ML20027D509

Monthly Operating Repts for Apr 1980

ML20027D509
Person / Time
Site:	Quad Cities
Issue date:	05/01/1980
From:	Beth Brown COMMONWEALTH EDISON CO.
To:
Shared Package
ML20027D506	List: ML20027D505 ML20027D509
References
NUDOCS 8211040402
Download: ML20027D509 (14)

Text

~

OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATE May 1. 1980

~

COMPLETED BY ~B Brown. ,

TELEPHONE 309-654-2241, Ext 245 OPERATING STATUS 0000 040180 '

1. Reporting period:2400 043080 Gross hours in reporting period s. 719 ~

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 719.0 2903.0 5761.'.i

6. Reactor reserve shutdown hours 0.0 0.0 t i 3421.9

7. Hours generator on line '719.0 2903.0 54943.9

8. Unit reserve shutdown hours. 0.0 0.O' '909.2 ..

~

9. Gross thernal energy generated (MWH) 1652783 6642019 'i11186000

10. Gross electrical energy generated (MWH) 535624 2173081 35796135

11. Net electrical energy generated (MWH) 494512 2051141- 33466677' ,

12. Reactor service factor 100.0 100.0- 82.4

13. Reactor ovallobility factor 100'.5 100.0 87. 3 , ,

14. Unit service factor 100.0 100;0J 78.6'

15. Unit availability factor, 100.0 10b 0 79.9'

..~.:.

16. Unit capacity factor (Using MDC) 87.2 8 9 . 6_ T ~ '

'60'.7 }

m

17. # Unit capacity factor (Using Des.MWe) 89.4 91.9 62.3 f .

18. Unit forced outage rate 0.0 ,

O.0' 7.8 _

E .

... + '

. - . , ~*

19. Shutdowns scheduled over next 6 nonths (Type ,Date ,and Duration of. eoch ) :? ,P

')

s. , :, - : ,

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

' NA -

v . ~-.

8The MDC nay be lower than 769 MWe dering periods of high edient tenperatere det ' ^ ~f' ' S' '~ >'i to the thernal perfernance 4 the sprop conel.

8211040402 800505 -

.1: / ^ ' "UH ' ~

PDR ADOCK 05000254 .__~ - <

") # , .. . '

i> 'd R PDR m_ x-. *%,C w?r.9 W

~

OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATE May 1. 1980

. COMPLETED BY B Brown TELEPHONE 309-654-2241, Ext 245

~

j OPERATING STATUS 0000 040180 .

1. Reporting period:2400 043080 Cross hours in reporting period 719

.2. Currently authorized power level (MWt): 2511 Mox. 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 Cunujotiv

5. Number of hours reoc' tor was critical

\T.b153G-s \T*5 153d .*

b a>TI 532823

6. Reactor reserve shutdown hours 0.0 0.0k ' 2985.8 SO 9 tid

7. Hours generotor on line -

'1/ 71 8 \\971]T

/

50d W

8. Unit reserve shutdown hours. 0.0 0.0 702.9

9. Gross thermal energy genercted(MWH) 167344 167344 103183453

! r i 10. Gross electrical energy generated (MWH) 46936 46985 32910035 i

f 11. Het electrical energy generated (MWH) 39394 i*i28 30744253 il j 12. Reactor service factor 21.3 5.3 77.3

13. Reactor availability factor 21.3 5.3 81.6 i!

14. Unit service factor 10.0 2.5 73.7 t 15. Unit avo11obility' factor 10.0 2,5 74.8

16. Unit capacity -factor (Using MDC) 6.9 .i 56.5 l 17. Unit capacity factor (Using Des.MWe) 7.1 .i- 58.0 i

L s

18. Unit forced.outoge rote 62.3 62.3 9.4

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

i .

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

k *The MDC ney be leur than 769 MWe dering periods of high onbiont tenperatere det to the thernal perfernonce of the spray canal, ,

.a

,y a .: :. . l

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATE May 1. 1980 COMPLETED BY B Brown TELEPHONE 309-654-2241, Ext 245 MONTH April 1980 DAY AVERAGE DAILY POWER LEVEL DA'Y AVERAGE DAILY POWER LEVEL' (MWe-Net) ~ (MWe-Net)

i. 739.8 17, 689.5

2. 729.0 ' 18. 681.0

3. 719.2 19. 673.8

4. 737.0 20. 666.1

5. 743.6 21. E 693.6 1-

6. 693.0 22, 628.7 I 651.7

7. 736.7 23,

8. 724.3 24. 656.7 t

9. 721.0 25, 635.8 10, 720.0 26. 646.4 ii. 712.5 27. 601.3 1

12. 720.1 28, 648'.5 _

i. 3 . 708.5 29, 606.3

14. 703.4 30, 633.5 i .

15, 696.5

~16 . 697.3 INSTRUCTIONS On this fern, list the overage daily snit power level in leie-Net for each day in the reporting month.Conpete to the nearest whole negawatt. .

s These figures will be used to plot a graph for each reporting nenth. Note that when noxinen gependable capacity is used for the net electrical rating of the snit there may be occostens We the delly overage power level exceess the 1911 line (or the restricted power level line)lIn sich cases,the cetrage daily snit power setpet sheet sheeld be _ '

footnoted to explain the opperent onenely .

Z-- A - _4_ .. _m -.} _

a APPENDIX B AVERAGE DAZLY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATE May 1, 1980 .

COMPLETED BY B Brown - - --

TELEPHONE 309-654-2241, txt 2%

MONTH April 1980

~

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL.

~

(MWe-Net) (MWe-Net)

-4.9 17 . - -7.5 1.

-8 'i

~

2. -4.9 18.

3. -4.8 19. -8.4

~

4. -5.0 20. -11.3~

5. -5.0 21. f 97.0 i-

6. -4.8 22. -11.5

' 7. -4.5 2.5 . 86.9 B. -5.8 24, 273.9

(

9. -6.0 25. -12.0

10. -5.7 26. -11.5

11. -5.9 27. -11.2

12. -7.4 28. 229.7

13. -7.2 29. 495.3'

~

14. -8,5 30, 638.3

15. -8.4

16. -9.4 INSTRUCTIONS On this forn, list the average daily snit power level in MWe-Net for each dat in the reporting nonth. Compete to the necrest dele negawatt.

These ependable capacit!i s os d forfigeres the netwill be esed electrical to plot rating a grnph of tie snit t refornay ekth bereporting occastensnenth.

whenNote the dailythat overa when notinen 10lI line (or the restricted power level line)!!n sich cases,the average daily stpet snit sheet power sh:sid be le powe '

festnoted to explain the apparent onenal; _

6 D P* .M- d- 4,,, g_ ,

g. . - .

' '1 E C'M F-*"1 0""I l~1 t "9 T1 F"S l'9 F"1 n t""'*J C"'I  !""*1 C- 7 n C- ' , t i n p .

, , . APPENDIX D , , QTP 300-S13 -

50-254 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO. March 1978 quad-Citles One T. Hafera U_ NIT NAME , COMPLETED BY DATE M y 1, 1980 REPORT MONTH TELEPHONE APRIL 1980 309-654-2241 Ext. 176 m 5 -

m = Eb z E Ee @ gg$ LICENSEE pg gg ,

po' DURATION $ 5 !;;

• EVENT y8 g: 8 NO. DATE (HOURS) 5 y@g REPORT NO.

• 8 CORRECTIVE ACTIONS / COMMENTS R

6 800429 F 0.83 A NA 80-12/03L CB PUMPXX-B 1A Recirc pump tripped on low oil pressure when

. lAl Recird M-G Set oil pump tripped; IB Recirc pump was reduced to 30 percent power. Oil pump was restarted and performed satisfactorily; 14 Recirc pump was restarted and performed normally.

i

>l I

NJ i

i t

1 (final) e

• e . . .m

y.q

~ ~

p- [..[.[. q [A$ 7.U( } 5,u[ ,h 7 g g ,._q p. ,

o s

APPEllDIX D , .

QTP 300-S13 ',

50-265 UNIT Sil0TDOWNS AND POWER REDUCT10!45 Revision 5 DOCKET NO. March 1978 UNIT NAME Quad-Cities Tw T. Hafera

, COMPLETED BY DATE May 1, 1980 REPORT MONTil APRIL 1980 TELEPHONE 309-654-2241, 3 Ext. 176 m 8 -

m = Eb z 5 ye 8 g; $ LICENSEE pg gg ,

f- o DURATION 5g" EVENT *8 g:8 NO. DATE (HOURS) g5g REPORT NO. 8 CORRECTIVE ACTIONS / COMMENTS .

R

'Ibl* N A Unit Two Cycle 4 Refueling Outage 13 791125 5 463l15 C ty NA NA NA 1 800420 F U.1 r34'

$- A 1 80-II/03L CC VALVEN Repair 3C Electromatic Relief Valve 800422 18 /~

,63 00 Repair pressure suppression chamber vacuum 2 F A 1 80-10/03L SE C breakers

.n i, (finai)

s. -

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

A. Main Steam Relief Valve Operations 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 DESCRIPTIONS UNIT DATE ACTUATED ACTUATIONS CONDITIONS OF EVENTS 2 4-20-80 2-203-3A 1 Manual Rx Press Surveillance T.S.

2-203-3B 1 Manual 400 4.5.D.I.b. and 2-203-3C Failed to Open .

Acoustic Monitor 2-203-3D 1 Manual Modification Test 2-203-3E i Manual 2 4-21-80 2-203-3C Failed to Open Rx Press Test after fall 400 to open,on 4-20-80 2 4-23-80 2-203-3C 3 Hanual Rx Press Testa /kerfailto 2-203-3D 1 Manual 400 open on 4-20-80 &

Acoustic Monitor

- Modification Test.

(2-203-3C failed to open from control room. Actuated locally I time.

Adjusted stroke on pilot valve.

Operated 2 times from control room.)

u

\

i 4

, - - _ - m_. - . . - ,-. ...- _ _ _ _ _ . _ _ , . , . . _ _ . . , -

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.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.

i i

1

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT I & 2 CONTROL R0D DRIVES, FROM 1-1-80 TO 12-31-80 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION 20 50 90 Technical Specification 3 3.C.1 &

NUMBER 5 3.3.C.2 (Average Scram insertion Time).

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.

0.28 0.51 1.00 1.74 F-7 Cold Scram Timing Unit 2 G-9 and M-12 2-28 176 were timed on March I, 1980. N-4 1.98 sec was not scram timed and will be after repair of scram valve limit switches.

0.32 0.53 0.99 1.68 N-4 Unit 2 Rod N-4 was cold scram timed 4-15 1 to complete all of the cold scram 1.68 timing.

0.70 1.48 2.59 M-12 Sea B Hot Scram Timing Unit 2 4-21 89 0.32 3.19 4-24 88 0.31 0.69 1.46 2.56 E-10 Seq A Hot Scram Timing, Uni t 2 2.95 j 0.98 1.69 J-9 Cold Scrain Timir.g rois L-12, J-9, G-8

!4-27 4 0.28 0.51 1.75 and M-6 after drive replacement.

0.72 1.50 2.60 J-9 Hot Scram Timing rods L-12, J-9, G-8 4-28 4 0.32 and M-6 after drive replacement 2.76 l

\

VIl. REFUELING INFORMAT10N The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978 licensing memorandum (78-24) f rom D. E. O'Brien to C. Reed, et. al. , titled "Dresden, Quad-Cities, and Zion l

Station - NRC request for refueling information dated January 18, 1978.

i l

4

\

i

s .v. i u s . i n llarch 19/3

, "' /

• QhAD-CITIESREFUEll!1G ll!FOPJMTIO!; REQUEST .

C

(

e 5 .__ cycle: 6 _ .;

1 Reload:

.1. Unit: _

8_q1_'pn (m'Mnun (EOC5) 2.

Scheduled date for next refueling shutdown: - .

12-7-80(Startu.o BOC6)

Scheduled date for restart following refueling: ' '

3 hi l

4. Will refueling o'r resumption of operation d t: thereaf ter require a tec n caN

. specification change or other license amen men The review will' be conducted fos future cycles of Quad Cities Unit 1. . .

in June, 1980.

i .

Scheduled date(s) for submitting proposed. licensing act~aion _

90 and days support ng 5 June, 1980 for 10cFR50.59 related changes

~

~

information: ~. .

prior to shutdown. -

e.g., new or Important licensing considerations

6. ' dif ferent fuel desig'n or supplier, unreviewed design 'or performance Sna associated w'ith refueling, -

i d r s: c methods, significant changes in fuel design, new operat ng proce u e New fuel designs: Retrofit 8x8 fuel 2.65 w/o% (^- 224) .

(- .

} .

- ~

~/. , The number of fuel assemblies.

. 724

a.  !! umber,of assemblics in core:

596

b. ilumber of assemblies in spent fuel pool: .

fuel pool storage capacity and the size of any S.

The present licensed spentincrease in licensed storage capacity that has b .

in number -of fuel assemblies: ,

1460 .

a.

Licensed storage capacity for' spen't fuel:

' None .

b. Planned increase in licensed storage: _

refueling that can be discharged to the 9 The projected date of the last licensed capacity: Septeinber, 1985 pent' fuel ool asso:ning the present XPPROVND

~

end of ba ch discharge' capability)

APR 2.01973 O. C. O. S. R.

i F.evi s i on 1 e ,r ,1 .

March 1978

- QUAD-CITIES REFUEllitG .

INFORMATION REQUEST-i -

• 5 7 2 _ Reload: 4 Cycle: _ -

1. Unic: ,

Scheduled date for next refueling shutdown:

. 11-4'-79(ShutdownE004)

2.

• Schechuled date for restart following refueling: 1-17-80 (Startuo BoC5) 3 ' '

4. Will refueling o'r resumption of operation thereaf ter require a technical ^

No, Plan 10CFR50.59 Tiloads specification change or other license' amendment: The review will be conducted-for future cycles of Quad Cities Unit 2. -

by early September,1979 5

scheduled date(s) for' submitting proposed licensing action and supporting information: Early August,1J/9 for 100FR50.59 related changes a 90 days prior to shutdown. .

e.g., new or '

! 6. Important licensing considerations associated with refueling,

' dif ferent fu::1 desigh or supplier, unreviewed design or performance bnalysis -

methods, significant changes in fuel design, new operating procedures:

j New Fuel Design: Retrofit 8x8 fuel (180) . .

a nat. U at bundle top and bottom .

'" b two larger water rods j, _ _ ,

j' e new enrichraent distribution

~ --'

J .

. d prepressurized .

This fuel design was 'previously used for Quad Citie's Unit 1 Cycle 5 l '

and Dr sden Unit 2 Cycle 7 -

,P t

7 The number of fuel assemblics.

724

! a. Number of assemblies in core:

l Number of assemblies in spent fuel pool: 492 b.

! S. 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: -

i Licensed storage capacity for ' spent fuel: 1460 -

a.

Non I b. Planned increase in licensed storage: _

~9 The projected date of the last refueling that can be discharged to the

' spent Tuci pool assuming the present licensed capacity: March,' 1986 (End of batch discharge capability) X P P R O V .E D APR 2.01973 d* Q.C.O.S.R. ,

... e .5 Vill. GLOSSARY The following abbreviation which may have been used in the Monthly Report, are defined below:

CRD - Control Rod Drive System SBLC -

Standby Liquid Control System MSIV -

Main Steam isolation Valve RHRS - Residual Heat Removal System RCIC - Reactor Core isolation Cooling System HPCI -

High Pressure Coolant injection System S RM

- Source Range Monitor IRM - Intermediate Range Monitor LPRM - Local Power Range Monitor APRM -

Average Power Range Monitor TIP - Traveling incore Probe RBCCW - Reactor Building Closed Cooling Water System TBCCW - Turbine Building Closed Cooling Water System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System HEPA -

High-Efficiency Particulate Filter RPS - Reactor Protection System IPCLRT - Integrated Primary Containment Leak Rate Test LPCI - Low Pressure Coolant injection Mode of RHRS i

RBM -

Rod Block Monitor BWR -

Bolling Water Reactor l

ISI - In-Service inspection

\

MPC -

Maximum Permissible Concentration j

t i

- n 3 PCI - Primary Containment isolation SDC

- Shutdown Cooling Mode of RHRS LLRT - Local Leak Rate Testing MAPLHGR - Maximum Average Planar Linear Heat Generation Rate R.O. -

Reportable Occurrence DW -

Drywell RX Reactor l

EHC Electro-Hydraulic Control System MCPR -

Minimum Critical Power Ratio PC10MR - Preconditioning interim Operating Management Recommenda tions LER - Licensee Event Report ANSI -

American National Standards Institute ..

NIOSH - National instituteforOccupationalSafetyadh-Health ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring i

l l

l l

i c

- ._- _ _ - _ - - , - -- .. . ~ , - - . - . - - - , _ , - _ - - . , _ , _ _ - - . _ - - - _ , - - _ - _ , _ , _ . . . - - - -