ML19340F004
| ML19340F004 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/02/1981 |
| From: | Dupree D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19340F003 | List: |
| References | |
| NUDOCS 8101160474 | |
| Download: ML19340F004 (10) | |
Text
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT DECEMBER 1 - DECEMBER 31, 1980 i
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 j
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l TABLE OF CONTENTS f
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Operations Summary..
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Significant Operational Events
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Average Daily Unit Power Level.....................
3 1
l Operating Data Report-
.4 i
j Unit Shutdown and Power Reduction
. 5-6 Plant Maintenance Summary
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i Outage Maintenance Summary..
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Operations Summary December, 1980 The following summary describes the significant operational activities i
for the month of December.
In support of this summary, a chronological log of significant events is included in this report.
There were fifteen Licensee Event Reports and one Special Report, 80-6, inadvertant injection of Sodium-24 into the turbine building sump.
There were four scrams during December.
Unit 1 continued testing in preparations for full power operation. The reactor was at 75% power producing 900 MW's at the beginning of the month.
(
On December 6,1980, the reactor scrammed and remained in mode 5 for eight days for oil seal repairs on the RCP's and other general maintenance. The reactor was taken critical on December 14, 1980 and was in mode 1 at 90%
power producing 1030 MW's at the end of the month.
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r-Significant Operational Events Date Time Event 12/01/80 0001 Unit I was in mode 1 at 75% reactor power; 900 MW's.
12/02/80 0752 The reactor tripped due to a turbine trip caused by a loss of vacuum when condenser circulating water pump 1A tripped. A faulty pressure switch caused the back flow gates to close which tripped the condenser circulating water pumps IB and 1C.
1 12/02/80 2224 Reactor critical.
12/02/80 2252 Reactor tripped on #1 S/G low low level ala rm.
12/03/80 0028 Reactor critical.
12/03/80 0515 Reactor tripped because a high generator stator temperature caused a turbine trip.
The stator cooling water isolation valve was found isolated.
12/03/80 0937 Reactor critical.
12/06/80 1330 Reactor tripped because test instrumentation was improperly installed.
12/07/80 0845 Reactor in mode 5.
12/14/80 2130 Reactor critical.
12/29/80 0902 Reactor at 90% power.
12/29/80 2100 Unit I cooling tower put in service.
12/31/80 2400 Reactor at 90% power,1030 MW's.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-327 UNIT One DATE 1-2-81 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 MONTH December DAY AVERAGE DAILY POWER LEVEL DAY
. AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1021 17 598 2
692 18 759 3
905.
19 850 4
76 20 810 5
839 21 835 6
253 22 544 7
0 23 959 8
0 24 858 9
o 25 966 10 0
26 988 11 0
27 1039 12 0
28 918 l
13 0
29 1027 14 0
30 1027 15 352 31 994 16 458 i
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in l
the reporting month. Compute to the nearest whole megawatt.
1 (9/77) l
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OPERATING DATA REPORT DOCKET NO.
50-327 DATE 1-2'81 COMPLETED BY David Duoree TELEPHONE (615) 842-0295 OPERATING STATUS 1.
Unit Name:
Sequoyah One Notes 2.
Reporting Period:
necamber 1980 3.
Licensed Thermal Power (MWt):
3411 4.
Nameplate Rating (Gross MWe):
1220.58 5.
Design Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity (Gross MWe):
1183 7.
Maximum Dependable Capacity (New MWe):
1148 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted, If Any (New MWe):
10.
Reasons For Restrictions, If Any:
This Month Yr-to-Date Cumulative 11.
Hours in Reporting Period 744 7,345 7,345 12.
Number of Hours Reactor Was Critical 522.5 1,538.6 1,538.6 0
o o
13.
Reactor Reserve Shutdown Hours sn6.9 843.99 843.99 14.
Hours Generator On-Line 15.
Unit Reserve Shutdown Hours 0
0 0
16.
Gross Thermal Energy Generated (MWH) 1.7n4.770 1.679.n1n 1 A79.nto 17.
Gross Electrical Energy Generated (MWH)
~ 447,821
'557,321
~ 557,321 l
18.
Net Electrical Energy Generated (MWH) 426.516 518.840 518.840 19.
Unit Service Factor mn un up 20.
Unit Availability Factor NR NR NR 21.
Unit Capacity Factor (Using MDC Net)
NR NR NR 22.
Unit Capacity Factor (Using DER Net)
NR NR NR 23.
Unit Forced Outage Rate NR NR NR 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 7-04-80 7-05-80 INITIAL ELECTRICITY 8-21-80 7-22-80 l
COMMERCIAL OPERATION 1-18-81 i
(9/77) I
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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET No.
50-327 UNIT NAtIE ScauoyalLDan DATE l-2-81 C0tlPLETED BY David Dupree REPORT t!ONTil _pptegAen TELEPIIONE (615) 842-0295 e
S o eo 8 Licensee U
Cause & Corrective e -,,
u No.
Date "o
S0 E
oS$
Event
@ 'l E*o Action to R
US E
.8 U $
Report #
$3 0.3 Prevent Recurrence H
$5 US N
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12-18-80 F
12 Ilr A
Derated for maintenance on the feedwater flow 19 Min system.
2 12-22-80 F
6 Hrs F
Derated for chemistry adjustments.
54 Min s
3 12-23-80 F
2 Hrs A
Derated for maintenance on I-A maih feed 7
34 Min pump turbine.
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3 4
F: Forced Reason:
?!cthod:
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-flanual for Preparation of Data B-Maintenance or Test 2-flanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Admini s t ra tive G-Operational Error (Explain) 5 (9/77)
II-Other (Explain)
Exhibit I-Same Source I
i UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-327 UNIT NAtIE Sequoyah_0ne DATE l-2-81 C0t!PLETED BY David Du REPORT t!ONTli December TELFPHONE (615D42dree 295 mu l
o co 8 Licensee U
Cause & Corrective c^
N No.
Date "b
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Event E*e Action to I
4 R
E
.8 ti y Report #
%1 8,2 Prevent Recurrence I
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k 26 12-2-80 F
A 3
Reactor Trip: The condenser circulating water
- 19 Hrs pump tripped causing a loss of vacuum that 02 Min tripped the turbine and reactor.
i 27 12-3-80 F
A 3
Reactor Trip: Trip was caused by a low level l
in the steam generator #1.
i 28 12-3-80 F
13 lir, H
3 Reactor Trip: Unit tripped due to a high 52 Min generator stator temperature.
29 12-6-80 F
204 lirs H
3 Reactor trip because of improperly installed 11 Min test equipment in the solid state protection g
cabinets.
I
- Combi ne duration for i rips 26 and 2 7.
h 1
2 3
4 l
F: Forced Reason:
tiethod:
Exhibit G-Instructions i
S: Scheduled A-Equipment Failure (Explain) 1-flanua l for Preparation of Data I
B-flaintenance or Test 2-flanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (EER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
{
E-Operator Training & License Examination e
F-Administrative G-Operational Error (Explain) 5 (9/,77)
H-Other (Explain)
Exhibit I-Same Source
1 r-Plant Maintenance Summary The following significant maintenance items were completed during the month l
of December, 1980:
1 1.
Replaced turbocharger and af tercooler on 1A-1 diesel engine.
2.
Replaced defective speed switch and relays 'LA' and 'AS' on lA-A diesel generator.
3.
Modified reactor coolant. pump motor oil level switch. Modifications allows determination of high or low levels from outside containment.
^ ^ - - ' - " - - - - - - -
i Outage Maintenance Summary The following significant maintenance items were completed by Outage Maintenance during the month of December,1980.
1.
Continued work on hanger repair and painting in accordance with IE Bulletin 79-14.
2.
Work continuing on rerouting ERCW pump and fire pump train B power cables.
3.
Completed the replacement of 9 system 30 and 32 solenoid valves.
4.
Work was completed to the addition of interlocks to the 6900V shut-down board breaker automatic close circuit to insure that load shedding has occurred before the emergency feeder breaker is closed.
5.
Completed replacement of 3 existing train A solenoid valves associ-ated with the containment vacuum relief valves.
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i TENNESSEE VALLEY AUTHORIII DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT DECEMBER 1 - DECEMBER 31, 1980 DOCKET NUMBER 50-327 i
LICENSE NUMBER DPR-77 l
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i TABLE OF CONTENTS l
Operations Summary..
1 Significant Operational Events.
2 Average Daily Unit Power Level...................
3 Operating Data Report 4
Unit Shutdown and Power Reduction 5-6 l
t Plant Maintenance Summary 7
i Outage Maintenance Summary..
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Operations Summary December, 1980 The following summary describes the significant operational activities for the month of December.
In support of this summary, a chronological log of significant events is included in this report.
There were fifteen Licensee Event Reports and one Special Report, 80-6, inadvertant injection of Sodium-24 into the turbine building sump.
There were four scrams during December.
Unit 1 continued testing in preparations for full power operation. The reactor was at 75% power producing 900 MW's at the beginning of the month.
On December 6,1980, the reactor scrammed and remained in mode 5 for eight days for oil seal repairs on the RCP's and other general maintenance. The reactor was taken critical on December 14, 1980 and was in mode 1 at 90%
Power producing 1030 MW's at the end of the month, t
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Significant Operational Events Date Time Event 12/01/80 0001 Unit I was in mode 1 at 75% reactor power; 900 MW's.
12/02/80 0752 The reactor tripped due to a turbine trip caused by a loss of vacuum when condenser circulating water pump 1A tripped. A faulty pressure switch caused the back flow gates to close which tripped the condenser circulating water pumps IB and IC.
12/02/80 2224 Reactor critical.
12/02/80 2252 Reactor tripped on #1 S/G low low level ala rm.
12/03/80 0028 Reactor critical.
12/03/80 0515 Reactor tripped because a high generator i
stator temperature caused a turbine trip.
The stator cooling water isolation valve was found isolated.
12/03/80 0937 Reactor critical.
12/06/80 1330 Reactor tripped because test instrumentation was improperly installed.
l 12/07/80 0845 Reactor in mode 5.
12/14/80 2130 Reactor critical.
i l
-'12/29/80 0902 Reactor at 90% power.
l 12/29/80 2100 Unit I cooling tower put in service.
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12/31/80 2400 Reactor at 90% power, 1030 MW's.
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AVERAGE DAILY UNIT ' POWER LEVEL DOCKET NO.
50-327 UNIT s one s
DATE 1-2-81 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 MONTH December DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1021 17 598 2
692 18 759 3
905 19 850 4
76 20 810 5
839 21 835 6
253 22 544 7
0 23 959 8
0 24 858 9
o 25 966 10 0
26
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27 1039 12 0
28 918 13 0
29 1027 14 0
30 1027 15 352 31 994 16 458 INSTRUCTIONS
~
On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) e 1
.. =.
- -~
OPERATING DA?A REPORT DOCKET NO.
50-327 DATE 1-2'81 COMPLETED BY David Dupree TELEPHONE (615) 842-0295 OPERATING STATUS 1.
Unit Name:
Sequovah one Notes 2.
Reporting Period:
nee.mher 1980 3.
Licensed Thermal Power (MWt):
3411 4.
Nameplate Rating (Gross MWe):
1220.58 5.
Design Electrical Rating (Net MWe):
1148 6.
Maximum Dependable Capacity (Gross MWe):
1183 7.
Maximum Dependable Capacity (New MWe):
1148 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9.
Power Level To Which Restricted, If Any (New MWe):
10.
Reasons For Restrictions, If Any:
This Month Yr-to-Date Cumulative 11.
Hours in Reporting Period 744 7,345 7,345 12.
Number of Hours Reactor Was Critical 522.5 1,538.6 1,538.6 13.
Reactor Reserve Shutdown Hours 0
0 0
14.
Hours Generator On-Line
~
506.9 843.99 843.99 15.
Unit Reserve Shutdown Hours 0
0 0
16.
Gross Thermal Energy Generated (MWH)
_j.2na.770 1.679.n1n 1 A79. nan 17.
Gross Electrical Energy Generated (MWH)
~ 447,821
~557,321
~ 557,321 18.
Net Electrical Energy Generated (MWH) 426.516 518.840 518.840 19.
Unit Service Factor Nn Nn NR 20.
Unit Availability Factor NR NR NR 21.
Unit Capacity Factor (Using MDC Net)
NR NR NR 22.
Unit Capacity Factor (Using DER Net)
NR NR NR 23.
Unit Forced Outage Rate NR NR NR 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.
If Shut Down At End Of Report Period, Estimated Date of Startup:
26.
Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY 7-04-80 05-80 INITIAL ELECTRICITY 8-21-80 7-22-80 COMMERCIAL OPERATION 1-18-81 (9/77)-.
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9 UNIT SIIUTDOWNS AND PDWER REDUCTIONS DOCKET NO.
50-327 UNIT NAt!E Senuoyah onn DATE l-2-81 COMPLETED BY David Dupree REPORT ?!ONTil Jgermbet TELEPil0NE (615) 842-0295 1
'o ao 3 Licensee Cause & Corrective em a
No.
Date S0 E
ojy Event Oiu E*e Action to R
E
.8 0 g Report #
M]
8,~8 Prevent Recurrence 05 e
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1 12-18-80 F
12 IIr A
Derated for maintenance on the feedwater flow 19 Min system.
2 12-22-80 F
6 Ilts F
nerated for chemistry adjustments.
54 Min d
3 12-23-80 F
2 11rs A
Derated for maintenance on I-A ma?h feed i
34 Min pump turbine, i
i 1
2 3
4 F: Forced Reason:
Me t hc,d :
Exhibit G-Instructions S: Scheduled A-Equipment Failure (Ex, plain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (I.ER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Adminis t ra tive G-Operational Error (Explain) 5 (9/77)
H-Other (Explain)
Exhibit I-Same Source l
t
I ti UNIT SilDTDOWNS AND P0bT.R REDUCTIONS DOCKET NO.
50-327 UNIT NAME Seguayah_Dnn DATE l-2-81 COMPLETED BY David Du REPORT t!ONTII December TELEPIIONE (615FBE2:pree 0295 I
m I.
ke o ao 8 Licensee U
Cause & Corrective cm n
No.
Date SC
.o 3 %
Event E*e Action to 1
R y@
g j ij j Report #
%3 8,3 Prevent Recurrence H
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o 26 12-2-80 F
A 3
Reactor Trip: The condenser circulating water M 9 Hrs pump tripped causing a Irss of vacuum that 02 Min tripped the turbine and reactor.
27 12-3-80 F
A 3
Reactor Trip: Trip was caused by a low level in'the steam generator #1.
., I Tj 28 12-3-80 F
13 Hr, H
3 Reactor Trip: Unit tripped due to a high S2 Min generator stator temperature.
29 12-6-80 F
204 Hrs 11 3
Reactor trip because of improperly installed 11 Min test equipment in the solid state protection cabinets.
i (Combi ne duration for i rips 26 and 2 7.
i 1
2 3
4 i
F: Forced Reason:
tiethod:
Exhibit G-Instructions f
S: Scheduled A-Equipment Failure (Explain) 1-Hanual for Preparation of Data B-tfaintenance or Test 2-tfanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161) 4 E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) 5 (9/,77)
II-Other (Explain)
Exhibit I-Same Source 1,
t-Plant Maintenance Summary The following significant maintenance items were completed during the month J
of December,1980:
1.
Replaced turbocharger and aftercooler on 1A-1 diesel engine.
2.
Replaced defective speed switch and relays 'LA' and 'AS' on IA-A diesel generator.
3.
Modified reactor coolant pump motor oil level switch. Modifications allows determination of high or low levels from outside containment.
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Outage Maintenance Summary The following significant maintenance items were completed by Outage Maintenance during the month of December, 1980.
1.
Continued work on hanger repair and painting in accordance with IE Bulletin 79-14.
t 2.
Work continuing on rerouting ERCW pump and fire pump train B power cables.
3.
Completed the replacement of 9 system 30 and 32 solenoid valves.
4.
Work wa:: completed to the addition of interlocks to the 6900V shut-down board breaker automatic close circuit to insure that load shedding has occurred before the emergency feeder breaker is closed.
5.
Comnleted replacement of 3 existing train A solenoid valves associ-ated with the containment vacuum relief valves.
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