ML20140C419

Monthly Operating Repts for May 1984

ML20140C419
Person / Time
Site:	Quad Cities
Issue date:	05/31/1984
From:	Kalivianakis N, Kimler D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-84-186, NUDOCS 8406190347
Download: ML20140C419 (23)

Text

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT MAY 1984 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 5

l 8406190347 840531 PDRADOCK05000g R

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TABLE OF CONTENTS I, Introduction

. I I, Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Expertnents, 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 Infonnation VIII, Glossary

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i I. 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 Iowa-Illinois Gas & Electric Company.

i The Nuclear Steam Supply Systems are General Electric Company  ;

i Boiling Water Reactors. The Architect / Engineer was Sargent &

bundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license  !

numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor criticalities for Units One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial  ;

generation of power began on February 18, 1973 for Unit One and March 10,1973 for Unit Two.

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

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SUMMARY

OF OPERATING EXPERIENCE A. Unit One Unit One remained shutdown throughout the month for End of Cycle ,

, Seven Refueling and Maintenance.

B.- Unit Two May 1-8: Unit Two began the month shutdown for a scheduled Maintenance Outage to replace the 2A Circulating Water Pump Discharge Valve. 'At 1425 hourc, on May 8, control rods were pulled to achieve criticality. At 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> the Reactor was critical. At 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br /> the Reactor was manually scrammed due to a leaking pilot valve on the 2-203-3C Main Steam Relief Valve.

E May 9-31: At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, on May 9, rods were pulled for criticality.

At 0807 hours0.00934 days <br />0.224 hours <br />0.00133 weeks <br />3.070635e-4 months <br /> the Reactor was critical. At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> the Generator was synchronized and on-line at 90 MWe. At 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br />, on May 11, i

-the load increase ~was interrupted due to a sticking #1 Turbine .

-Control Valve. At 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br /> the load increase to full power was resumed. At 1640 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.2402e-4 months <br />, on May 15, load was dropped to 700 MWe for bi-weekly Main Steam isolation Valve' testing. At 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> the unit "

began a normal load increase to full power. At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, on May 20, load was dropped to 700 MWe for weekly Turbine tests. At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> .

the unit began a' normal load increase to full power. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on May 22, load was dropped to 725 MWe to perform Main Steam isolation Valve testing. At 0222 hours0.00257 days <br />0.0617 hours <br />3.670635e-4 weeks <br />8.4471e-5 months <br /> the unit began a normal load increase to full power. At.0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, on May 27, load was dropped -

to 700 HWe for weekly Turbine tests. At 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br /> the unit began a

• normal load increase to full power. .

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i III. PIANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifica-tions There were no' Amendments to the 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 or Experiments requiring NRC ,

approval for the reporting period. .

.D. Corrective Maintenance of Safety-Related Equipnent .

The following represents a tabular summary of the major safety-related maintenance performed on Unit One and Unit Two during the reporting period. This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Hal functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER -

0F ON ACTION TAKEN T0 s NUMBER NUMBER COMPONENT MALFUNCTION ' SAFE OPERATION PREVENT REPETITION i

Q34719 84-7 IB RHR Service The cause of this The leak .ates The leaking penetration Water Vault occurrence was pipe encountered vere will be repaired and

. Penetration vibration and small enough that tested before unit

l Leaks subsequent loosening the RHR Service startup.

of the penetration Water Vault Sump l seals. Pumps could have These penetrations are adequately dis- tested for leakage charged any water once an operating which may have leaked cycle. This is through; therefore, considered adequate to the effect on safe keep significant cperation is minimal. leakage from the penetrations in check.

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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 Q29617 83-20/OlT Weld Number Unknown. Suspect Indication was not 100% Weld overlay was 02BS-S3 on IGSCC induced th rough-wa l l . performed as designed

'B' Recircula- circumferential by NUTECH Engineers, tion Suction crack indication. Incorporated.

Line ,

Q29618 83-20/OlT Weld Number Unknown. Suspect , Indication was not 100% Weld overlay.was 02BD-S6 on IGSCC induced through-wall. performed as designed

'B' Recircula- ci rcunfe rential by.NUTECH Engineers, tion Discharge and axial incorporated. .

Line indications.

Q29619 83-21/OlT Weld Number Unknown. Suspect Indication was not 100% Weld was treated using

.02AS-59 on IGSCC induced through-wall, lHSI, then weld overlay ,

'A' Recircula- circumferential was performed as t

tion Suction and axial designed by NUTECH l Lane indications. Engineers, I nco rpo ra t.ed .

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( Q29968 83-20/0lT Weld Number Unknown. Suspect Indication was not 100% Weld was treated using l 02G-53 on IGSCC induced through wall. lHSI, then weld overlay .

i 'G' Jet Pump ci rcumferent i al was performed as l

Riser and axial designed by NUTECH indications. Engineers, incorporated.

Q30825 83-20/OlT Weld Number Unknown. Suspect Indication was not 100% Weld overlay was 105-FI, RHR IGSCC induced through-wall. performed as designed  ;

Shutdown ci rcumfe rential by NUTECH Engineers, l Cooling Line indication. Incorporated.

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l Q30879 83-21/0lT Weld Nunber Unknown. Suspect Indication was not 100% Weld was treated using 02F-F6 on IGSCC induced through wall. lHSI, then weld overlay

. 'F' Jet Pump ci rcumfe rential was performed as Riser indication. designed by NUTECH Engineers, incorporated.

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1 UNIT TWO MAICTENANCE

SUMMARY

. CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO IIUMBER NUMBER C0ff0NENT MALFUIICTION SAFE OPERATION PREVENT REPETITION q30949 83-21/0lT Weld Number Unknown. Suspect Indication was not 100% Weld was treated using 02J-F6 IGSCC induced th rough-wal l . lHSI, then weld overlay ci rcumferential was performed as indication. designed by NUTECH Engineers, incorporated.

Q32305 IRM 11 Did not respond to too effect on safe Installed new detector, flux change; operation. IRM 11 put detector reached in Bypass until end of life. repaired.

Q34550 2E Electro- Drain line sheared The sheared drain line Line was immediately matic Relief off. Probable would not inhibit the replaced, in addition, Valve cause - excessive operation of the Engineering has an Condensate vibration. relief valve, architect engineer Drain Line analyzing the problem.

Q34724 84-5 3C and 3E The seating There were no effects New pilot valves were

& Electromatic surfaces of the on safe operation as installed and tested.

Q34725 Relief Valve valves were found the Electromatic Relief These pilot valves are Pilot Valve to be scored in Valves were fully replaced during each several areas. operable at all times. refueling outage, in This scoring is addition, procedures attributed to dirt call for monitoring accumulating relief valve discharge between the mating line temperatures very surfaces. closely and recording each valve's daily temperature. These practices have prevented

. pilot valve seat leakage as a mode of Electro-matic Relief Valve failure.

O

e 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 reportahic occurrence reporting requirements as set forth in sections 5.6.B.l. and 6.6.B.2. of the Technical Specifications.

UNIT ONE ,

Licensee Event Report Number Date Title of Occurrence 84-6 5-1-84 Potential Secondary Containment Problem 84-7 5-7-84 RHR Service Water Vault Penetration Leak 84-8 5-11-84 125 Volt DC Battery Charger Re-evaluation 84-9 5-19-84 IRM Reactor Scram UNIT TWO 84-5 5-8-84 Electromatic Relief Valve Pilot (repai r)

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,y V, DATA ' TABUIATIONS The following data tabulations are presented in this report:

A, Operating Data Report B ,' Average Daily Unit Tower Level C, Unit Shutdowns and Power Reductions  ;

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s OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE f

DATEJune 7 1984 COMPLETED BYDave Kinler TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 050184

1. Reporting period:2400 053184 Gross hours in reporting period: 744

'2. Currently authorized 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 Cunulative S. 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. 0f 0.0 909.2

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

10. Gross electrical energy generated (MWH) 0 1213148 54471764 ii. Het electrical energy generated (MWH) -2109 1150264 50756231 12.~ Reactor service factor 0 . 0_ 42.8 80.5

13. Reactor availability factor 0.0 42.8 83.8 14.. Unit service factor 0.0 42.8_ 77.5

15. Unit availability factor 0.0 42.8 78.4

16. Unit capacity factor (Using MDC) .4 41.0 62.4

17. Unit capaci'ty factor (Using Des.MWe) .4 40.0 60.9

18. Unit forced outage rate 0.0 0.0 6.1

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

20. If shutdown at end of report per i od ,e st inated d ate o f s t ar t up ___];gD _8}____ _

' 8The MDC ney be lower then 769 mie dering perleds of high onbient tenperature due to the thernel perfernance of the sprey canel.

$UNOFFICIALCOMPANYIUlKRSAREUSEDINTHISREPORT L

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. OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATEJune 7 1984 COMPLETED BYDave Kinler TELEPHONE 309-654-2241xi92 OPERATING STATUS 0000 050184

1. Reporting period:2400 053184 Gross hours in reporting periodi 744 2.-Currently authorized 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):

This Month Yr to Date Cumulative

5. Number of hours reactor was critical 546.7 2164.6 80082.1

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 534.5 2066.8 77276.6 0.-Unit reserve shutdown hours. 0.0 0.0 702.9

9. Gross-thernal energy generated (MWH) 1270133 4797454 160179542

10. Gross electrical energy generated (MWH) 415708 1564289 51000069

11. Het electrical. energy generated (HWH) 395987 1486841 47820901

12. Reactor service factor 73.5 59_4 76.4

13. Reactor avullability factor 73.5 59.4 79.3

14. Unit service factor 71.8 56.7 73.8

15. Unit'avo11obility factor 71.8 56.7 74.4

16. Unit copocity factor (Using MDC) 69.2 53.0 59.3

17. Unit capacity factor (Using Des.MWe) 67.5 51.7 57.8

10. Unit forced outage rate 4.0 5.9 8.6

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

20. If shutdown at end of report period ,estinated date of star tup ___NA __________

8The 10C nor be lower then 769 lh dering perleds of high on6ient tenperatore due to the thernal perfernance of the spray canel.

l $ UNOFFICIAL. COMPANY NUNKRS ARE USED IN THIS REPORT

o' APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATEJune 7 1984 COMPLETED BYDave Kinler TELEPHONE 309-654-2241xi92 MONTH Mov 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. - -5.7 17. -2.3

2. -5.0 18. -2.4

.3. -5.3 19. -2,3  ;

4. -4.8 20. -2,4

5. -3.6 21. -2.5 f

6. -2.9 22. -3.4

7. -4.8 23. -3.3

8. -6.0 24. -3.5

9. -4.4 25. -3.3

10. -3.0 26. -3.8

.ii . -2.7 27. -3.0 f l

12. -2,2 28. -3.4 _

13. -2.2 29. -3.7

.14 . -2,3 30. -2.6

15. -2.3 31. -2.6

16. -2,4 INSTRUCTIONS On this fern, list the overage dolly unit power level in Mk-Net for each do; in the reporting nenth.Conpete to the metrtst whole negewett.

These figures will be used to plot a graph for each reporting nenth. Note that when notinen dependable capotite is used for the net electrical rating of the snit there ney be ettestens when the daily average power level exceeds the 100% line (or the restricted power level line),In sich cases,the overage daily snit power evtpet sheet should be feetnoted te esplsin the apparent onenelp

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEJune 7 1984 COMPLETED BYDave Kinler TELEPHONE 309-654-224ix192 MONTH Hov 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)- (HWe-Net)

1. -6.0 17. 774.8

~2. -6.4 iB. 778.8

3. -6.0 19 , , 774.5

4. -6,4 20, 750.5

5. -5.3 21, 764.8

6. -7.0 22. 759.5

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-9.2 23, 776.2

8. - -9.6 24, 774.3

9. 01.6 25, 765.1

10. 502.7 26. 776.4

11. 547.9 27. 767.9

. ia. 762.6 28. 770.7

13. 777.3 29. 700.3 14, 705.9 30. 773.5

15. 775.3 31. 776.4 16, 778.3 INSTRUCTIONS On this fwn, list the eserege dolly enit pour level in lWe-Net for each dat in the reporting nenth Compete to the neerest uhele negewett.

These figeres will be esed te plot a graph for each reporting nenth. Note that when na:Inen dependable capacite is esed for the net electrical rating of the enkt there ney be occasions when the dellt overage power level exceeds the 1991 line (w the restricted power level line).,In such cases,the everage dsily snit power setpet sheet sheeld be festnoted to esplein the apparent anonelp

M M M M .* M M M M M M M M M M n r""1 M y c.

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 CORRECTION COMPLETED BY D Kimler DATE May 4, 1984 REPORT HONTil APRIL 1984 TEI.EP110NE 309-6S4-2241 m 5 m "' 5 $E$  % !w

$ Q h@ LICENSEE @ @

u w DURATION M $g EVENT $ o u

NO. DATE (IIOURS) o REPORT No. CORRECTIVE ACTIONS / COMMENTS ca 84-16* 84-417 F 0.0 A 5 CH VALVEX Reduced load due to failed Feedwater Regulating Valve 84-17* 840422 S 0.0 B 5 HA TURBIN Reduced load for weekly Turbine tests 84-18* 840427 S 91.0 B 1 HF VALVEX Shutdown for repair of 2A Circulating 3

Water Pump Discharge Valve l

• These numbars were incorrect y re >orted a:, "85" on the April 1984 report.

APPROVED AUG 1 G 1982 (final) VGUbH

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M M M M M M M F""1 M y ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. _05_0_-2J4 August 1982 l) NIT NAME Quad-Cities Unit 1 COMPLETED BY D. Kimler DATE _ June 5, 1984 REPORT HONTil MAY 1984 TELEPil0NE 309-654-2241 w 5 g w" 5 SE "w Ww

$ Q M LICENSEE @ @

NO. DATE w DURATION M g"g EVENT REPORT NO.

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(Il0URS) o CORRECTIVE ACTIONS /CONNENTS o

84-14 840306 S 744 C 1 RC FUELXX Unit One remains shutdown for End of Cycle Seven Refueling and Maintenance APPROVED

. AUG 1 G 1982

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M n M M M M M M M M M M M M M M M M y ID/SA APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 05_0-265 August 1982 UNIT NAME _Q uad-Cities Unit 2 COMPLETED BY _ D. Kimle r DATE June 5, 1984 REPORT MONTil

• MAY 1984 TELEP110NE 309-654-2241 m 8 e w" 5 EE "w Am

$ Q ohm LICENSEE @ 2@

w DURATION M Mg EVENT g gu NO. DATE (Il0URS) "oo REPORT NO.

u CORRECTIVE ACTIONS / COMMENTS 84-18 840427 5 187.2 B 1 HF VALVEX Shutdown for repair of 2A Ci rculating Water Pump Discharge Valve 84-19 840508 F 22.3 A 2 84-5 CC VALVEX Shutdown for repair of 2-203-3C Relief Valve Pilot Valve Assembly 84-20 840515 5 0.0 B 1 CD VALVEX Reduced load for bi weekly MSIV (Main

- Steam isolation Valve) testing 84-21 840520 S 0.0 B 1 HA TURBIN Reduced load for weekly Turbine tests 84-22 840522 S 0.0 B 1 CD VALVEX Reduced load for Main Steam isolation Valve testing 84-23 840527 5 0.0 B 1 HA TURBIN Reduced load for weekly Turbine tests APPROVED AUG 1 G 1982

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

A. MAlH 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 Acutations Conditions of Events 1 3-5-84 1-203-3A 1 Manual Rx Press Surveillance 1-203-3B 1 Manual 990 T.S. 4.5.0.1.b l-203-3C 1 Manual 1-203-3D 1 Manual ,

1-203-3E I Manual Rx Press Surveillance 990 T.S. 4.5.0.1.b (Failed to open, will be repaired during Refueling Outage) 2 5-9-84 2-203-3C 1 Manual Rx Press Post Maintenance 2-203-3E I Manual 860 (Replaced pilot valve)

B. CONTROL R0D 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.

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s-e VII. 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 Informa tion",

dated January 18 1978.

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" QTP 300-S32 R2 vision 1

$- I QUAD-CITIES REFUELING March 1978 it ,

INFORMATION REQUEST q

• J 1. Unit: QI 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 thereaf ter require a technical specification change or other license amendment: Yes. Preparatory Technical Specification changes have been submitted to include MAPLHGR 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 Spect fication change has been submitted February 21, 1984.

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) All new fuel assemb11es 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.

I 3) Four Barrier Lead Test Assemblies will be re-inserted to gather

! information on the ef fects of extended exposures.

7 The number of fuel assembiles.

a. Number of assemblies in core: 0

b. Number of assemblies in spent fuel pool: 2650 o

f., 8. The present Ilcensed spent fuel pool storage capacity and the size of any Increase in licensed storage capacity that has been requested or is planned

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in number of fuel assembites:

1' a. Licensed storage capacity for spent fuel: 3657

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

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APR 2.01973

, Q.C.O.S.R.

L QTP 300-532

. Revision 1 I

QUAD-CITIES REFUELING Harch 1978

[, INFORMATION REQUEST s- *

} 1. Unit: Q2 Reload: 7 Cycle: 8

2. Scheduled date for next refueling shutdown: 3-18-85 3 Scheduled date for restart following refueling: 5-26-85

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

lI Not as yet determined. *

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

. Information:

January 18,._1985, if licensing action required.

f 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 procedurcs:

All new fuel assemblies will be GE78-type (barrier clad, extended I) exposure design). ,

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

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"- 7 The number of fuel assemblies.

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a. Number of assemblies in core: 724

b. Number of assemblies In spent fuel pool: 414 1

,, 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 licensed storage: _ 0 9 The projectnd date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003

[ WPPROVED

, APR 2 0 El3 Q.C.O.S.R.

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J VIII. CTAS9ARY The following abbreviations which may have been used In the Monthly Report, are defined holow:

ACAD/ CAM - Atmospheric Contalnment Atmospheric DLlution/ Containment Atmospheric Monitoring ANSI - American National Standards Inntitute APRM - Average Power Range MonLtor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-llydraulic Control System EOF - Emergency Operations Facility CS EP - Generating Stations Emergency Plan llEPA - filgh-Ef ficiency Particulate Filter llPCI - liigh Pressure Coolant Injection System IIRSS - lilgh Radiation Sampling System IPC LRT - Integrated Primary Containn.ent Icak Rate Test IRH - Intermediato Rango Monitor IS I - Inservice Inspection LER - Licensco Event Report LlRT - Local Leak Rate Tont LPCI - Inw Prennare Coolant Injection Mode of RllRS LPRM - Incal Power Range Monitor MAPLilCR - Maximum Averago Planar Linear llent Cenoration Rate MCPR - H!nimum Celtical Power Ratio MFLCPR - Maximum Fraction Limiting Critical Power Rat to MPC - Maximum Perutselble Concentration MSLV - Main 8teten Isolatlon Valvo N LOS!! - National Institute for Occuentional Safety and floalth PCI - Primary Containment Inolation PCIDHR - Preconditiontng Interlm Operating Management Recommendations RBCCW - Reactor Building Closed Cooling Water Syntna RBM - Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RilRS - Ros tdual llent Removal Systtu RPS - Reactor Protection Syntom RWH - Rod Worth Minimizer SBCTS - Standby Can Treatment System SBIE - Standby Llepild Control SDC - Shutdown Cooling Modo of RllRS SDV - Scrnm Dischargo Volume SRM - Source Rango Monitor TBCCW - Turbine Bullding Cloned Cooling Water System TIF - Travorn tng Incorn Probo TSC - Technical Support Contor

• ^N - Commonwealth Edison

• , 'O- Quad Citiss Nucizar Powar Station (2;j ') 22710 206 Avenue North Cordova, lilinois 61242 Telephone 309/654-2241 NJK-84-186 June 1, 1984 Director, Of fice of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D, C, 20555 Attention: Document Control Desk Gentlemen:

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 May 1984.

Very truly yours, COMt0NWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION k -

N. J, Kalivianakis l Station' Superintendent

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