k0KO 162N R

o TABLE OF CONTENTS 1, Introduction ,

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11. Summary of Operating Experience A. Unit One B. Unit Two 111. 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 Powe r Reductions VI, Unique Reporting Requirements A. Main Steam Relief Valve Operations B, Control Rod Drive Scram Timing Data Vil, Refueling Information Vill, Glossary

p 1, INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling 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 lowa-1111nois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors. The Architect / Engineer was Sargent &

Lundy, incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling wa ter source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively; pursuant to Docke t Numbers 50-254 and 50-265.

The date of initial Reactor critica11tles for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Comme rcial generation of power began on February 18, 1973 for Unit One and March 10,1973 for Unit Two.

This report was complied by Becky Brown and Dave Kimler, telephone number 309-654-2241, extensions 127 and 192.

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11,

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Unit One remained shutdown throughout the ne th for End of Cycle Seven Refueling and Maintenance.

B. Unit Two June 1-10: Unit Two began the month reducing load in preparation for unit shutdown. On June 2, at 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months , the Turbine was tripped and at 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months the unit was scrammed to perform maintenance on an oil leak in Transformer 21. On June 4, at 0111 hours0.00128 days 0.0308 hours 1.835317e-4 weeks 4.22355e-5 months , the heactor was critical and at 1250 hours0.0145 days 0.347 hours 0.00207 weeks 4.75625e-4 months the unit began a normal load increase to full power. On June 6, at 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months , load was dropped to 600 MWe to perform Control Rod maneuvers. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months the unit began a normal load increase to full power. On June 10, at 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , load was dropped to 700 MWe to perform bi-weekly testing of the Main Steam isolation Valves. At 0150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months the unit scrammed due to a " FAST" closure of the #4 Control Valve during testing. At 1955 hours0.0226 days 0.543 hours 0.00323 weeks 7.438775e-4 months the Generator was back on-line at 124 MWe.

June 11-23: On June 11, at 1650 hours0.0191 days 0.458 hours 0.00273 weeks 6.27825e-4 months , load was reduced at 20 MWe/ hour to allow Maintenance to perform repairs on a Feedwater Heater Valve.

At 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months , on June 12, the unit began a normal load increase to full power. On June 13, at 0000 hours0 days 0 hours 0 weeks 0 months , load was dropped to 600 MWe to perform Control Rod maneuvers. At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months a normal increase to full power was initiated. On June 16, at 2355 hours0.0273 days 0.654 hours 0.00389 weeks 8.960775e-4 months , load was dropped to 700 MWe to perform weekly Turbine tests. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months , the unit began a normal load increase to full power.

June 24-30: On June 24, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , load was dropped to 700 MWe to perform weekly Turbine tests. At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months the unit began a normal Icad increase to full power. On June 30, at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months , load was dropped to 700 MWe to perform weekly Turbine tests.

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Ill. . PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

.A. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

4 B. Facility or Procedure Changes Requiring NRC Approval There were no facility or Procedure changes requiring NRC approval for the = reporting period.

C. Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety j related maintenance performed on Unit One and Unit Two during

the reporting period. .This summary includes the following headings: Wbrk Request Numbers, LER Numbers, Components,

Cause of. Malfunctions, Results and Effects on Safe Operation, i 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 Q26819 4KV/480V Transformers 18 & No " hot" spots or No further action is Trans forme rs 19 were inspected abnormalities were being considered for 18 & 19 for faulty found, therefore, Unit 1. Transformers connections using there are no safety 28 & 29 will also be thermovision implications. inspected.

camera as response to NRC Bulletin IE 83-37 Q33802 M0 1-202-4A Valve disc was net Valve has no PCI Stem was replaced and Valve completely seating. function. In case of disc was polished. No a pipe break, valve further corrective would have limited action is being flow to 5 gpm. considered.

Q34098 Reactor Pressure Micro-switch The Reactor was The micro-switch was Permissive contacts failed shutdown at the replaced.

Switch for Core OPEN. time of discovery Spray injection and redundant Core 1-263-52B was Spray System was inoperable operable.

Q34538 84-5 Weld Repair Unknown. Suspect Indication was not The crack was repaired, Leak on 'H' Jet IGSCC induced 100%.through wall and then a weld overlay Pump Riser -- axial indication until treated with was performed as Weld 0211-S3 worsened by 1d51. IHSI. designed by Nutech Engineers, Inc.

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.. UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER' 0F ON ACTION TAKEN TO NUMBER NUM8ER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q34539 84-5 Veld 02H-S4 on Unknown. Suspect The indication was Repaired pipe by

'H' Jet Pump IGSCC induced not 100% through- peening and welding, Riser axial indications. wall until treated then weld overlay was with IHSI. performed as designed by Hutech Engineers, Inc.

Q34541 84-5 Veld 02J-S4 on Unknown. Suspect Indication was not Repaired leak by

'J' Jet Pump IGSCC induced 100% through wall welding and then weld Riser axial and until treated with overlay was performed as c i rcumfe rent ia l IHSI. designed by Nutech indications. Engineers, Inc.

. q34544 84-5 Weld 02J-F6 on Unknown. Suspect The crack indications Repaired leak by

'J' Jet Pump IGSCC induced were nearly 100% welding'and then weld Riser axial indications. but the maximum axial overlay was performed as indication was li designed by Nutech

. inches long. Engineers, Inc.

Q34718 84-5 Veld 02J-S3 on Unknown. Sespect Indication was not Repaired leak by

. 'J' Jet Pump IGSCC induced 100% through-wall welding and then weld Riser' axial and until treated with - overlay was performed as circumferentici IHSI. designed by Nutech indications. Engineers, Inc.

Q34887 84-5 Weld 02B-S7 Unknown. Suspect Indication was not Leak was repaired by on 0-Ring IGSCC induced 100% through wall welding, then a weld Header axial indication, until treated using overlay was performed lHSI. as designed by Nutech Engineers, Inc.

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UNIT ONE MAINTENAN'CE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q35641 Reset Lift Metallic foreign The latest monthly The relief valve was Pressure of IB material prevented operating flow replaced and Standby Liquid valve from seating surveillance was successfully tested Control Relief and subsequently satisfactory. The six times.

Valve 1-11053 system pressure unit was shutdown could not reach and the 1A Standby the required 1400 Liquid Control pump to 1490 psig. could achieve the required 1400 psig.

Therefore, the safety implications of this occurrence are minimal.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q30722 Replace Elbow During the Fall 1983 Indication was not Elbow was replaced as on Reactor ISI, and IGSCC was 100% through-wall. designed by Nutech Water Clean-up identified and a Engineers, Inc.

Line 2-1202-6"A weld repair could not be accomplished; therefore, the elbow was replaced.

Q31042 83-21/01T Weld 2BS-F7 Unknown. Suspect Indication was not Weld was treated using on 'B' lGSCC induced 100% through-wall. lHSI then weld overlay Recirculation circumferential was performed as Suction indication. designed by Nutech Piping Engineers, Inc.

Q35387. Repalced PCI Coil on relay was This relay is one of Replaced the relay.

Relay 2-595- burnt out. four arranged in one-104D out-of-two-twice logic. Failure of this relay did not prevent or cause a Group 11 isolation.

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IV , LICENSEE EVEKr REPORTS The following is a tabular summary of all licensee (>cnt 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 tF, Technical Specifications.

Unit One Licensee Event Report Number Date Title of Occurrence 84-10 5-30-84 IRH Reactor Scram 84-11 6-15-84 Reactor Scram 84-12 6-22-84 RHR Service Water Vault Sump Pump Discharge Check Valves Leak Excessively Unit Two 84-6 6-1-84 Tardy Weekly Surveillance 84-7 6-10-84 Reactor Scram -- #4 Turbine Control Valve L_____ _ _ _- , ,,_,

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

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[ OPERATING DATA REPORT DOChET NO. 50-254 UNIT ONE DATEJULY 9

-! - COMPLETED BYDAVE KIMLER TELEPHONE 309-654-224iXi92 OPERfTING STATUS 0000 060184

.t. Reporting period 2400.063084 Gross hours in reporting period: 720

, 2'. Currently.outhorized power level (MWt): 2511 Max. Depend copocity

.(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):

j This Month Yr to Date CumulotIve

5. Number of hours reactor.was critical 0.0 1562.1 85117.7

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 0.0 1561.2 81909.1

8. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thernal energy generated (MWH) 0 3659732 168766438

10. Gross electrical energy generated (MWH) 0 1213148 54471764

11. Net electrical energy generated (MWH) -2634 1147630 50753597

12. Reactor service factor 0.0 35.8 80.0

13. Reactor availability factor 0.0 35'.8 83.2

14. Unit service.fuctor 0.0 35.7 77.0

15. Unit _ovo11obility factor 0.0 35.7- 77.8

16. Unit capacity factor (Using MDC) 5 34.2 62.0

.17 . Unit capacity factor (Using Des.MWe) .5 33.3 160.4

- 18 . . Unit forced outage rate- 0.0 0.0 6.1

'i9. Shutdowns scheduled'over next 6 months-(Type,Date,ond Durotion of each):

30. If shutdown at end of report p er i o d , e st inat ed d at e o f s t ar t up ]__3_0-84 _,_____,

8The llBC not be louer then %9 mie dering perleds of high enblent tenperatore see to the thernal perfernece of the sprep cenel.

WlOFFICIAl. COMPANY NWIIERS ARE UIED IN THIS RDORT u

OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATEJULY 9 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 OPERATING STATUS 0000 060184

1. Reporting period 2400 063084 Gross hours in reporting period 720

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (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 Cumulotive

5. Number of hours reactor was critical 656.5 2821.1 80738.6

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 644'.2. P711. 0_ 77920.8

8. Unit reserve shutdown hours. 0.0 0.0 702.9

9. Gross thernal energy generated (MWH) 1482529 6279983 161662071

10. Gross electrical energy generated (MWH) 474417 2038706 51474486 11.' Net electrical energy generated (MWH) 453336 1940177 48274237 12.- Reactor service f ac tor 91.2 _

64.6 76.5

13. Reactor availability factor 91.2_ 64.6 79.4

14. Unit service factor- 89.5 62.1 73.9

15. Unit avo11obility factor 89.5 62.1 74.5

16. Unit-capacity factor (Using MDC) 81.9. 57.8 59.5 17._ Unit capacity _foctor (Using Des.MWe) 79.8 56.3 58.0

10. Unit forced autoge rote 2.7 5 ~. 2 8.5

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

20.'If shutdown at end of report p er i o d ,e st ina t e d dat e o f s tar t u p __NA__________

SThe 110C not be lower then 769 Inle dering perleds of high enblent tenperatore due to the thernel perfernece of the sprer canel.

81BIDFFICIAl. C3flPAlti implIERS ARE USED Ill THIS REPORT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATEJULY 9 COMPLETED BYDAVE KIMLER TELEPHONE 309-654-2241Xi92 MONTH June'1984 DAY AVERAGE-DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (NWe-Net)

1. -2.5 17. -3,0

2. -2.6 18. -3.2

3. -2.5 19. -3.2

4. -2.5 20. -3.2

5. -2.4 21. -

-3.1

6. -2.7 22. -2.9

7. -2.9 23. -2.8

0. -3.0 24. -2.8

9. -2.8 25. -2.7

10. -2.9 26. -3.0

11. -2.0 27. -2,9

12. -2.B' '28. -2.9

13. -i.9 29. -3.3

14. -2.8 30. -3.7 15 .- -2.7

16. -3.2 INSTRUCTIONS On this forn, list the enrage dellt enit paar level in IWe-Net for ecch day in the reporting nenth. Compete to the nearest uhele negewett.

These figures allt be used to plot u graph for each reporting nenth. Note that uhen notinen dependeble cepecite is used for the net electrical reting of the ennt there ney be occasient when the daily eseroge pwer level enceeds the 10H line (or the restricted power level 1.:e).,In suh cases,the estrege daily enit power eetpet sheet should he -

. feetnoted to explain the apperent enenely I

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i APPENDIX D AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEJULY 9 COMPLETED BYDAVE KIMLER TELEPHONE 3_j}9-654-2241Xi9q I

HONTH June 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL .

(HWe-Net) (MWe-Net)

1. 731.5 17. 764.2

2. 14.4 10. 763.3

3. -0.4- ,

19, 759.8

4. 148.8 20. 759.2

5. 556.8 21, 760.3

6. 647.6 22. 759,2

7. 745.3 23, 762.5

8. 776.4 24. 758.1

9. 764.9 25. 762.7 to. 77.5 26, 761.9 11, 203.2 27. 751.0 12, 550.2 20. 771.0 13, 619.4 29, 779.8

14. 757.7 30. 743.5 15, 763.2 16, 759.0 INSTRUCTIONS On this forn, list the onrege daily enit pouct level in Mlle-Net for each day in the reporting nonth Compete to the peertst whole Mgewett.

These figeres will be esed te plot a graph for eeth reperting unth. Note that when notinen dependable capacity is ofgj for the net electrical reting of the snit there not be eccesions when the delly everage power level exceeds the test line (or the restricted power level line),In. soth cases,the everage dolly snit power evtpet sheet shtold be feetnoted to esplein the opperent onently

M M M M M M M M M M M M M M M M y c.

ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY D Kimler DATE July 10, 1984 REI' ORT HONTII JUNE 1984 TELEPIIONE _

309-654-2241 N $ g w" 5 $EE gm Ww

&$ y M LICENSEE m@ O h

w DURATION @

EVENT $" o NO. DATE (IIOURS) REPORT NO. CORRECTIVE ACTIONS / COMMENTS ca 84-14 840306 S 720 C 1 RC FUELXX Unit One remains shutdown for End of Cycle Seven Refueling and Maintenance APPROVED AUG 1 G 1982 (final) ygg3g

M M M M M M M M M M M M M M M f

cx ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY D Kimler DATE _ July 10, 1984 REPORT HONTil JUNE 1984 TELEPil0NE 309-654-2241 N e w" 5 $EE gm Am g@ "e M LICENSEE m@ @@

w DURATION d EVENT $U $U NO. DATE (IiOURS) "oo REPORT NO.

U CORRECTIVE ACTIONS / COMMENTS 84-19 840601 S 6.5 B 5 RC CONROD Reduced load for rod maneuver in preparation for unit shutdown 84-20 840602 S 57.8 8 2 ED TRANSF Manually scrammed unit to repair oil leak on Transformer 21 84 840606 S 2.0 H 5 RC CONROD Reduced load to perform Control Rod maneuver per Nuclear Engineer 84-22 840610 S 1.1 B 5 CD VALVEX Reduced load to perform bi-weekly Main Steam Isolation Valve test 84-23 840610 F 18.1 A 3 CC VALVEX Reactor scram due to " FAST" closure of

4 Control Valve during testing 84-24 840611 S 11.7 8 5 CH VALVEX Reduced load to allow Maintenance to work on Feedwater Heater Valve 84-25 840613 S 0.5 H 5 RC CONROD Reduced load to perform Control Rod maneuver per Nuclear Engineer APPROVED AUG 1 G 1982 (final) ygg3g

M M F""1 M M M .

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M M M M M M M y ID/5A APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY D Kimler DATE July 9, 1984 REPORT MONTil JUNE 1984 TELEPIIONE 309-654-2241 N $ e w" 5 $EN gw $w g@ Q M LICENSEE m@ @

NO. DATE w DURATION @ "

EVENT REPORT NO.

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(110URS) CORRECTIVE ACTIONS / COMMENTS a

84-26 840616 S 2.5 B 5 HA TURBlN Reduced load to perform weekly Turbine tests 84-27 840624 S 1.5 B 5 HA TURBIN Reduced load to perform weekly Turbine tests 84-28 840630 S 2.0 B 5 HA TURBIN Reduced load to perform weekly Turbine tests APPROVED AUG 101982 (final) ygg3g

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 Two There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

Vll, REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D, E, O'Brien to C, Reed, et al. , titled "Dresden, Quad-Cities, and Zion Station-NRC Request for Refueling Information",

dated January 18, 1978.

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QTP 300-S32

. Rsvision 1

$-- QUAD-CITIES REFUELING liarch 1978 e INFORMATION REQUE;T q

1 1. Unit: Q1 Reload: 7 ,

Cycle; 8

. Refueling Outage

2. Scheduled date for next refueling shutdown: Currently in Progress 3 Scheduled date for restart following refueling: 7-30-84

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: Ye . . Preparatory Technical Specification changes have been submitted to include PAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.

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

. Information:

Technical Speci fication change has been submitted February 21, 1984.

6. Important IIcensing consideratio7s associated with refueling, e.g., new or

' different fuel design or suppIIer, unreviewed desigr. or performance analysis methods, significant changes in fuel design, rew operating procedures:

1) All new fuel assemblies will be CE7B-type (barrier clad, extended exposure design).

2) A generic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

3) Four Barrier Lead Test Asser:.blies will be re-inserted to gather

[ information on the effects of extended exposures.

I 7. The number of fuel assemblies.

a. Number of assemblies in core:- 724

b. Number of assemblies in spent fuel pool: 1926 j 8. The present IIcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requestea or is planned j in number of fuel assemblies:

1 a. Licensed storage capacity for spent fuel: 3657

b. Planned increase in IIcensed storage: 0 l 9 The projected date of the last refue1Ing that con be discharged to the

{ spent fuel pool assuming the present Ilcensed capacity: 2003 L

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XPPROVED f ,

APR 2 01978 i,

Q.C.O.S.R.

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. QTP 300-S32

! Rsvision 1 I

QUAD-CITIES. REFUELING Harch 1978

{, INFORMATION REQUEST

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} 1. Unit: Q2 Reload: 7 Cycle: 8 it 2. Scheduled date for next refueling shutdown: 3-18-85 f

l 3 Scheduled date for restart following refueling: 5-26-85 l

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

E Not as yet determined.

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

. Information:

January 18, 1985, i f I tcensing action required.

f 6. Important IIcensing 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:

I) All new fuel assemblies will be GE7B-type (barrier clad, extended exposure design).

2) A generic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

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"- 7 The number of fuel assemblies.

a. Number of assemblies in core: 724 I

b. Number of assemblies in spent fuel pool: 414

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

a. Licensed storage capacity for spent fuel: 3897

b. Planned increase in IIcensed storage: 0 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003

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WPPROVED m

APR 2 01978 Q.C.O.S.R.

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