ML20042A382

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Monthly Operating Repts for Apr 1981
ML20042A382
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 05/01/1981
From: Tubbs R
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20042A375 List:
References
NUDOCS 8203230375
Download: ML20042A382 (11)
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OPERATIllG DATA REPORT DOCI'ET 110. 50-294 UllIT Ot[E

- . DATE May 1, 1981

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COMPLETED DY R C Tubbs TELEPH0tJE 309-654-2241 ext ~~~774 OPERATING STATUS 0000 040101

1. Repor ting period :2400 043001 Gross hours in reporting period: 719 2, Currently authorized power level (MWt): 2511 Max. Depend capacity

( MWe --ile t ) : 7694 Design electrical rating ( Mue-fic t ) : 789

3. Power level to which restricted (if any)(MWe-tiet): NA
4. Reasons for restriction (if any): .

This Month Yr,to Date Cunulotive S. tdunber of hours reactor was critical 739.0 2710.0 63416.3

6. Reactor reserve shutdown hours 0.0 0.0 3421.9 719.0_ 2656.0 60539,8
7. Hours generator on line 0.0 0.0 909,2 B. Unit reserve shutdown hours.
9. Gross thernal energy generated (MUH) 1765545 6147461 122389549
10. Gross electrical energy generated (MWH) 579972 202411_4 39403021
11. N e 't electrical energy generated (MWH) 540673 1886242 36743521
12. Reactor syrvice factor 100.0 94.1 80.6 1.3 . Reactor ovcilobility factor 100.0 94.1 05.0
1. 4 . Unit service factor 100.0 92.3 77.0
15. Unit ovallobility factor 100.0 92.3 70.1
16. Unit capacity factor (Using MDC) 97.0 05.2 60.8
1. 7 . Unit capacity factor (Using Des.MWe) 95.3 83.0 59.2
10. Unit forccd outage rate - 0 . 0__ 2.3 7.6
19. Shutdowns scheduled over next 6 nonths (Type, Dote,and Duration of each):
20. If shutdown at end of report period, estimated date of startup NA

-C 8203230375 810501 inds of high edient terpuotne he PDR ADOCK 05000254

OPER A'I ING DAT A REP ORT D O C ,'a.  ?!G . 50-265 UNIT TWO

- . DATE _May 1, 1981

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COMi'LETED BY R C Tubbs TI:LEPl10NE 309-654-2241, ext. I'74 OPER ATING STATUS 0000 040181

1. Reporting period:2400 043001 Gross hours ,n reporting period: 719
2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 709
3. Power level to which restricted (if any)(MWe-Net): NA
4. Heosons f or restriction (if any):

This Month Yr,to Date Cumulotive

5. Nunber of hours reactor was critical 677.5 2783.6 61616.4_-

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6. Reuctor reserve shutdown hours 0.0 0.0 2905.8
7. Hours generutor on line 667.0 2757.0 59039.0
8. Unit reserve shutdown hours. 0.0 0.0 702.9
7. Gross thernal energy generated (MWH) 1566169 6436213 121636621
10. Gross electrical energy generated (hWH) 499989 2047887_ 30769430
11. Het electrical energy generated (MWH) 476_B2Z 1940614 362(?7566
12. Reactor service factor 94.2 96._7 79.3
13. Reactor availability factor 94.2 96.7 03.1
14. Unit service fuctor 92.9 95.0 76.
15. Unit ovallobility factor 92.9 95.0 76.9
16. Unit cupacity factor (Using MDC) 86.2 G7.7 60.7
17. Unit capacity factor (Using Des.MWe) 84.1 05.4 59.2
10. Unit forced outage rate . 7.1 1.8 0.8
19. Shutdowns scheduled over next 6 nonths (Type,Date,and Dorotion of coch ) .

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20. If shutdown at end of report period,estinated date of sto-tup __NA___,_______
  • The MC my be lower then 769 M'Je during periods of high ambient terperature due to the thernl perf arnece of the sprey ccnol.

AP P El11/lX It AVERAGE DAILY UtJI T POWER LIVEL DOEKET t10, 50-254 Ut1T T OtJE _

DALE May 1, 1981 _~

C0tiPLETED 14Y R C Tubbs TELEPIlot1E_}09-654-224L ext. 174 Mut1TH Apr 11 i901 _

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL

( t1Ue -tJe t ) ( tiUc-fle t )

1. , 70L_8 17. 762.0 2, 751.0 18. 762.5
3. ___

750.7 19. 741.6 20, 755,1

4. 776.;' .
5. 7?7.6 21. 755.2 L
6.
  • 750.9 22. 760.8
7. 745.3 23, 776.9 H. 756.4 24. 735.7 9 .- 761.6 25, 759.7
10. 746.9 26, 656.3
11. 762.2 27. 767 ?

!2. 739,2 20. 753.0

1. 3 . 755.2 29. 770.7 14, 755.7 30. 7^9.4 iG. 766.6 __
16. 755.0 It4STR UC T 10tJS On this fern. list the overegt dcily enit power level in Hh-Nit fer ec h do; in the reporting nonth, Compute to the .,

neertst khalt etacw3tt,.

is Ihtst figsres will be used to plot a crc;h f6r cath reportire eenth, tJ te that .htn r.0 imum deperdoble capacit!s the used for the net electrical rating ef'the snit,there may te accesions wken the daily overc;e pcwcr level excee 1003 line (6r the restricted power level line).In Suth ccses,the overcge daily snit p0Wer output steet sha'Jld be -

footnoted to explain the c;p: rent onently

, APPENDIX 14 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-365 UNIT TWO

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DATE May 1, 1981 ,_

COMPLETED BY R C Tubbs TELEPHONE 309-654-2241 ext. 174 110 NTH Ant 11 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWc-Net) (MWe-Net)

1. 751.4 17. 750.5
2. 742,0 18. 739.0
3. 749.5 19. 748,1
4. 757.4 20, 738.5
5. 744.4 21, 726.3 ,
6. 730,n 22. 729.6
7. 727.4 23. 748.6 U. 74n.5 24. 698.9
7. 741.0 25. 671.1 *
10. 727.6 26. .6
11. 611.5 27. -15.3 12, 701.0 20, 312.2
13. 754.8 29. 550.4
14. 758.8 30. 714.7
15. 759.0 l 16. 749.6 i

INSTRUCTIONS On this forn, list the overage daily init power level in Mile-Net for toch day in the reporting conth. Compete to the negrest whole necowstt.

These figures wifl be efed to plot a graph ist each reporting nonth. Nate that when noxinun dependable capacity is used for the net electrical rating of the unit there may be occasions when the dcily overage power level exceels the 1991line (or the restricted power level line).,In scch cases,the overage daily snit power output sheet should be festneVed to explain the opperent ons.ioly 1 l -

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twe r g y .$ ,r $ p_ ., I'7 '9 n u j n n r i 'h i g-

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APPEND 1X D QTP 300-S13 50-25 UNIT SHUTDOWNS AND POVER REDUCTIONS Reviste, 5 DOCKET NO.

March 1978 UNIT NAME Quad-Cities Unit On COMPLETED BY R C Tubbs DATE MoY I. I90I REPORT MotiTil APRIL 1981 TELEPHONE 309-654-2241, o

e'x t . 174 m 8 -

m = E0 z 5

, Ee 8 @p$ LICENSEE gg gg i

C u-OURATION $ 5 !;" EVENT m8 g3 -

1 NO. DATE (HOURS)

  • y=y REPORT NO. "

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8 CORRECTIVE ACTIONS /COMENTS i

81-8 810426 s 0.0 B/H 5 RB CONROD Load reduction to perform special rod moves, Turbine weekly tests and reverse condenser

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APPENDIX D

" QTP 300-T.13 50-265 " ^" " '

DOCKET NO.

March 1973 UNIT NAME -

Qu d-Cities Unit Two COMPLETED BY R C Tubbs DATE May 1, 1981 APRIL 1981 REPORT MONTH TELEPHONE 309-654-2241

  • t AL. 6 /t w 8 -

m = Eb z 5 Ee 8 @p$ LICENSEE Wg gg yo' OURATION $ 5 t;;

  • EVENT *8 g: 8 NO. DATE (HOURS) y=g REPORT NO.
  • 8 CORRECTIVE ACTIONS / COMMENTS R

81-7 810411 S 0 .,0 B/H 5 RB CONROD Load reduction to perform special rod moves, Turbire weekly tests, and reverse condenser

, flow.

81-8 810426 F 51.3 B 2 MA ZZZZZZ Excessive leakage from improper valve line up into Drywell sump.

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

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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 DESCRIPTION UNIT DATE ACTUATED ACTUATIONS CONDITIONS OF EVENTS 2 4-26-81 2-203-3A I Manual RX PRESS Surveillance

, 2-203-3B 1 Manual 920 T.S. 4.5.D.I.b.

2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual 2 4-28-81 2-203-3B 1 Manual RX PRESS Post Maintenance 2-203-3C 1 Manual 600 (Replaced pilot .2 2-203-3D 1 Manual solenoid valve) 2-203-3E 1 Manual

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B. Control Rod Drive Scram Timing Data For Units One and Two There were no Control Rod Drive Scram Timings for the report *ng period.

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Vll. REFUELING lilFORitATION 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.

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QTP 300-532 Revision 1

, QUAD-CITIES REFUELING March 1978

.(n lilFORMATION REQUEST

1. Unit: 1 Reload: -

6 Cycle: 7

2. Scheduled date for next' refueling shutdown: 9-12-82 (Shutdown EOC6) 3 Scheduled date for restart following refueling: 12-5-82 (Startup BOC7)
4. Will refueling or resumption of operation thereaf ter require a technical specification change or other IIcense amendment: No, Plan 10CFR50 59 reloads for future cycles of Quad Cities Unit 1. The review will be conducted in August, 1982.

5 Scheduled date(s) for submitting proposed licensing action and supporting information: August, 1982 for 10CFR50.59 related changes es 90 days prior to shutdown.

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:

New fuel designs: ..

7. The number of fuel assemblies.
a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 820
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: 1460
b. Planned increase in licensed storage: None t'
9. The projected date of the last refueling that, can be discharged to the (

spent fuel pool assuming the present licensed capacity: September, 1985 J (end of batch discharge capability) --

(- 4PPROVED APR 2 01973

, O. C. O. S. R.

QTP 300-532 Revision 1 QUAD-C! TIES REFUELING March 1978

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INr0RMATICN REQUEST

1. Unit: 2 Reload: 5 Cycle: 6
2. Scheduled date for next refueling shutdown: 8-30-81 (Shutdown E0C5) 3 Scheduled date for restart following refueling: 12-20-81 (startuo BOC6)
4. Will refueling or resumption of operation thereaf ter require a technic 61 specification change or other license amendment: No, Plan 10CFR50 59 Reloads for future cycles of Quad Cities Unit 2. The review will be conducted by early August, 1981.
5. Scheduled date(s) for submitting proposed licensing action and supporting

. Information: Early August, 1981 for 10CFR50.59 related changes as90 days prior to shutdown.

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6. Important licensing considerations associated with refueling, e.g., new or

'different fuci design or supplier, unreviewed design or performance analysis -'

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

New Fuel Design: 1. Barrier Fuel .;

2. Control Cell Core e

7 The number of fuel a,ssemblies.

a. Number of assemblies in core: 724
b. Number of assemblies in spent fuel pool: 672
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: 1460
b. Planned increase in licensed storage: None a

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

spent fuel pool assuming the present licensed capacity: September. 1984 (End of batch discharge capability) ,

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APR 2 01973 Q.c.o.S.R.

Vill. GLOSSARY The ft lowing abbreviations which may have been used in the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment -

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Atmospheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor ATWS -

Anticipated Transient Without Scram BWR -

Bolling Water Reactor CRD -

Control Rod Drive EHC -

Electro-Hydraulic Control System EOF -

Emergency Operations Facility GSEP -

Generating Station Emergency Plan HEPA -

High-Efficiency Particulate Filter HPCI -

High Pressure Coolant injection System HRSS -

High Radiation Sampling System IPCLRT -

Integrated Primary Containment Leak Ra'. 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 Fower Range Monitor .:.

MAPLHGR -

Maximum Average Planar Linear Heat Generation Rate MCPR -

Minimum Critical Power Ratio MPC -

Maximum Permissible Concentration MSlV -

Main Steam isolation Valve NIOSH -

National Institute for Occupational Safety and Health PCI -

Primary Containment Isolation PCIOMR -

Preconditioning Interim Operating Management Recommendations RBCCW -

Reactor Building Closed Cooling Water System RBM -

Rod Block Monitor RCIC -

Reactor Core Isolation Cooling System RHRS -

Residual Heat Removal System RPS -

Reactor Protection System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System 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 -

Traveling Incore Probe TSC -

Technical Support Center

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