Text

Monthly Operating Repts for Sept 1983
	ML20080S150
Person / Time
Site:	Quad Cities
Issue date:	10/03/1983
From:	Kalivianakis N, Misak A; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
	NJK-83-350, NUDOCS 8310180263
	Download: ML20080S150 (26)
	v • d • e

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[E QUAD-CITIES NUCLEAR POWER STATION UNITS . I AND 2 MONTHLY PERFURMANCE REPORT SEPIFABER 1983 C0fMONVEALTH EDISON COMPANY AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30

, 8310180263 831007 PDR ADOCK 05000254 PM R

TABLE OF CONTENTS I, -Introduction II, Summary of Operating Experience A. Unit One B. Unit Two III, Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A, Amendments to Facility License or Technical- Specifications B. Facility or Procedure Changes Requiring NRC Approval C, Tests and Experiments Requiring MRC 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 Stean Relief Vai re Operations B, Control Rod Drive Scram Timing Data VII, RefuelinF Information VIII, Glossary k

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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 Coma wealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Ste9m Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was r

Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Cor.*,tructors. 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 PPR-29 and DPR-30, issued October 1,1971, and March 21,1972 respectively, pursuant to Docket Numbers 50-254 and 50-265. The date of initial reactor critica11 ties for Units 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 fcr Unit 2.

This report was complied by Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.

II,

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE September 1-7: Unit One began the month operating at 600 MWe due to

.lme Service Wr'er pressure as a result of high cooling canal tempera-ture. This load was maintained until 0930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months on September 4 when a normal load increase was initiated. The load increase was terminated at 0645 hours0.00747 days 0.179 hours 0.00107 weeks 2.454225e-4 months on September 5 with the load at 775 MWe.

September 8-14: Unit One dropped load to minimum Recirculation pump speed at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on September 8 in preparation for beginning one Recirculation pump operation. At 0050 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months on September 9, the 1A Recirculation Pump Motor-Generator Set was tripped, and at 0250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months the unit increased load with one Recirculation pump. The load increase was terminated at 0405 hours0.00469 days 0.113 hours 6.696429e-4 weeks 1.541025e-4 months at 442 MWe. At 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months the Station began open cycle cooling operation, and at 2210 hours0.0256 days 0.614 hours 0.00365 weeks 8.40905e-4 months the unit began dropping load to 390 MWe in order to achiese 50 percent thermal power. At 2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months the Station terminated open cycle cooling ope ra t ion. At 2115 hours0.0245 days 0.588 hours 0.0035 weeks 8.047575e-4 months on September 14, the unit began dropping load in preparation for a schedule ( Maintenance Outage.

September 15-22: At 0010 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months , on September 15, the Turbine was tripped, and at 0029 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months , the Reactor was manually scrammed as the unit was shutdown for maintenance. The unit was shutdown until 0555 hours0.00642 days 0.154 hours 9.176587e-4 weeks 2.111775e-4 months on . September 21 when the Reactor became critical. At 1355 hours0.0157 days 0.376 hours 0.00224 weeks 5.155775e-4 months the Reactor scrammed due to Hi-HI 1RM indication caused by the '

injection of cold Feedwater into the vessel for maintaining water level. The Reactor was critical again at '751 hours0.00869 days 0.209 hours 0.00124 weeks 2.857555e-4 months , and the Generator was placed on line at 0814 hours0.00942 days 0.226 hours 0.00135 weeks 3.09727e-4 months on September 22. At 0815' hours, a nornel load increase was initiated. ,

September 23-30: Unit One continued a normal load increase until 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months on September 26 when the unit achieved full power with a ;

load of 809 MWe. The unit maintained full power for the remainder of the month.

B.- UNIT TWO_

Unit Two began the month derated.to approximately~350 MWe due to End of Cycle Fuel-Depletion. The unit operate'd at this level until 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months on September 4 when the unit dropped lea'd ,in preparation for a scheduled Pefueling and Maintenance Out ge. The Generator was taken off line at 1202 hours0.0139 days 0.334 hours 0.00199 weeks 4.57361e-4 months and the Reactor was shutdown at 1505 hours0.0174 days 0.418 hours 0.00249 weeks 5.726525e-4 months .

Unit Two remained shutdown for the remainder of the month.

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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.

B. Facility or Procedure Changes Requiring NRC Approval There ware 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 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 Mal functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT OilE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q25864 IB Of f-Gas Suction The valve sticks in The valve serves as The ' val ve was ' dis-Valve 1-5401-B the "open" position. isolation of Condenser assembled & the valve vacuum pump. The pump guides were repai red, is normally isolated F.' , with a manual valve.

Q25865 t IA Off-Gas Suction The valve sticks in The valve serves as The valve was dis-Valve 1-5401-A the "open" position, auto-isolation for assembled & the guides Condenser vacuum pump. were repaired.

. This pump is normally isolated with a manual valve. -

Q26655 83-24/03L Vacuum Breaker The position in- The valve indication The switch was 1-1601-33F, dication switch showed dual indication replaced.

Division 2, malfunctioned, when tne Operator Indication was attempted to close it.

Replaced. The Drywell/ Torus '

Separation Test was run successfully; thus, the valve was actually closed.

027700 LPRM 24-33A Failed operational The LPRM was spiking- The operational amplifier. nigh, and in bypass. amplifier was replaced The other LPRMs were on the LPRh circuit.

working.

Q28026 Main Steamline

Hi Flow Sw'*ch OPIS-1-261-2R had the Barton Switch Replaced.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ~ ACTION TAKEN TO l NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION 1

Q28302 83-34/03L lA Recirculation Cabling to the~ The v.= # ve was denlared The cable was replaced j Pump Discharge valve in the Dry- inoperable. The lA during the dual unit l Valve 1-202-5A well was shorted- Recirculation pump was outage.

out. shutdown, and the unit was operated with one Recirculation pump.

All required survell-lances & limit adjustments were performed.

Q28326 1-2301-48 Valve, The motor came This valve ic not The motor was replaced.

l HPCI Cooling loose from the requi red for HPCI to Water valve, be operable.

Q28204 HPCI Controller A resistor (R-5) HPCI was not declared The resistor was

, 1-2340-1 on board 2-A inoperable, it was replaced like-for-l ike.

ampl i fier failed, still capable of meeting all require-ments.

Two motor bolts The valve would not 028232 1-1001-23B The motor bol ts were Back-up were broken & the open from the Control replaced and the Con ta i nmen t torque switch was Room. it was moved off . torque swi tch was Spray Valve out of adj ustment. the seat by hand and adjusted during the then opened f rom the dual unit outage (9-14 Control Room & st roked through 9-20). Also, three times and worked the valve was p rope rl y. successfully stroked three times & timed.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER -

0F ON ACTION TAKEN TO NUMBER NUMBER -COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q28?33 1-1001-7D Limit swi tches were The valve went full- The limit switches Suppression out of adjustment. closed twice and only were adjusted and the to ID RHR part closed four times pump start interlocks Pump Suction out of six. Bacause were adjusted. The Valve the safe position for valve was then stroked this valve is OPEN, and and timed.

no problem was encountered opening the valve, the valve was inope rabl e.

Q28485 83-35/03L I-203-3A The seal on the The unit was scrammed. The valve was replaced.

Target Rock pilot valve was This event occurred

. Safety Relief worn, preventing during a planned stat-Valvc immediate seating. down.

Q2G5G4 M0-1-220-1 The disk and seat This valve's leak rate A high spot on the Main Steamline were worn. put the total, as guide was filed down.

Drain Valve found leakage, over the See Work Requests

! Local Leak Rate limit. Q23594 and Q28637 Q28594 Main Steamline. The seat and disk The volune bounded by The seat and disk were Dra in Val ve we re wo rn . 1-220-2 & 1-220-1 machined and the valves 1-220-2 leaked enough to put were lehk rate tested.

the total local leakage over-the Tech Spac limit.

Q28637 Main Steamline The seat and disk The volume bounded by The seat 0,d disk were Drain Val ve were worn. 1-220-2 c l-220-1 machined aad the valves 1-220-1 leaked enough to put were leak rated tested.

the Icekage over the See Work' Requests Tech Spec limit. Q20594 & Q28584.

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! UNIT ONE HAlNTENANCE

SUMMARY

( , CAUSE RESULTS & EFFECTS I

W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q23658 83-36/03L ID Main Steamline Deterioration of - The Secondary The boot was replaced I Penetration to penetration boot Containment Integrity- and scaled.

'D' Heater Bay material. Test was successfully (MK-Il0) pe r fr meo be fore discovery of the crack, so the safety consequences were

minimal.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION Q27841 Core Spray Suction Auxiliary contacts The valve would not' New auxiliary contacts Valve 110 2-1402-3B were bad, open after being were installed.

closed. It was opened by hand and, left there.:U6ft was in refueling outage.

Q23320 Unit 2 24 VDC One of the The charger voltage The failed battery was 2AI Battery battery cells dropped. Consequently, replaced.

Charger failed by shorting, a half-scram was thus causing received when IRits 11, charger voltage to 12, 13 & 14 and SRMs d rop . went i nope rab l e.

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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 occtrring 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 83-32/03c 9-1-83 Secondary Containnent Test Failure 83-34/03L 9-8-83 1 A LPCI Loop inoperable 83-35/03L 9-15-83 Target Rock, 1-203-3A, Stuck Open 83-36/03L 9-20-83 Secondary Containment Brol an 83-37/03L 9-23-83 Unit One Not inerted Within 24 Hours UNIT TWO 83-13/03L 9-1-83 CRD 10-39 overtravel 83-14/03L 9-6-83 2A MSIV Failed Local Leak Rate Test 83-15/03L 9-12-83 Containnent Leakage Exceeded 0.6 LA 83-16/03L 9-12-83 HPCI High Temperature 2370D & 2371D

V, MTA TABUIATIONS The following data tabulations are presented in this report:

A, Operating Data Report B, Average Daily Unit Power Level C,. Unit Shutdos s and Power Reductions 1

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. OPERATING DATA REPORT DOCKET NO. 50-254 __,

UNIT ONE DATE0ctober 7 COMPLETED BYAlex L. Misok l

TELEPHONE 309-654-2241xi94 1 l

OPERATING STATUS 0000 090183

1. Reporting period:2400 093083 Gross hours in reporting period: 720

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 j

4. Reasons for restriction (if any):

This Month Yr.to Date Cumulative

5. Number of hours reactor was critical 566.6 6170.2 81361.4

6. Reactor reserve shutdown hours 0.0 0.0 3421.jt

7. Hours generator on line 543.9 6075.4 78162.1

8. Unit reserve shutdcwn hours. 0.0 0.0. 909.2

9. Gross thernal energy generated (MWH) 1063390 13693423 159906414

10. Gross electrical energy generoted(MWH) 340808 4432301 51554182 ii. Net electrical energy generated (MWH) 315945 4165133 4799404,1_

12. Reactor service factor 78.7 94.5 81.5

13. Reactor availability factor 78.7 94.5 84.9

14. Unit service factor 75.5 92.7 78.3

15. Unit availability factor _

75.5 92.7 79.2

16. Uni- capacity factor (Using MDC) 56.9 82.6 62.5

17. Unit capacity factor (Using Des.MWe) 55.4 80.5 60,9 l

18. Unit forced outage rate 3.3 2.3 6.4 l

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

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20. If shutdown at end of report period, estimated date of stortop __NA _ _ _ _ _ _ _ _ ,

The MDC naf be lower than 769 MWe dsring perleds of high anbient tenperature due to the thernal perfernance of the sprop ccnol.

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$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

r-OPERATIMG DATA REPORT DOCKET NO. 50-265 UNIT TWO DATE0ctober 7 1

COMPLETED BYAlex L. Misok :

TELEPHONE 309-654-2241x194 OPERATING STATUS 0000 090183

1. Reporting period:2400 093083 Gross hours in reporting period: 720

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 testriction (if any):

This hinth Yr to Date Cunulative

5. Number of hours reactor was critical 87.1 5654.1 77917.5

6. Reactor reserve shutdown hours 0.0 0.0 2985.E

7. Hours generator on line 84.0 5621.7- 75209.8

8. Un1+ reserve shutdown hours. 0.0 '0.0 702.9

9. Gross thernal energy generated (MWH) 98588 10790594 155382088

10. Gross electrical energy generated (MWH) 28418 3398245 49435780

11. Net electrical energy generated (MWH) 19888 3157729 4634: 2o6

12. Reactor service factor 12.1 86,3 78.8

-13. Reactor avo11ob111ty factor ___

12.1 86.3 81.8

! 11.7 85.8 76.0

14. Unit service factor l 15. Unit ovellabillty factor 11.7 85.8 76.7

16. Unit capacity factor (Using MDC) 3.9 62.8 60.9

17. Unit capacity factor (Using Des.MWe) 3.8 61.2 59.4

18. Unit forced outage rate 0.0 1.8 8.6

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

20. If shutdown at end of report period, estimated date o f s t ar t up ___I-8-84 _ ________

The liDC nny be lower than 769 l%ie during periods of high enbient tenperatsre due to the thernal perfernance of the spray canal.

$UN0FFICI AL CtAPANY IUU!ERS ARE USED IN THIS REPORT

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APPE!OIX B

. . AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATEOctober 7 COMPLETED BYAlex L. Misok -

TELEPHONE 309-654-2241xi94 MONTH Seo_tember 1983 DAY AVERAGE DAILY POWER t.EVEL DAY AVER AGE DAILY. POWER LEVEL (MWe-Net) (MWe-Net)

1. 549.3 17. -8.9

2. 562.2 18. -8.2

'3. 546.5 19. -9.4 4, 618.1 20. -11.2

5. 726s 4 21, -11.5

6. 724.4 22, 255.0 4

-7. 741.2 23. 552.6 8.- 730,7 24. 586.3

9. 414.3 25. -666.4

10. 354.8 26. 755.2 ,

i l ii. 345.8 27. 761.9 i 12. 339.5 28. 745.5 13, 367.6 29. 754.4

14. 317.5 30. .

773.5

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16. -10.6 INSTRUCTIONS On this forn list the everage dolly snit power level in Mlle-Net for each der in the. reporting nGath Conpete t e the resserole negem,ett.

7 These fleeres will be osed to plot a graph f or each reporting nenth. Note that when notinen dependable copecity is

- used for the net electrical rating of the unit

~ ill! line (or the restricted power levelIn line/.there sich cases,theney be occasions everage dully snit powerwhen cetpetthe daily sheet everage should 6e- power le festnoted to esplein the opperent monal; i~

APPENDIX B ,

. AVERAGE DAILY UNIT POWER' LEVEL DOCKET NO. 50-265 UNIT TWO DATE0ctober 7 COMPLETED BYAlex L. Misak TELEPHONE 309-654-2241x194 MONTH September 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 319.9 17. -7.6 2, 313.8 18. -7.5 3 ', 314.5 19. -7.5 4 122.3 20. -7.9

5. -15.6 21. -7.6

6. -6.4 22. -6.7

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-9.3 23. -4.6

8. -8.0 24. -3.3

9. -7.0 25. -2.4

10. -8.3 26. _ -2,2 ii. -8.3 27. -2.6

12. -8.4 28. -i 9

13. -8.3 29. -2.3

14. -0.0 30. -2.8

15. -9.2

16. -7.6 INSTRUCTIONS On this forn, list the average daily snit power level in IWe-Net for each dop in the reporting nanth. Compete to the tre7 delt megeustt.

These flgeres will be used to plot a graph for each raporting month. Note that when notinen dependable copecite is used for the net electrical rating of the enit there nay be occasions when the deilt everage puer level exceeds the illI line (or the restricted power level line),.In sich cases,the average daily snit power e etpet sheet shev'.id be feetnoted to explain the apparent enenelp

m n m n M M M M t""E M M M M M M n n bp 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 One COMPLF.TED BY Alex Misak DATE October 3, 1983 REPORT HONTil SEPTEMBER 1983 TELEPliONE __ 309-654-2241 N $ p w" s $$$ gw B! w

$ $ d LICENSEE m@ @

u w DURATION d g EVENT Uu o u

NO. DATE (Il0URS) c REPORT NO. CORRECTIVE ACTIONS /COHHENTS o

83-59 830908 S 0.0 B 5 CB VALVEX Reduced load to test 1-202-5A valve 83-60 830908 F 0.0 0 5 CB VALVEX Reduced load to SOS thermal power for one Recirculation loop operation 83-61 830915 S 157.8 B 1 CB VALVEX Unit shutdown f' maintenance on the 1-202-5A valve 13-62 830921 F 18.3 G 3 IA INSTRU ' Unit scrammed during startup due to Hi-lli IRM indication caused by the injection of cold feedwater into the vessel for maintaining water level 83-63 830924 S 0.0 H 5 RC FUELXX Reduced load to change control rod pattern a

APPROVED 1

AUG 1 G 1982

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M M f*"1 m m y ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit Two COMPLE'It.D BY Alex itisak DATE October 3, 1983 REPORT HONTII SEPTEtiBER 1983 TELEPIIONE 309-654-2241 N $

w" 5 $$U gw hw h$w $ h LICENSEE m@ @

o DURATION @ g EVENT $u 0 u

NO. DATE (IIOURS) o REPORY NO. CORRECTIVE ACTIONS / COMMENTS o

83-65 830904 S 0.0 H 5 RC FUELX:( Load reduced in preparation for End of Cycle Six Refueling Outage 83-66 830904 S 636.0 C 1 RC FUELX;; Unit shutdown for End of Cycle Six fefueling Outage 1

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AUG 1 G 1982 .

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T VI. UNIQUE REPORTING REQUIREMENTS The'following items are included in' this report based on prior commitments i to the commission:

-A. . Mall 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 2 9-04-83 2-203-3A 1 Manual Rx Press Surveillance T.S.

2-203-38 -1 Manuai 972 4.5.D.I.b 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual 1 9-15-83 1-203-3A i Manual Rx Press Surveillance T.S.

920 4.5.D.1.b (stuck open to 360 psig)

'I 9-22-83 1-203-3A 1 Manual Rx Press Surveillance T.S.

910 4.5.D.I.b (Post-

' Maintenance; Replaccd Valve) 1 9-22-83 1-203-3B 1 Manual- Rx Press. Surveillance T.S.

1-203-3C 1 Manual 910 4.5.D.I.b (Post-1-203-3D 1 Manual Maintenance;.

1-203-3E 1 Manual Replaced Pilot Valve)

m B. CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO The basis for reporting ti11s data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifica-tions 4.3.C.i and 4.3.C.2.

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

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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 CONTROL ROD DRIVES, FROM 9-1 TO 9-30-83 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

Insertion DESCRIPTION NUMBER S 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 Tine)

'9-14 88 0.28 0.65 1.40 2.50 2.96 Unit One Hot Scram Time "A" (G-10) Sequence i.

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VII, REFUELING INFORMATION The following information about future reloads at Quad-Cities 4

Station was requested in a Jant'ary 26, 1978, licensing memorandte (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 R: vision 1

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QUAD-CITIES REFUELING March 1978

( , INFORMATION REQUEST

_: 1. Unit: Q1 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: 9-6-82 3 Scheduled date'for restart following refueling: 12-18-82

4. Will refueling or resumption of operation thereafter require a technical specification change ^< other license amendment: Yes 5

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5. G.-heduled date(s) for submitting proposed IIcensing action and supporting

] . Information: 8-19-82: Tech. Spec. changes submitted to the NRC.

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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:

a) All 7x7 fuel assemblies vill be removed from the core.

b) MAPLHGR curves for fuel types in the core are being extended to h0,000 MWD /ST. ,

c) MCPR limits vill be detemined by GE's ODYU computer code.

o d) "he vessel pressure safety limit is being modified to accommodate the i~ potential for higher reactor pressures as ' alculated c by ODYN.

1 li 7 The number of fuel assemblies.

a. Number of assemblies la core: 724 l b. Number of assemblies in spent fuel pool: 800

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: 36 9

b. Planned increase in IIcensed storage: 0 k

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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XPPROVED APR 2.01978 Q.c.o.S.R.

QTP 300-S32 3 '

i Ravision 1 I

QUAD-CITIES REFUELING March 1978 g .. ,

INFORMATION REQUEST o- ,

n 1. Unit: Q2 Reload: 6 Cycle: 7 b 2. Scheduled date for new.t refueling shutdown: 9-5-83 3 Scheduled date for restart following refueling: 11-12-83 3

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

P No, however, a change to the Technical Specifications- is being saSmitted 3

(see below).

5 Scheduled date(s) for subm!tting proposed licensing action and supporting

. Information:

June 14, 1983 (Scheduled)

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:

a) All new fuel assemblies will be of barrier design; MAPLHGR curves will be

( re-labeled to include the barrier designation.

b) The use of ifnproved assumptions in the load reject without bypass analysis resulted in a much improved MCPR operating limit. Technical Specifications are being changed to provide this additional operating margin.

(

7 The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 204

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 0

-b. Planned increase in licensed storage:

9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity 2003

3 WPPROVED APR 2 01978 Q. C. c. S. R.

p h .. ,

VIII, GLOSSARY The following abbreviations shich may have been used in the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric Containnent Atmospheric Dilution /Containnent Atmospheric Monitoring ANSI -

American National Standards Institute

,- APRM - Average Power Rang' Monitor ATWC- - Anticipated Transient Without Scram e bWR -

Boiling Water Reactor CPD -

Control Rod Drive EHC -

Electro-Hydraulic Control System EOF .- . Emergency Operations Facility CSEP - Generating Stations Emergency Plan HEPA - High-Efficiency Particulate Filter HPCI -

High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT -

Integrated Primary Containment Leak Rate Test IRM - Latermediate Range Monitor ISI - Inservice Inspection LER - Licensee Event Report LLRT -

Local Leait bte Test LPCI - Low Pressure Coolant Injection Mode of RHRS LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR -

Minimum Critical Power Ratio MFLCPR - Maximum Fraction LLmiting Critical Power Ratio MPC -

Maximum Permissible Concentration MSIV -

Main Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI - Primary Containnent Isolation PCIOMR - Precondition 1ng Interim Operating Management Recommendativns RBCCF - Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RURS- - Residual Heat Removal System RPS - Reactor Protection System RWM -

Rod Worth Minimizer SBGTS - Standby Gas Treatment Systen SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM.

- Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center

Commonweilth Edison C. Quad Citi1s Nuclitr Power St tion

&'* 22710 206 Avenue North Coroova, Illinois 61242 Telephone 309/654-2241 NJK-83-350 October 3, 1983 Director, Of fice of Inspection & Enforcanent United States Nuclear Regulatory Commission Washington, D, C, 20555 Attention: Document Control Desk Gentlemen:

Enclosed for yo'tr information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during tne month of September 1983.

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION e# Y N J Kallvianakis

[

Station Superintendent bb f

l Encloeu re l

. - . _ _ _ _ _ _ _ _ _ . _ . . . . _ _ _ _ . . _ . . _.. _ . _ _ _ _ _ _ ,. _ . _ .. _ _ . _ . __.

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