ML20128K650

Monthly Operating Repts for June 1985

ML20128K650
Person / Time
Site:	Quad Cities
Issue date:	06/30/1985
From:	Kronich C, Tamlyn T COMMONWEALTH EDISON CO., IOWA-ILLINOIS GAS & ELECTRIC
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
TKT-85-37, NUDOCS 8507240191
Download: ML20128K650 (23)

Text

E,;'-a.,m A

4

.,~

' 1 v.

E r

QUAD-CITIES NUCLEAR POWER STATION, i

UNITS 1 AND 2

[

MONTHLY PERFORMANCE REPORT JULY 1985 COMMONWEALTH EDISON COMPAIN AND IOWA-ILLINOIS CAS & ELECTRIC COMPANY.'

NRC DOCKET NOS. 50-254, AND 50-265 I

LICENSE NOS. DPR-29 AND DPR-30 pe 1,

]W'%'[8p,m,,;

8 \\

em 3

V

/

W.

,-_d_.-'____

--a

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 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 0027H 0061Z

I.

INTRODUCTION Quad-Cities Nuclear Power St'ation 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.

The Nuclear Steam Supply Systems are General Electric Company Bolling Hater Reactors.

The Architect / Engineer was Sargent & Lundy, 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 OPR-29 and DPR-30, issued October 1, 1971, and March 21, 1972, respectively; pursuant to Docket Numbers50-25e 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.

i i

0027H 0061Z

II.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One June 1-16: Unit One began the month of June shutdown from a Reactor scram on May 30.

On June 1, at 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, the Reactor went critical, and was placed on line at 2152 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.18836e-4 months <br />. Full power was reached after a normal load increase on June 4 at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />. On June 5, at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />, load was dropped to 700 IUle for Turbine surveillances. At 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> load began an increase to 800 MWe, and at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br /> the unit was placed on Economic Generation Control (ECC).

June 17-22: On June 17, at 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />, a normal orderly shutdown coamenced at 25 IfWe/ hour, because the 1/2 Diesel Generator was out of service and the Unit One RIIR Service Water Pumps were inoperable con-currently, due to Technical Specification 3.9.E.1.

On June 18, at 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br />, the shutdown was terminated due to the operability of the 1/2 Diesel Generator and the Unit One RHR Service Water Pumps, and a normal load increase to maximum pouer began. Maximum load was reached at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.

June 23-30: On June 23, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, load began a drop to minimum power as per the Load Dispatcher. Minimum power was reached at 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br />. At 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> load began an increase to full power, and the unit was placed on ECC, on June 24 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. On June 30, at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, load was dropped to 600 MWe for Turbine weekly surveillances.

At 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, load was decreased to 550 inie for a Control Rod pattern adj ustment. At 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br />, the unit began a normal load increase to full power.

B.

Unit Two June 1-13: Unit Two began the month shutdown for the End of Cycle Seven Refueling and Ibintenance Outage. On June 5, at 2301 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.755305e-4 months <br />, the Reactor went critical and remained in HOT STANDET until June 7, at 0214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br />, when the unit was placed on line. At 0538 hours0.00623 days <br />0.149 hours <br />8.895503e-4 weeks <br />2.04709e-4 months <br /> the unit was taken off line for a Turbine Overspeed Test, and was placed back on line at 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br />. Maximum power was reached on June 13 at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> after a normal load increase.

June 14-22: On June 14, at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, load began a drop to. HOT STANDBY to repair an EHC oil leak. The unit went off line on June 15, at 0313 hours0.00362 days <br />0.0869 hours <br />5.175265e-4 weeks <br />1.190965e-4 months <br />, and was returned on June 16, at 0052 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />. At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, load began a normal increase to full power. On June 18 full power was reached at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. On June 21, at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, load was decreased to 750 MWe, and the unit-was placed on ECC at 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br />.

0027H 0061Z

m.

i II.

SUMMARY

OF OPERATING EXPERIENCE I

(continued)

.B.

Unit Two (continued).

June 23-30: On June 23, ;at 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />,. load began a drop to mintmum

' power as per Load, Dispatcher.~ : Minimum speed was reached at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br />.

At 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />,. load began a normal increase to full power.- On June 24,' at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br />, the unit was holding load at 810 IWe.

On June 26, at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br /> load began a decrease to 650.MWe as per Load Dispatcher.. At 0425 hour0.00492 days <br />0.118 hours <br />7.027116e-4 weeks <br />1.617125e-4 months <br />s-load was holding at 650 MWe, At-0505 hours load was increased to maximum power. At 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> load reached 812 1Rie and held steady.

On June-28,lat 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, load was decreased to 700 MWe-to repair a leak in the vent of the 2B2 Feedwater Heater. At 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> load

~

. began an increase-to full-power. On June 29, at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, the unit reached 815 MRe and held load for the duration of June.

i 4

l j

+

c t

6 9

1 j

i I

+

~

.l l

l

III. PLANT OR PROCEDURE CllANGES, 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.

B.

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

In accordance with Technical Specification Section 6.7.B. a notification of changes to the Offsite Dose Calculation Manual (ODCII), Revision 11, was made. This notification was in the form of a letter dated April 26,.1985, to D. Eisenhut from Krista Licari, and was acknowledged by Avis M. Paulson on May 30,1985.

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 Units One and Two during the reporting period. This summary includes the following: Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

l l.

j UNIT 1

' MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAXEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION I

Q42744 Unit 1 Diesel Fatigue and life of 1/2 Diesel Cencrator Replaced fuel flex

Generator Flex line (line was was operable. All line and fittings.

l Fuel Line From original part, 12 necessary surveillances Day Tank years old).

were initiated.

t i-t

(

l

[

4

+,-.

UNIT

'2 MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q37513 Solenoid Valve on 1/2 Diesel Cen-1/2 Diesel Generator Solenoid valve replaced Unit 2 Diesel crator solenoid did not start. Alarm as preventative Generator Air valve " bound up".

reset; the 1/2 Diesel maintenance on all three Start Systen Uould not open on Generator did start.

Diesel Generators, start signal.

Q42127 85-006 A0 2-203-2B Out-Valve seating Leak rate exceeded Tech Lapped main seat, board 11SIV.

surface uear due to Spec 4. 7. A.2.E., but replaced main disc, Repaired Valve &

high pressure steam minimum implications pilot seat, and pilot Prepared for Second flow, since Unit 2 was in disc. Retested LLRT; Failed First SHUTDOWN mode.

satisfactorily..

LLRT.

Q42193 85-007 In 2-220-1 Itain Valve seating Leak rate exceeded Tech-Cleaned valve internals Steam Drain, surface wear.due to Spec limit 4.7.A.2.E.,

_and lapped the seat.

Rebuilt & re-high pressure steam but minimal lapped, new grease, flow.

implications. Since Failed LLRT.

Unit 2 vas in COLD SHUTDOUN mode.

Q42508 85-013 Unit 2 Diesel Governor compen-Unit 2 Diesel Generator The governor compensating Generator sating mechanism tripped on overspeed mechanism was properly was out of adjust-while 1/2 Diesel adjusted and successfully ment due to normal-Generator was out of tested.

operational wear, service. Declared GSEP Unusual event, but was minimal since Unit 2 was in COLD SHUTDOUN.

IV.

LICENSEE EVENT REPORTS r

l The follow 1ng is a tabular sumary of all. licensee event reports for l

-Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.8.2. of the Technical Specifications.

l l

UNIC 01."i Licensee Event Report Number Date Title of Occurrence 85-08 6-17-85 1C RHR Service Pump Inoperable; 1/2 Diesel l

Cenerator and IB RHR I

Service Water Pump Inoperable UNIT TWO 85-15 6-28-85 2A Reactor Building Ventilation Monitor Drift; Standby Gas Treatment System Auto-Start i

l l

l l

0027H

-0061Z

i j

l l

V.

DATA TABULATIONS I

The following data tabulations are presented in this report:

f l

... Operating Data Report A.

l l

B.

Averige Daily Unit Power Level C.

Unit Shutdowns and Power Reductions t

i e

b e

b j'

0027H l.

'0061Z

OPERATING DATA REPORT DOCKET NO.

50-254

)

UNIT ONE DATE. JULY 8 1985 COMPLETED BYCAR0t. L KRONICH TELEP HO NE309-654-224 i x 1(? 3 CPERATING STATUS

-0000 060105 1.

Reporting period:2400 063085 Gross hours in reporting period:

720 1

j 2.

Currently authorized power level (MWt): 2511 Mox. Depend copocity i

(MWe-Net): 769* Design electrical roting (MWe-Net): 789 3.

Power level to which restricted (if any)(MWa-Net): NA 4.

Reascos for r e s t r i c t.t o n (if any):

1 l

lhis Month Yr,to Date CumulotIve l

r 5.

Number of hours reactor was critical 706.4 4094.0 92416.4 i

6.

Reactor reserve shutdown hours 0.0 0.0 3421.9

}

l 7.

Hours generator on line 6'70.1 4036.4 89071.7

8. Unit reserve shutdown' hours.

0,0 0.0 909.2 9.

Gross thermol energy generated (MWH) 1633804 9481367 185227757

10. Gross electrical energy generated (MWH) 538583 3131841 59909292

[

11. Het electrical energy generated (MWH) 515297 2999088 55954790 J'

12. Reactor service factor 98.1 94.3 00.2 i

13. Reactor ovcilobility factor 98.i 94.3 83.2 i

l

.14.

Unit service factor 97.0 92.9 77.3

15. Unit cvullability factor 97.0

/

92.9 78,1 i

16 Unit cocccity factor (Using MDC) 93,1 89.8 63.2 17 Unit ccpacity factor (Using Das.MWe) 90.7.

07.5 61,6 1

1 18, Un tt forced outoga rate 5.9 7._0 6,t

19. Shu tdowns scheduled over next 6 months fType, Dote,ond Duration of each) l

20. If shutdown at end of report period,ect anted date of starten ___l@________

.8%e FX ncy be luer tran 7f,9 Ne dsting perisds of ti;h canent tea;eretste he i

to the thernal perfstnance of the spray canol.

$UWFICIAL COMPANY te$ERS ARE USED IN THIS REPORT 4

(

OPERATING DATA REPORT DOCKET NO.

50-265 l

UNIT TWO l

DATElULY O 1985 COMPLETED BYCAROL L KRONICH TELEPHONE 309-654-2241x193 OPERATING STATUS 0000 060185 1.

Reporting period:2400 063085 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 Cumulative 5.

Nunber of hours reactor was critical 601.0 2231.8 87137.8 6.

Reactor reserve shutdown hours 0.0 0.0 2985.8 7.

Hours generator on line 551,3 2159.9 84209.1

8. Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thermal energy generated (MWH) 1146225 4068047 176387914

10. Gross electrical energy generated (MWH) 36900_5 1586554 56239965

11. Net electrical energy generated (MWH) 352439 1514501 52032490

12. Reactor service factor 83.5 51.4 76,3

13. Reactor availability factor R3,5 51.4 78.9

14. Unit service factor 76.6 49,7 73.7 15.-Unit ovellability factor 76.6 49.7 74,3

16. Unit capacity factor (Using MDC) 63,7 45.3 60,1

17. Unit copocity factor (Using Des.MWe) 62.0 44.2 50,6

18. Unit forced outage rate 0.0 8.1 8.4

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

20. If shutdown of end of report period,estinated date of startup

_)@__________

• The 19C m1f he 1swer then 769 Ne during periods si high onbient tenperature dit et the thersol performance of the sprop canal.

l

$UN0FFICIAL COMPANY NUMPERS f.GE USED IN THIS REPORT j

1

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254 UNIT ONE DATEJQLY G 1705 COMPLETED BYCAROL L KRONICH TELEPHONE 309-654-2241x193 MONTH-June-1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

2.5 17.

776.2 2.

489.2 18, 778.9 3.

736.7 19.

771.6 4,

760.4 20, 737.8 5.

748.6 21, 721.1

-6.

846.0 22.

751.0 7,

671.2 23, 622.6 8.

761.7 24.

771.7 9,

787.5 25.

739.4 10, 771.3 26, 752.2 ti.

701J 27, 781,2 i

12.

77i_.3_

20.

74i.i 13.

744.1 29, 765.6 14, 771.6 30.

630.5 15.

725.9 740.4 16.

INSTRUCTIONS On this forn, list the overait dsily snit power level ir St-Wet for tech day in the reporting nanth. Compete to the rectest whelt esgowatt.

%tse figsrts will be estd te plot a graph for enth reportir.g nenth. Nett that when noninen dependable ccp2 city is used for the net electrical rating of the unit there may be occasions when the daily citragt power letti tittels the 161% line (or the restricted power level lind,.In sich casts.the average daily unit power estpet sheet sheeld be festnoted to tipltin the opptrent unently

~

c APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEJULY 0 1705 COMPLETED DYCAROL L KRONICH TELEPil0NE309-654-2241 x 193 MONTH June 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Nat)

(MWe-Net) 1.

-5.2 17.

576.2 2.

-5.7 10.

725.3 3.

-5.8 19.

773.9 4.

-9.5 20.

778.4 5.

-10.4 21, 730.4 6.

-15.4 22.

717.1 7.

12.0.7 23.

615.1 8.

296.5 24, 745.3

?.

382.6 25.

771.1 10.

482.0 26.

735.1 11.

593.7 27, 774.2 12.

707.9 20, 713,8 13.

758.7 29.

763.8 14, 758.3 30.

748,0 15.

-6.8 16.

392.2 INSTRUCTIONS On this forn, list the average daily slit power level in IWe-Net for ecch day in the reporting rentL.terpite to the neuest whole neasectt.

These figures will be ssed to plot a graph for each repsrting nonth. Note that when esiinin dependeble cepetity is ssed for the net electrital rating of the init 1011 line (or the restricted power level line).,there not be occasions when the daily overage pswer level exceeds the In sich cases,the overcge delly snit power estpit sheet shseld be festnsted to explain the appvent ansnely

M M

M F"E M

M M

M M

$M M

99E f*4 P"Il

fe9 ID/SA APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.

050-254 August 1982 UNIT NAttE Quad-Cities Unit 1 COMPLETED BY C Kronich DATE July 8, 1935 REPORT 110NTil JUNE 1985 TELEPil0NE 309-654-2241 H

N w"

5

$E9 gw Am A* $

Q d

LICENSEE m@

EVENT DURATION d

Ei g g

u C3.

DATE (110URS)

REPORT NO.

CORRECTIVE ACT10NS/C0 tit 1ENTS g

85-30 850605 S

0.0 11 5

llA TURBIN Reduced load to 700 !Me for weekly Turbine surveillances 85-31 850617 F

0.0 D

5 85-08 ZZ ZZZZZZ Commenced orderly shutdown due to 1/2 Diesel Generator out of service and RHR Service Water pumps out of service con-currently (terminated shutdown - 3.75 hrs) 85-32 850623 S

0.0 11 5

ZZ ZZZZZZ Reduced load per Load Dispatcher 85-33 850630 S

0.0 H

5 RC CONROD Reduced load to 550 MWe for Control Rod pottern adjustment APPROVED AUG 1 G 1982

- - - - (final) y G. O d H

M M

M M

M M

M M

M M

IM M

M M

M

,m ID/SA APPENDIX D QTP 300-S13 UNIT Sl!UTDOWNS AND POWER REDUCTIONS Hev'sion 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY C Kronich DATE July 8, 1985 REPORT NONTil JUNC 1985 TELEPil0NE 309-654-2241 5

g m

w" 5

$$9 gw@

bi w LICENSEE 2@

h$

$ hM m

DURATION M

EVENT 5"

w NO.

DATE (110URS)

REPORT NO.

CORRECTIVE ACTIONS / COMMENTS 85-21 850614 S

21.65 B

5 IIB XXXXXX Reduced load and placed uni.t on IIOT STANDBY to repair EllC oil leak 85-22 850621 S

0.0 11 5

XX ZZZZZZ Reduced load to 750 MWe to place unit on Economic Generation Control (ECC) 85-23 850623 S

0.0 11 5

ZZ ZZZZZZ Reduced load per Load Dispatcher 85-24 850626 S

0.0 11 5

ZZ ZZZZZZ Reduced load per Load Dispatcher 85-25 850628 F

0.0 B

5 Hil HTEXCII Reduced load for 2B Feedwater IIeater leak repair APPROVED AUG 1 G 1982

- (final)

VGUdh

p -

l VI.

UNIQUE REPORTING REQUIREMENTS-l_

The following items are included in this report based on prior commitments j- -

to the co= mission:

l A.

Main Steam Relief Valve Operations Relief valve operations during the reporting period are summarized in the following table.f The table includes information as to which relief valve was. actuated, how it was actuated, and the circumstances resulting in its actuation.

Unit: One' Date: June 1, 1985 Valve Actuated No. & Type of Actuation 1-203-3A 1 Manual Plant Conditions: Reactor Pressure - 924 lbs Description of Events: Surveillance Technical Specification 4.5.D.l.b B.

Control Rod Drive Scram Timing Data for Units'One and Two The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 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.

1 l

l l

l 1

l i

L.

al a

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1 TO 12-31-85 AVERAGE TIME IN SECONDS AT %

Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION NUMBER 5

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 inse rt ion T iine) 6-8 176 0.31 0.68 1.45 2.54 3.17 Unit 2 Ilot Scran Tining (F-7)

(11-3 Out of Service but verified during cold tining)

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 Information", dated January 18, 1978.

i i

i 9

6 f

0027H 0061Z 1

l.

QTP 300-S32 Ravision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.

Unit:

21 Reload:

7 Cycle:

8 1-2-86 2.

Scheduled date for next refueling shutdown:

3 Scheduled date for restart following refueling:

4-2-86 4.

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

NOT AS YET DETERMINED.

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

)

Information:

DECC4BER 19,1985; IF LICENSING ACTION REQUIRED.

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-NONE PLANNED AT PRESENT TIME.

i

\\

t t

i 7.-

The number of fuel assemblies.

a.

Number of assemblics in core:

724 b.

Number of assemblies in spent fuel pool:

2340 8.

The present Itcensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned i

in number of fuel assemblies:

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 F

WPPROVED e APR 2 01978 a

Q.C.C.S.R.

QTP 300-S32 Ravision I i

QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST e

1.

Unit:

Q2 Reload:

7 Cycle:

8 2.

Scheduled date for next refueling shutdown:

10-6-86 3

Scheduled date for restart following refueling:

12-22-86 4.

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

Yes. A routine MAPLHGR amendment has been approved as a preparatory change to allow a 10 CFR 50.59 review.

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

Not Applicable.

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:

None planned at present time.

L 7

The number of fuel assemblies.

a.

Number of assembiles in core:

724 b.

Number of assembiles in spent fuel pool:

176 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 in number of fuel assemblies:

a.

Licensed storage capacity for spent fuel:

3897 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

/C P P R C) N/ E [>

s. APR 2 01978

~

C3. C:. c). EB. ft.

L._..._....._....___..'..

L

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

ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATHS Anticipated Transient Without Scram BWR Bolling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System E0F Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampilng System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor 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 MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolatior PCIONR Preconditioning Interim Operating Management Recommendations RBCCW Reactor Building Closed Cooling Water System RBH Rod Block Monitor j

i RCIC-Reactor Core Isolation Cooling System j

RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod North Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCH Turbine Building Closed Cooling Water Systein TIP Traversing Incore Probe TSC Technical Support Center 0027H 0061Z

Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, lilinois 61242 Telephone 309/654-2241 l

[

TKT-85-37 July 1, 1935 Director, Office 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 rnonth of June 1985.

Respectfully, CCMMONHEALTH EDIS0N CCMPANY QUAD-CITIES NUCLEAR POW TATION V

l T. K. Tamlyn Services Superintendent i

bb Enclosure ff

\\

0027H

\\

0061Z

- _ - _ _ _ _