ML20027D495
| ML20027D495 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/01/1981 |
| From: | Tubbs R COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20027D494 | List: |
| References | |
| NUDOCS 8211040368 | |
| Download: ML20027D495 (11) | |
Text
__
OPERATING DATA REPORT DOCKET NO.
50-254
. ~ - ~ ' ~ ONE
' ' ' ~ ~ ~ ~
~
DATE0ctober 1 1981 COMPLETED BYRobert C Tubbs
_. _ _.__. TELEPHONE 309;654;224iXi74 OPERATING STATUS
~~ ~~
~ ~ - ~
-- ~ ~ ~ ~ ~ ~ ~
' 0 0 0 0 0 9 0181 ~~~ ~ ~ ~ ~-
- 1. Reporting period:2400 093081 Gross hours in reporting period:
720
- 2. Currentlp"outhorized power ~1cW 1~(MWt')T 25ii Max.Depdhd~copoc~ity
~~ ~
~
(MWe-Net): 769* Design electrical roting (MWe-Net): 789 l
- 3. Powdr level to-wh ich~ r es t r ic t ed (Tf ~on yT(MWe-Ne t ) :7 A~~ ~~
-- -~------
4.
Reasons for restriction (if any):
This Month Yr.to Date Cumulative
- 5. Number of hours reactor was~~ critical ~ ~ ~ ~~ 712.2
~
6301.6..* ~ ~ 67 0 07. 9 -~
~
~~
j.
- 6. Reactor reserve shutdown hours 0.0 0.0 3421.9
- 7. Hours generator on line 708.4 6171.8 64055.6
- 8. Unit reserve shutdown'houFs. - ~'~
~
~ ' - ~ ~ 0 ~. 0 0.0 909.2~
~
~
[
9._ Gross thernal ene_rgy generated (MWH) 1645941 13948598 130190686
- 10. Gross electrical energy generated (MWH) 534250 4542671 41921578 ii. Net e lec t r ical ~ e nerg y generothd (MWH)~-~-~ ~ ~49901~6~ ~ ~~4223845 '~ 39081124
- 12. Reactor service factor 98.9 96.2 81.4
- 13. Reactor availability factor 98.9 96.2 85.6
{
- 14. Unit-ser vTce"f oc t or-- - - - - -
-~
'98 :4 -
9 4. 2
77.8 ^
i
- 15. Unit availability factor 98.4 94.2 78.9
- 16. Unit capacity factor (Using MDC) 90.1 83.8 61.7 I g e l.7. Unit copocity factor (Using~ Des ~iMWs)~~~
B T.' B ~
'- ~ ~ ' 81. 7_
~
60~.2-~
3> mo
- o nia.18. Unit forced outoge rate 1.6
\\ 2.6 7.3 o
l~m
- 19. Shutdowns scheduled over next 6 months (Type,Date,ond Duration of each):
O O
mv 20. If shutdown at e nd 'o f rc p o r f p er'i o d, s s t'iWEtid-d ot e orst or t u p _JUL____Z_~__
~
~
~
00 to 04 tihe MC n2y be lower than 769 MWe daring periods of high anblant temperatore due~~~~~~ ~ '~~~ ~
~
~~'
g to the thern21 performance of the sprey canal ~ '
~
~~
ha.x
OPERATING DATA REPORT DOCKET NO.
50-265 l
~
- ~ ~ - - ~ ~
~~ ~ ~~
~ ~ ~
~
' UNIT
~~
TWO
~ ~ ~ ' ~
~
l DATE0ctober i 1981 COMPLETED BYRobert C Tubbs l
~
.~
-~~ TELEPHONE 309;-654;2241Xi74~ ~
OPERATING STATUS
~ ~ ~~~- ~ ~ ~ ~ ~ ~ ~ ~
~ -~
- ~ ~ ~ 0 0 0 0 0 9 0 i 81~~
---~-~~~ '
- 1. Reporting period:2400 093081 Gross hours in reporting period:
720 2.
Currently cuthoFized ~ power level-~(MutTi 2511 M6Y~. Depend copocity'~~~~ ~
~
(MWe-Net): 769* Design electrical rating (MWe-Net): 789
~ ~ ~ ~ ~ - ' ~ ~
- 3. Power leve1 to whTch Festricted(If~any)(MWe-Net): NA~ ~ --~
~
~
~
~
4.
Reasons for restriction (if any):
This Month Yr.to Date Cumulative
~ 5. Number-o f hi u r;s ~r e c~c t o r" was c r i t ic o1~ ~ ~~ 14574 -
5881.03 64713 8 R k'
- 6. Reactor reserve shutdown hours 0.0 0.0 2985.8 7.
Hours generator on line 144.3.
5854.1 62135.3 8.~ Unit ~ reser ve sku~td owri h ours. ~~
~
'~ ~~-'~ ~ 0. 0 ~ ~~
0.0 702.9
~
- 9. Gross thernal ener_gy generated (MWH) 2361'80 12558041 127758449
- 1. 0. Gross electrical energy generated (MWH) 71734 3948205 40669756
- 11. Net electrical energy generated (MWH)~
64507 3739209 38096161
- 12. Reactor service factor 20.2 89.8 79.5
- 1. 3. Reactor ovallobility factor 20.2 89.8 83.2
- 14. Unit ~ service'foctor 2 0 7 0 ~~~~- ~ ~ 89 / 4
~ ~ 76.3
- 1. 5. Unit ovallobility factor 20.0.
89.4 77.2 t
- 16. Unit copocity factor (Using MDC) 11.7 74.2 60,9
- 17. Unit capacity factor (Using Des.MWe)~
'-~~
11.4
~ 72.3 59.3~~
\\
.9 8.4 0.0 1.0. Unit forced outoge rate
- 19. Shutdowns scheduled over next 6 nonths (Type, Dote,and Duration of each ):
s
~
~ f s t or t u p
_1_2_,22-81______ ~
of ~r eport p er i o d 'ie~s~t'inat e d 'd at e o
- 20. If shutdown ot~ end -
37he MDC nh be lower than 769 MWe dering periods of high onblant tenperatsre due to the thernal perferncnce of the sproj canal.
APPENDXX B-AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-254 UNIT ONE
.._.D ATE 0c t o b e re i-19 81- -
~
COMPLETED BYRobert C Tubbs TELEPHONE 309-654-2241Xi74
' ~~~HONTH ~~~Se n thb e r i'981- ~
~ ~ - -
~~-
~~~
~ ~ ~ ~ ~ ~
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL' ' ~
~ (MME-Ne t')
~~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
-~(MWe'-Net)'
J 1.
739.1 17, 743.8 2.
732.1 18.
748.6 4,
738.4 20.
678.2 5.
499.8 21.
73b.B 560T9~'
~~~~-~~'-~--~~~22~.-~~~~--
~ ~'
754.0-~~ - ~-~
7.
592.2 23.
235.4 8.
709.9 24, 506.8
~
'9.
~ 7 4 4.' O "~ ~~ ~
~~~-25, - ~
~ ~ ~
~
~673.B~
10.
743.2 26, 765.7 ii.
742.9 27 711.1 12.
~746.0-~~ - ' --------~~
28.~
~ ~ ~ ~ - ~ ~ 768. 4
~ - ~ ~ ~ ~
13.
713.7 29.
722.8 14, 737.9 30.
748.5 5.
~~
~ ~ ~ ~
- W2T
'--~~-~~~~'
~ ~ ~ ' - ' ~ ~
~ ~ ~ ~ ~ ~ - -
16, 751.O s
INSTRUCTIONS On this fern, list the average daily unit power level in Nit-Net for each day in the reporting nonth.0enpite to the recrest 6hele eecavatte --
These ficeres will be osed to plot a graph for each reporting nonth. Note that when narinen dependable capacity is tsed for tne net electrical rating of the ontt there not be occassens when the daily average power level exceels the-1801line (cr the restricted power level line).,In such cases,the average daily unit power estost sheet should be festnotet to explain the a;prent.cacncly p.
,s..
e,
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-265 UNIT TWO
-.. _. D ATE 0 c t ob e r i ~ 19 81-~ ~ ~
COMPLETED BYRobert C Tubbs TELEPHONE 309-654-224tXi74 MONTH ~~Sep t e nber ~ 198f~
~ ~
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER _ LEVEL
_g g..__._.
)
i.
479.i 17.
-5.7 2.
471.7 18.
-4.5
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20.
-4.3 4.
468.4 5.
472.3 21.
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-11.3 23.
-2.8 0.
-9.6 24.
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9.
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- 1. 0.
-6.1 26.
-2,i 1.1.
-6.0 27.
-2.0 12.-
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~-2.1 13.
-6.0 29.
-2.0 i
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-6.0 30.
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16.
-5.9 INSTRUCTIONS On this fern, list the avercge daily unit power level in Me-Net for each dat n the reporting nonth.Conpate to the-i neoetst whole neaawatt. -- -
le capacit is These figires will be used te olet a gr$ch for each repartina ncnth. Note thgt uhto notinen dependogevel exce esto for the net electratal rating of t e snit,there nay be 6ttastens when the daily overage power 1001 line (or the restricted power level line).In such cases,the average daily snit power estput sheet shegld be feetneted to explain the c; parent ananaly-
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('T APPENDIX D QTP 300-S13 DOCKET NO.
50-254 UNIT Sl1UT00WNS AND POWER REDUCTIONS Revision 5 March 1978 UHlT NAME qu d-Cities Unit One rf COMPLETED BY R. C. Tubbs DATE October 1, 1981 REPORT MONT}i SEPTEMBER 1981 TELEPHONE x
74
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LICENSEE pg gg so DURATION $
IH" EVENT mo
- a. o hh h"
CORRECTIVE ACTIONS / COMMENTS (HOURS)
NO.
DATE REPORT NO.
.l-24 810905 S
0.0 B/H 5
RB CONROD Reduced load for weekly Turbine tests; and to change the control rod pattern 31-25 810923 F
11.6
'G 3
HC ZZZZZZ Reactor scram on Condenser Low Vacuum, due to improper valve line up 4
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VI.
UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior cemitments to the cmmission:
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 war 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
9-7-81 2-203-3A 1 Manual Rx Press Surveillance 2-203-3B 1 Manual 980 T.S. 4.5.D.1.b 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3:
1 Manual k
B.
CONTROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND WO There were no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.
\\
I VII.
REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandtsu (78-24) frcu 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.
9 E
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g.
7-,
..--,-e
&,m
--y y
9 - - - -
.--__y.
-w
\\-
QTP 300-532 Revision 1 QUAD-CITIES REFUELING March 1978
.(--
INFORMATION REQUEST 1.
Unit:
1 Reload:
6 Cycle:
7 2.
Scheduled date for next refueling shutdown:
9-12-82 (Shutdown EOC6) 12-5-82 (Startup BOC7) 3 Scheduled date for restart following refueling:
4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license 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 changeses 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:
'k '
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 fuei assemblies:
Licensed storage capacity for spent fuel:
1460 a.
b.
Planned increase in licensed storage:
None 9
The projected date of the last refueling that can be disch'arged to the spent fuel pool assuming the present licensed capacity: Septembe., 1985 (end of batch discharge capability)
WPPROVED
.(~
.. APR 2 01978 Q.C.G.S.R.
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING Harch 1978
-(-.
INFORMATION REQUEST 1.
Unit:
2 Reload:
5 Cycle:
6 2.
Scheduled date for next refueling shutdown:
8-30-81 (Shutdown EOCS) 3 Scheduled date for restart following refueling:
. 12-20-81 (Startup BOC6) 4.
Will refueling or resumption of operation thereafter require a technical 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 - 90 days prior to snutdown.
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 Design:
1.
Barrier Fuel 2.
Control Cell Core F
7 The number of fuel a.ssemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
672 1
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:
Licensed storage capacity for spent fuel:
1460 a.
None b.
Planned increase in licensed storage:
9 The projected date of the last refueling that can be discharged to the spent fuel pcol assuming the present licensed capacity:
September, 1984 (End of batch discharge capability)
XPPROVED Q,
APR 2 01978 C3. CL C).E5. R.
I
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 American National Standards Institute ANSI APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Energency Operations Facility GS EP Generating Stations Emergency Plan High-Efficiency Particulate Filter HEPA HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inservice Inspection LER Licensee Event Report LLRT Local Leak Rate Test j
LPCI Low Pressure Coolant Injection Mode of RHRS LPRM Local Power Range Monitor MAPLHGR Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio MCPR MFLCPR Maximum Fraction Limiting Critical Power Ratio MFC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containnent Isolation Preconditioning Interim Operating Management Recommendations PCIOMR Reactor Building Closed Cooling Water System RBCCW RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System Rod Worth Minimizer l
RRM SBGTS Standby Gas Treatment System Standby Liquid Control SBLC l
SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Thirbine Building Closed Cooling Water System TIP Traveling Incore Probe Technical Support Centcr TSC g
f
_-