ML20027D524
| ML20027D524 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/29/1980 |
| From: | Beth Brown COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20027D521 | List: |
| References | |
| NUDOCS 8211040441 | |
| Download: ML20027D524 (10) | |
Text
-
lW February 1977 2
1
'if Ad OPERATING DATA REPORT
,7 DOCKET NO.
50-254 UNIT ONE g
4G
.DATE February 29, 1980 COMPLETED BY B. Brown
)
~
TELEPHONE 303-654-2241 ext. 245 Il
![G OPERATING STATUS 0000 020180 2400 022980' 3
J.
Reporting period:
Gross hours in reporting period:
696 W
Currently author-I ed power level (MWt):
2511 Max. depend. capaci ty y
2.
t (MWe-Net) :
769* Design electrical rating (MWe-Net):
789
-i
?
L 3
Power level to which restricted (if any) (MWe-Net):
NA 4.
Reasons for restriction (if any):
This Month Yr. to Date Cu,mulative i
5 Number of hours reactor was critical 696.0' 144050
}56154.1 0.0 0.0 3h21.9 6.
Reactor reserve shutdown hours F-696.0 '
1440.0 53480.9 y
-7 Hours generator on 'ine 0.0 0.0 909 2 y
8.
Unit reserve shi.
an hours.
tc 1532337 3279550 107B23531 9., Gross thermal energy generated (HWH)
U
- 10. - Gross electrical engergy generated (MWH) 500761 1076887 34699941 477145
'1026916 32442452 11.
Net electrical Energy Generated
h h
12.
Reactor service factor 100.0 100.0 82.1 13 Reactor availabilify factor 100.0 87.1 inn n g!*
14.
Unit service factor 100.0 100.0 78.2 15 Unit availability factor 100.0 100.0 79.5 16.
Unit capactly factor (Using MDC) 89.1 92.7 61 7 17 Unit capacit.y factor (Using Des. HWe)
- 18. Unit forced outage rate 0.0
- 0. 0_
8.0 Tif 19 Shutdowns scheduledover *iext 6 months (Type, date, and durotlor$ of each):
g 20.
If shutdown at end of report period, estimated date.of startupjg.
NA
.i. 4: %
1
- The HDC may be lower than 769 MWe during periods of high ambiant temperature due to the thermal performance of the spray canal.
- 41Q 1, g 377
~
M.
B211040441 800303 1 (final)
L.,
PDR ADOCK 05000254 (Q. C. O. 5. p.
-...-.DR P
R
- -.-.~.
. February 1977 I
- g..
(
D.
OPERATING DATA REPORT
.g DOCKET NO. 50-265
[3, UNIT wo DATE February 29, 1980 COMPLETED By B. Brown
~
TELEPHONE 309-654-2241 ext. 245
~
OPERATING STATUS 0000 020180 2400 022980 3.
Reporting period:
Gross hours in reporting period:
696 cM 63 i-2.
Currently authort ed power level (MWt):
2511 Max. depend. capaci ty t
(MWe-Net) :
769* Design electrical rating (MWe-Net):
789 9
L 3
Power level to which restricted (if any) (MWe-Net):
NA c'
4.
Reasons for restriction (if any):
0 P
This Month Yr. to Date Cumulative
,s 00 00
$'53128.9 l
S.
Number of hours reactor was'criticai 0.0 0.0 2985.8 6.
Reactor reserve shutdown hours 0.0 0.0 50791.8 L
7 Hours generator on line
[
8.
Unit reserve shutdown hours.
O.0 0.0 702.9 St 9., Gross thermal energy generated (MWH) 0 0
103016109
- 10. - Gross electrical engergy generated (MWH) 20 27 32863077 _
11.
Net electrical Energy Generated
-13270
-27085 30715440 i
12.
Reactor service factor 0.0
' 0. 0 78.7 13 Reactor availabilify factor gg g_ g ny i i
l(f
- 14. Unit service factor 0.0 0.0 75.2 0.0 0.0 76.3 15 Unit availability factor L.
16.
Unit capactly factor (Using MDC)
-2.5
-2.4 59.2 A
17 Unit capacity factor (Using Des. MWe)
-2.4
-2.4 57.7 f
18.
Unit forced outage rate 0.0 0.0 9.2 19 Shutdowns scheduledover next 6 months (Type, date, and duration of each):
i 20.
If shutdown at end of report period, estimated date of startupA.
March 15, 1980
,. a, s y
.r,
- The MDC may be lower than 769 MWe during periods of high ambiant temperature due a
to the thermal performance of the spray canal.
- ffL' i g. jff) 1.)
o
{
l (final)
Q. C. O. S. A,
[
l trir s u; I
a Revision 4
~
d APPENDIX B Jun2 1976 AVERAGE DAILY UNIT-POWER LEVEL Docket No.
50-254
- Q
. ~.
3 Unit ONE k
Date 2-29-80 Completed by B. Brown l
Telephone 309-654-2241 ext.
245 m
HONTH February 1989' DAY AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
~
(MWe-Net) 1.
732.4 17, 708.5 2.
442.6 18.
'726.0 3
560.1 19, 734.1 4,
747 2 20.
726 8 5
762.4 21 724.2
.y
[
6.
760 5 22.
719.9 7
756.8 23 713 7 l.
8.
751 7 24.
294.0 399 9 9
737.9 25
>h 10..
710.3 26.
603 3 L9f" 11.
764.1 27 711.7 12.
679 9 28.
748.0 e
739 2 29 721.5 l
13 3
.3 14.
734.5 30.
736.6 33.
~n 15.
avFHvVED
- j 16.
733 5
's JUN 2 01976 1
INSTRUCTIONS On this form, lat the average daily unit power Icvel in ?.!Wc. Net for cach day in the reporting mo9thkukmOufSh:
nearest whoic inegawatt.
.}
These figures will be used to plot a graph for each reporting month. Note that when nuximum dependable capacityis
'd used for thi net cicetrical rating of the unit. there may be occasions when the daily ascrage power !cvel exceeds the 1001 line (or the restri. sed power lesel hac). In such cases, the average daily unit power output sheet should be footnoted to explans the apparent anomaly.
E. y 1 (final)
APPENDIX B Revision 4 k'
AVERAGE DAILY UNIT-POWER LEVEL Juna 1976 K-(Q Docket No.
50-265 WO Unit Date 2-29-80
~
~
B. Brown f
Completed by 309-654-2241 ext.
Telephone 245 re HONTH February 1980 DAY AV.ERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
'(HWe-lict)
(HWe-Net) 1.
-19.2 17
-17.'O m
' 18.8 2.
-19.5 18.
I 3
-17.5 19
-21.5 y
r 4.
-19.3 20.
-20,.0
-lb3 O
5
-18.4 21
.. e,
[
6.
~
-8.3 22.
-19 5
-18.1
)
7
-29 3 23 M
-18.4 L
8.
-17 3
- 24. _ _
p l
9
-18.8 25
-18.4 10.
-19 0 26.
-19.1
. I1.
-19 0 27
-18.3
%N 12.
-18.8 28.
-19.4
-20.1 13 21.3 29 e t<M 14.
-21.4 30.
b 15
-20.5 31, AFFHUVED Pg
-IO 3 16.
l Juli 2 01976 nn fM INSTRUCTIONS P'
On this form. hst the average daily unit power Icvel in ?.!Wc. Net for each day.in the reporting rno9th9uMuf3he l
nearest whole merswatt.
These figures will tc used to plot a graph for each reporting month. Note that when maximum dependsb!r espacityis d
used for the net electrical rating'of the unit. there may be ocessions when t!.e daily aserage power level exeecds the 1004 line (or the restrused power lesel kne). In such cases, the average daily unit power output sheet shou!d be footnoted to exp;am the apparent anomaly.
[fj 1 (final) t_.
9 M
F"1 P"1 r""1 P"1 3""5 r""'S M
n M
C""'S C
C n
n n, Q C" ]
Ql 0
D APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.
50-254 March 1978 UNIT NAME Quad-Citles Unit one COMPLETED BY D. Hannum DATE March 3, 1980 REPORT HONTH February 1980 TELEPHONE 309-654-2241 ex. 175 o
m i
Eb m
z r
Ee 8
@g5 LICENSEE gg gg i
po DURATION 6 p,"
EVENT y8 g8 (HOURS) 10.
DATE u-y5g REPORT NO.
8 CORRECTIVE ACTIONS / COMMENTS R
l 2
2-2-80 F
B NA NA NA NA Load reduction for investigation of potential j
con' denser tube leaks.
3 2-24-80 S
H NA NA NA
'NA Load reduction'for one-line contro1 rod sequence exchange.
i l
s i
6 l
4 l
i (finai)
O O
3 APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.50-265 March 1978 Quad-Cities Unit Two p
DATE March 3, 1980 REPORT HONTH February 1980 TELEPHONE 309-654-2241 ext. 245 3
oa Ee LICENSEE hg
$g R
DURATION $
p3 EVENT p8 S8 (HOURS)
NO.
DATE' u-5 CORRECTIVE ACTIONS / COMMENTS E5g REPORT NO.
R 4
i 13 791125 S
6'96 C
1 NA NA NA Unit Two Cvele 4 Refueling Outage i
i F
i e
9 n
j
.s4 (finai)
O
March 1978 QbAD-CITIESREFUEllllG
~
^
1HFORMAT10N REQUEST C.
1 Reload:
5
_ cycle:
6 c
- .1.
Uni t:
8 '.n_'An (h,+-anwn (EOC5 Scheduled.date for next refueling shutdown:
12 'T-80(Starttto BOC6) d
~
2.
Sciieduleddateforrestartfollowingrefueling:
3
-l Will refueling o'r resumption of operation thereaf ter require a tech
- 4.. specification change or other 1icense amendment:The review will be conducted ~
fos future cycles of Quad Cities Unit 1.
.in June, 1980.
scheduied date(s) for submitting proposed. licensing action and supporting information:
June, 1980 for.10CFR50.59 related changes ~
90 days 5
<t prior to shutdown.
Important licensing considerations associated w'ith r'efueling, e.g., new or
' different fuel desig'n or supplier, unreviewed design 'or performance 5nalysis 6.
methods, significant changes in fuel design, new operating procedures:
New fuel. designs:
Retrofit 8x8 f6el 2.65 w/o% (^- 224)
~
j, f
- 7., The number of fuel assemblies.
s.
i 724 Number of assemblics in core:
a.
~
596 Number of assemblies in spent fuel pool.
b.
i The present licensed spent fuel pool storage capacity an S.
in number of fuel assemblies:
1460 Licensed storage capacity for' spent fuel:
a.
^
.I-NoEe Planned increase in licensed storage:
.b.
refueling that can be discharged to the 9
The projected date of the last licensed capacity: Septeinber, 1985 l*
spent Tuel pool assuming the present (end of batch discharge' capability)
WPPROVND a
. +,. '
APR 2.01973 Q.C.O.S.R.
i I
-.eF1.
~-
~-._y.-
hevision 1 CUAD-CITIES REFUEllflG March 1978
!!!FORiiATIOi! REQUEST 1.
Unic:
2 Reload:
4 Cyc1 :
5 11-4-79 (Shutdown EOC4 2.
Scheduled date for next refueling shutdown:
3 Scheduled date for restart following refueling:
1-17-80 (Startuo BoC5)
~
4.
Will refueling o'r 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 2.
The review will be conducted by early September,1979 scheduled date(s) for submitting proposed licensing action and supporting 5
l Information: Early August,1979 for 10CFR50 59 related changes a 90 g
days prior to shutdown.,
Important licensing considerations associated with refueling, e.g., new or l
- 6. ' different fuel desig'n or supplier, unreviewed design or performance snalysis methods, significant changes in fuel design, new operating procedures:
l New Fuel Design:
Retrofit 8x8 fuel (180)
~
a nat. U at bundle top and bottom P
b two larger water rods
~
}-
c new enrichment distribution i
d propressurized
~
~
I This fuel design was 'previously used for Quad C1 tie ~s Unit 1 Cycle 5 E
and Dresden Unit 2 Cycle 7
~
g I
7 The number of fuel assemblics.
724
~
Ilumber of assemblies in core:
I a.
l b.
Ilumber of assemblics in spent fuel pool:
492 The present licensed spent fuel pool storage capacity and the size of any
~
}
S.
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.
Non$
I b.
Planned increase in licensed storage:
9 The projected date of the last refueling that ccn be discharged to the spent' fuel pool assuming the present licensed capacity: March, 1986 (End of batch discharge capability)
W P P R O V.E* D i
.- APR 2.01973
- Q. C. O. S. R.
6
...e*
.,,. - = = = = = =
Vill.
GLOSSARY The following abbreviations, which may have been used in the Monthly Report, are defined below:
CRD Control Rod Drive System SBLC Stand-By Liquid Control System MSIV Main Steam isolation Valve l
RHRS Residual Heat Removal System RCIC Reactor Core Isolation Cooling System HPCI High Pressure Coolant injection System SRM Source Range Monitor IRM Intermediate Range Monitor LPRM Local Power Range Monitor APRM Average Power Range Minitor TIP Traveling incore Probe q
RBCCW Reactor Building Closed Cooling Water System TBCCW Turbine Building Closed Cooling Water System RWM Rod Worth Minimizer SBGTS Stand-By Gas Treatment System HEPA High-Efficientry Particulate Filter Reactor Protection System RPS Integrated Primary Containment Leak Rate Test IPCLRT LPCI Low Pressure Coolant injection Mode of RHRS Rod Block Monitor RBM BWR Boiling Water Reactor ISI In-Service inspection
'g 8
MPC Maximum Permissable Concentration i
(
l PCI Primary Containment isolation SDC Shutdown Cooling Mode of RHRS 1
LLRT Local Leak Rate Testing MAPLHGR Maximum Average Planar Linear Heat Generation Rate R.O.
Reportable Occurrence DW Drywell Rx Reactor i
EHC Electro-Hydraulic Control System MCPR Minimum Critical Power Ratio Preconditioning interim Operating Management PCl0MR Recommendations LER Licensee Event Report ANSI American National Standards Institute k
NIOSH National Institute for Occupational Safety and Health ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring 1
l
\\
r l
I J
_