ML20073F539

Monthly Operating Repts for Mar 1983

ML20073F539
Person / Time
Site:	Quad Cities
Issue date:	04/04/1983
From:	Misak A COMMONWEALTH EDISON CO.
To:
Shared Package
ML20073F526	List: ML20073F520 ML20073F539
References
NUDOCS 8304150504
Download: ML20073F539 (22)

Text

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E i.

i QUAD-CITIES NUCLEAR POWER STATION i

UNITS 1 AND 2 MONTHLY PERNRMANCE REPORT a

MARCH 1983 COMMONWEALTH EDISON COMPANY AND IORA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 t

1 ew F304150504 830404 i

PDR ADOCK 05000254 R

PDR

TABLE OF CONTENTS I.

Introduction II.

Summary of Operatina 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 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

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INTRODUCTION l

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 lowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.

The Architect / Engineer was Sargent & Lundy, incorporated, and the primary construction contractor was United Engineers & Constructors. The condenser cooling nethod is a closed cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively, pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor criticalities for Units 1 and 2, respectively, were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973, for Unit I and March 10, 1973 fo r Un i t 2.

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

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II.

SUMMARY

OF OPERATING EXPERIENCE A.

UNIT ONE March 1-6: Unit One began the month deratri to 785 MWe due to fouling of the Main Condenser. At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, on March 6, load was decreased at 200 MWe/ hour to 620 MWe to perform weekly Turbine tests and reverse Main Condenser flow.

Load was increased normally until 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br /> when low Condenser vacuum caused the load increase to be terminated at 770 MWe.

March 7-10: The unit continued to be derated due to high Main Condenser backpressure until 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> on March 10, when the unit was shutdown for a weekend Maintenance Outage.

March 11-18: From March 11-14, the unit was in Cold Shutdown for a weekend preventative Maintenance Outage to clean the Main Condenser Tubes.

Unit startup commenced at 0410 hours0.00475 days <br />0.114 hours <br />6.779101e-4 weeks <br />1.56005e-4 months <br /> on March 15, but the unit did not come on line until 0905 hours0.0105 days <br />0.251 hours <br />0.0015 weeks <br />3.443525e-4 months <br /> on March 18 due to gasket leaks on two valves and high Turbine vibration.

March 19-24: Load was increased normally until a load of 812 MWe was achieved at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on March 21.

This load was maintained until 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on March 22, when load was decreased to 300 MWe to perform maintenance on a thermocouple on the 1A MSIV. At 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br />, load was increased normally until 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br /> on March 24, when a load of 831 MWe was achieved.

March 25-31: The unit load was maintained at an average of 825 MWe throughout the remainder of the month, except for a two hour period on March 27, when load was decreased to 700 MWe to perform weekly Turbine tests and reverse Main Condenser flow.

B.

UNIT TWO March 1-6: Unit Two began the month operating at 790 MWe.

On three occasions during this period, load was reduced due to Condensate Demineralizer problems.

In addition, at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, on March 4, load was reduced to 700 MWe to perform weekly Turbine tests.

March 7-10: The unit load was increasing normally on March 7, following Condensate Demineralizer maintenance, until 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> when the increase was terminated at 817 MWe.

Also, during this period, the barrier fuel test was performed, and Unit Two began experiencing end of cycle fuel depletion deratings.

1 March 11-24: Unit load was maintained at an average of 780 MWe throughout this period.

Load was reduced three times to 700 MWe, twice for weekly Turbine tests and once to reverse Condenser flow.

At 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, on March 24, the 2A Recirculation Pump Motor-Generator Set ramped down to minimum speed. The 2B MG Set was reduced to 44 percent speed, dropping the unit load to 350 MWe. The 2A MG Set was repai red, and the unit load was increased to 650 MWe. This load was maintained for about three hours until normal shutdown procedures were initiated in preparation for a weekend preventative Maintenance Outage.

March 25-31: At 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on March 25, Unit Two was taken off line and placed in Cold Shutdown. for a weekend preventative Maintenance Outage to repair a minor Feedwater piping leak and to perform preventative maintenance cleaning of the Main Condenser Tubes. This outage continued until 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> on March 30, when the unit was placed on line with the load increasing normally.

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III, PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED tiAINTENANCE A.

Amendments to Facility Licens or Technical Specifications On February 17, 1983, Amendment 78 was issued to License DPR-30. This Amendment allows adjustment of APRM gain instead of changing scram and rod block lines when operating with MFLPP/FRP greater than 1.0.

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 safety related maintenance performed on Unit One and Unit Two during the reporting period. This summary includes the I

following headings: Work Request Numbers, LER Numbers, l

Components, Cause of Malfunctions, Results and Effects j

on Safe Operation, and Action Taken to Prevent l

Repetition.

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UNIT 0!!E MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVENT REPETITION 021535

' B' Outboa rd Feed-flormal wear of the The valve failed Local Replaced 0-ring.

water Check Valve 0-ring.

Leak Rate Test.

CV-1-220-62B Q24751 Main Steam Drain Valve does not seal The inline 1-220-2 An oversize disc was 1-220-1 well enough to pass valve was closed installed in the valve LLRT. This is a during normal and the seat was resul t of wear and operation of the unit, lapped to accommodate repeated lapping of and isolates on a the disc. The valve the valve seat.

Group 11 Isolation then passed the Local signal.

Leak Rate Test.

Q24247 IB Recirc Pump Pressure between The seal deteriora-A rebuilt seal was Seal number I and number tion caused an in-installed.

2 seal was low due crease in Drywell to seal deteriora-Equipment Drain tion.p leakage.

Q21987 Condenser Off The solenoid valve The 1-5402A was The solenoid valve i

Gas Valve A0-failed to operate operable, but the was repaired, I

l-5402A properly due to faulty solenoid successfully bench normal wear of the valve prevented tested, and re-in-valve internals.

smooth operation of stalled. The I-5402A the valve.

valve was then j

successfully tested.

Q21986 Condenser.0ff Solenoid valve is The 1-5402B valve The solenoid valve Gas Valve A0-bad.

was operable, but was rebuilt, bench 1-5402B the faulty solenoid

. tested,,and re-in-valve prevented stalled.

smooth valve operation.

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l UNIT Of1E MAINTENANCE

SUMMARY

f CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCT10N SAFE OPERATION PREVENT REPETIT10N i

I Q23610 TIP flachine #4 The ball valve The ball valve was A new ball valve was Ball Valve internals were operable but did not installed and leak System 703 worn.

operate smoothly, tested.

Q23479 ACAD Air Supply Feed fuse failed.

Valve would not The feed fuse in Control Isolation Valve open; Containment Room panel 901-56 was

~

FCV-1-2599-113 integrity was intact.

replaced.

t Q24972 Inboard Feedwater The valve bonnet The worn pressure seal The pressure seal ring Check Valve 1-pressure seal ring ring resulted in a was replaced, and the 220-50A failed due to small leak at pressure.

valve was visually i

normal wear.

All leakage was con-checked for leaks at tained within the Dry-pressure. The seal well Floor Drain system.

ring still leaked (See

]

Work Request Q25010).

Q25020 DrYwell Floor The valve had dual The 1-2001-3 valve had Disassembled valve, Drain Sump indication when been in the isolated cleaned internals, i

isolation Valve being given open position previous to and replaced air 1-2001-3 signal. This this event and the in-operator. The valve was implied that the line 1-2001-4 valve was then stroked, timed &

1-2001-3 valve ope rabl e,

successfully Local was not going full Leak Rate tested.

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open.

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Q25068 Drywell Floor Valve would not The inline A0 1-2001-4 The valve stem was Drain Sump Pump indicate closed.

valve was operable &

turned & the limits

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Discharge I-would have provided were re-adj usted. The 2001-3 proper Containment valve was then isolation.

successfully. stroked and timed.

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l UNIT TU0 MAINTENANCE

SUMMARY

t CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO j

NUMBER NUMBER COMPONENT MALFUNCT10N SAFE OPERATION PREVENT REPETIT10N Q24780 Torus to Drywell Pressure switch Redundant vacuum Installed new switch Vacuum Breaker was out of breaker was fully and calibrated.

j A0-2-1601-20B cal i b ra t ion.

ope rabl e.

Q23012 Drywell Electrical The penetration The penetration would The' flange was l

Penetration 100G flange was loose, not hold 112 Pressure; tightened and the Containment integrity penetration was j

was intact.

successfully Local Leak Rate tested.

Q25221 2-1601-55 Valve Failure of seals The solenoid valve was A new solenoid valve in the solenoid blowing air out the was installed.

valve.

exhaust port, but was operable.

Q25262 "A" Reactor The undervoltage The breaker tripped A new undervoltage Protection trip release coil and would not close trip release coil was 4

l System MG Set failed.

in.

Installed in the Output Breaker output breaker.

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e IV, LICENSEE EVENT REPORTS l

The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.

UNIT ONE 4

Licensee Event Report Number Date Title of Occurrence 83-10/03L 2-24-83 Reactor Building Ventilation System Trip 83-il/03L 2-25-83 condenser Vacuum Scram Switch Out of Limits 83-12/0lT 3-10-83 Unit One Shutdown Out

(

of Sequence 83-13/03L 3-19-83 MSIV Pilot Temperature Detector Failed 83-14/03L 3-24-83 Unit one 250 volt Battery Inope rable i

s UNIT TWO 83-5/03L 3-16-83 Low-Low Level Switch, 2-263-72c, did not respond i

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V.

DATA TABULATIONS 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

OPERATING DATA REPORT DOCKET NO.

50-254

UNIT, ONE i

D ATE Ap r il 05 1983

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COMPLETED BYAlex Misok

(

TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 030183 ~

1.

Reporting period:2400 033183' Gross hours in reporti,ng period:

744 2.

Currently authorized power-level (MWt): 2511 Max Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789 I

tobhichrestricted(ifany)(MWe-Net):

3.

Power level NA 4.

Reasons for restriction (if any):

This Month Yr.to Date Cumulative 5.

Number of hours reactor was critical 591.3 2002.4_

77173.6 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on line 567.2 1973.9 74060.5 8.

Unit reserve shutdown hours.

0.0 0.0 909.2 Y.

Gross thernal energy generated (MWH) 1318996 4739092 150952083

10. Gross electrical energy generated (MWH) 427232 1552900 48674781 it. Net electrical energy generated (MWH)_

399701 1459803 45288711

12. Reactor service factor 79.5 92.7 80.9

13. Reactor ovallobility factor 79.5 92.7 84.4

14. Unit service factor 76.2 91.4 77.6

15. Unit avoilability factor 76.2 91.4 78.5

16. Urk i t capacity factor (Using MDC) 69.9 87.9 61,7

17. Unit capacity factor (Using Des.MWe) 68.1 85.7 60,1

10. Unit forced outage rote 8.9 3.2 6.6

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

20. If shutdown ot_end of report period,estincted date of_stortup

___NA________

IThe NDC nay be lower than 769 MWe during periods of high onbient tenperature due to the thernal performarce of the spray canal.

$ UNOFFICIAL COMPANY NUMPERS ARE USED IN THIS REPORT

OPERATING DATA REPORT DOCKET NO, 50-265 UNIT Tuo DATEApril 05 1983 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 OPERATING STATUS 0000 030183 1.

Reporting period:2400 033183 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' Cumulative 5.

Number of hours reactor was critical 629.9 1896.0 74159.4 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 612,7 1866,7 71454,8 B.

Unit reserve shutdown hours.

0,0 0. 0' 702.9 9.

Gross thermal energy generated (MWH) 1412692 4228411 148819905

10. Gross electrical energy generated (MWH) 461090 1348792 473'86327

11. Net electrical energy generated (MWH) 430918 1264540_

44448107 L2, Reactor service factor 84,7 87.8 78.4

13. Reactor availability factor 84.7 87.8 81.6

14. Unit service factor 82.4 86.4 75.6 L5. Unit avo11obility factor 82.4 86.4 76.3

16. Unit capacity factor (Using MDC) 75.3 76,1 61.1 L7. Unit copocity factor (Using Des.MWe) 73.4 74.2 59.6

18. Unit forced outage rate 2.8 5. 4_

9.0

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

20. If shutdown at end of report period,estinated date of startup ___g(________

• The MDC nap be lower than 769 MWe during periods of high onblent temperatore due to the thermal perfernance of the spray canal.

$ UNOFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT n

1 APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEApril 05 1983 COMPLETED BYAlex Misak TELEPHONE 309-654-224ix194, MONTH March 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

1.,

742.0 17.

-11,0 2.

746,1 18.

264.1 3.

764.1

_i9.

578,6 4,

733.0 20, 721.0 5.

772.2 21, 766,8 6.

701.5 22.

713.3 7.

676.3 23.

651,1 8.

636.7 24, 765.3 9.

588,8 25.

764.6 LO.

537.2 26.

764,6 ti.

-9.4 27.

749,1 12.

-6.2 28.

769.0 13.

-5.5 29.

775.3 14.

-6.3 30.

759.8 I

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19. _

~13.0 31, 778.2 16.

-12,5 INSTRUCTIONS On this forn nerest whole, list the average daily unit power level in HWe-Net for each day in the reporting nonth. Compete to the

recewett, These fiwes will be used to olet a crcch for acch reporting ninth. Nite that when nasinun dependable capacity is ocJ f ar the ne t.ectricci rating ef~ the Unit,there ncy he occasiens when the daily overage power level exceeds the 1;311tae (or the rotrictec p.er level line).In svtb ccses,the average daily unit ocwer evtput sheet should be footnoted to esplein the cpparent cnanaly

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APPENDIX B AVERAGE DAILY UNIT PO'AER LEVEL I

DOCKET NO.

50-265 l

UNIT TWO DATEApril 05 1983 COMPLETED BYAlex Misok l

TELEPHONE 309-654-224ix194 HONTH March 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

752.9 17, 719.6 2.

740.9 18, 734,'4 3.

753.2 19, 721.2 4.

672.0 20.

729.0 5.

689.1 21.

721.8 6.

713,7 22.

718.3 7.

738.5 23.

718,8 B.

728.9 24, 459.4 9.

731,3 25.

-6.9 10, 767.8 26.

-6.8 ii.

711.3 27.

-7,3 12.

743.3 28.

-9,7 13.

713.2 29.

-13.4

1. 4.

726.0 30, 218,8 15, 735.6 31.

608.0 16.

731,9 INSTRUC110NS On this fern, list the overage daily unit power level in MWe-Net for each day in the reporting nonth.Conpete to the ntorest whole negawatt.

x These figures will be used to plot a graph for each reperting nonth. Note that when nominun dependable capacity is used for the net electrical rating of the sait 1988 line (or the restricted power level line),there may be occasions when the dolly overage power level exceeds the

,In such cases,the overage daily snit power output sheet should be festnoted to explain the opptrent onomaly l

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j ID/SA APPENDIX D QTP 300-Sl3 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

50-254 August 1982 UNIT NAME Quad-Cities Unit One COMPLETED BY Alex Misak, ext 194 N

DATE April 4, 1983 REPORT HONTII MARCH 1983 TELEPil0NE 309-654-2241 g

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DURATION EVENT M

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DATE (IlOURS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS a

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83-16 830306 S

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine l

test 83-17 830308 F

0.0 H

5 HC HTEXCH Reduced load due to High Main Condenser Back Pressure 83-18 330310 S

101.2 B

]

HC HTEXCH Unit shutdown for Main Condenser Tube cleaning i

l 83-19 830315 F

23.3 B

1 CH VALVEX Unit shutdown due to gasket leaks on continuous head vent and 58A Feedwater

{-

Check Valves 33-20 830316 F

34.4 8

1 CH VALVEX Unit shutdown due to gasket leak on 58A Feedwater Check Valve 83-21 830318 F

3.4 B

9 HA TURBIN Generator tripped due to high Turbine vibration t

83-22 830322 F

0.0 B

5 CD INSTRU Reduced load to repai r Thermocouple on I A MSIV 83-23 830327 S

0.0 B

5 HA XXXXXX Reduced load to perform APPROVED weekly Turbine test AUG 1 G 1982

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ID/SA APPENDIX I)

QTP 300-S13 UNIT SilOTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. __50:245 August 1982 UNIT NAf1E _ Quad-Cities Unit Two COMPI.ETED HY Alex Misak, ext 194 UATE

_ April 4, 1983 REPORT fl0NTil MARCH 1983 TEI,EPil0NE 309-654-2241 5

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EVENT

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O NO.

DATE (Il0VRS)

REPORT No.

CORRECTIVE ACTIONS /C0 tit lENTS c2 83-21 830303 F

0.0 B

5 HG DEMillX Reduced load due to plugged 2B Condensate Demi ne ra l i ze r 83-22 830304 S

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine test 83-23 830304 F

0.0 B

5 HG DEMINX Reduced load due to Condensate Demin-eralizer problems 83-24 830306 F

0.0 B

5 HG DEttillX Reduced load due to Condensate Demin-eralizer problems 83-25 830313 5

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine test 83-26 830319 S

0.0 8

5 HA XXXXXX Reduced load to perform weekly Turbine test 83-27 830320 S

0.0 H

5 HC HTEXCH Reduced load to reverse Condenser Flow direction 83-28 830324 F

0.0 A

5 CB MECFUN Reduced load due to 2A Recirculation pump Motor-Generator APPROVED Set problems AUG 1 G 1982

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ID/SA APPENDIX D QTP 300-SI3 UNIT SilVTDOWNS AND POWER REDilCTIONS Revision 6 DOCKET NO. _50-265 August 1982 UNIT hat 1E _ Quad-Ci ties Unil_Two C0t1Pl.ETED BY _ Alex_111.sak._ ext 194 DATE April 4. 1983 REPORT t!ONTil f1ARCli_13Q3 TEI.EPil0NE 309-654-2241 I

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EVENT w

oO NO.

DATE (HOURS)

REPORT NO.

CORRECTIVE ACTIONS /Cott?!ENTS o

83-29 830325 s

113.8 B

1 ZZ ZZZZZZ Unit shutdown for minor Feedwater piping leak and preventative maintenance cleaning of Main Condenser 83-30 830329 F

17.5 B

1 SH VALVEX Unit shutd...in due to gasket leak on Electromatic Relief Valve 2-203-3C APPROVED AUG 1 G 1982

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VI.

UNIQUE REPORTING REOUIREMENTS The following items are included in this report based on prior conmitments 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 UNIT DATE ACTUATED ACTUATIONS COND I T I P'IS, DESCRIPTION OF EVENTS 1

3-11-83 1-203-3A 1 Manual Rx Press Surveillance T.S.

895 4.5.D.I.b i

3-15-83 1-203-3B 1 Hanual 890 Post-Maintenance -

1-203-3C 1 Manual replaced pilot valve 1-203-3D 1 Manual 1-203-3E 1 Manual i

2 3-25-83 2-203-3A 1 Manual 910 Surveillance T.S.

4.5.D.l.b I

2 3-29-83 2-203-3B 1 Manual 918 Post-Maintenance -

2-203-3C 1 Manual replaced pilot valve 2-203-3D 1 Manual 2-203-3E 1 Manual 2

3-30-83 2-203-3C 1 Manual 919 Post-Maintenance -

replaced flange gasket B.

CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There were no control rod drive scram timing data for the reporting period.

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VII.

REFUELING INFORMATION 1

a j

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 Infonnation",

dated January 18, 1978.

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QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 lHFORMATION 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 T*

4.

tilli refueling or resumption of operation thereafter require a technical specification change or other license amendment:

Yes 5.

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

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

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 7x7 fuel assemblies vill be removed from the core.

b) MAPIEGR curves for fuel types in the core are being extended to 40,000 MWD /ST.

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

s d) The vessel pressure safety limit is being modified to accommodate the

~

potential for higher reactor pressures as ' alculated by ODYN.

c 7

The number of fuel assembites.

a.

Number of assemblies la core:

724 l

b.

Number of assemblies in spent fuel pool:

800 n

L 8.

The present licensed spent fuel pool storage capacity and the size of any j

increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

I a.

Licensed storage capacity for spent fuel:

3657 l

b.

Planned increase in licensed storage:

O 9.

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

WPPROVED APR 2.01978 Q.C.O.S.R.

e m-e-mem me w m _.

e i

b.

QTP 300-S32 Revisicn 1 QUAD-CITIES REFUELING M:rch 1978

(

INFORMAT10N; REQUEST ~

1.

Unit:

Q2 Reload:

I Cycle:

7 2.

Scheduled date for next refueling shutdown:

9-11-83

[

3 Scheduled date' for restart following refueling:

11-20-83 4.

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

Depending upon the Licensing analyses, a MCPR limit change mayrbe*needed.

5 Scheduled date(s). for submitting proposed licensing action and supporting I"I '**'I 8-22-83 (if necessary) 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:

NFS intencs to apply 10CFR50 59 to the Q2R6CT reload unless MCPR Technical Specification change is required.

s 7

'The number of fuel assembites.

a.

Number of assemblies in core:

7 211 b.

Number of assemblies in spent fuel pool:

1140 m

d 8.

The present licensed spent fuel pool storage capacity and the size of any l

increase in licensed storage capacity that has been requested or is planned I

in number of fuel assemblies:

i a.

Licensed storage capacity for spent fuel:

3897 1

b.

Planned increase in licensed storage:

0 9

The projected date of the last refueling. that can be discharged to the I'

spent fuel pool assuming the present licensed capacity: 2003 os L.

APPROVED r

3 APR 2.01978 Q.C.O.S.R.

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

i ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment i

Atmospheric Monitoring American National Standards Institute ANSI Average Power Range Monitor APRM ATWS Anticipated Trandient Without Scram l

BWR Boiling Water Reactor l

CRD Control Rod Drive Electro-Hydraulic Control System EHC Emergency Operations Facility EOF 4

GSEP Generating Stations Emergency Plan 4

High-Ef ficiency Particulate Filter HEPA High Pressure Coolant Injection Systen HPCI s

RRSS High Radiation Sampling System Integrated Primary Containment Leak Rate Test IPCLRT IRM Intermediate Range Monitor 1

ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor i

MAPLHGR Maximum Average Planar Linear Heat Generation Rate l

MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve National Institute for Occupational Safety and Health NIOSH Primary Containment Isolation PCI i

PCIOMR Preconditioning Interim Operating Management Recommendations i

RBCCW Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System Reactor Protection System RPS RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System Standby Liquid Control SBLC s

l SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System j

TIP Traveling Incore Proba TSC Technical Support Center i

1 l

_.