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) | |
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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 j LICENSE NUMBER DPR-77 i
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Submitted By: ~ % Lu O_ t1_ (u 6
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l TABLE OF CONTENTS
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j Operations Summary . . . . . . . .. . . .. . . . . . . . . . . . . . . .1
} Significant Operational Events . . . . . . . . . . . . . . . .. . . . . .2 4, -
Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . 3 1
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Operating Data Report- . . . . .. . . . . . . . . . . . . . . . .. . . .4 j Unit Shutdown and Power Reduction . . . .. . . . . . . . . . . . . . . . 5-6
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Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . .7 1
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i Outage Maintenance Summary . . . . . . . .. . . . . . . . . . . . . . . .8 i
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Operations Summary December, 1980 i
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.
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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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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 I condenser circulating water pumps IB and i 1C. ;
1 12/02/80 2224 Reactor critical.
l 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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- l 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
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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
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28 918 13 0 29 1027 14 0 30 1027
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31 994
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INSTRUCTIONS -
l On this format, list the average daily unit power level in MWe-Net for each day in
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1 the reporting month. Compute to the nearest whole megawatt.
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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
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744 7,345 7,345
- 11. Hours in Reporting Period 1,538.6
- 12. Number of Hours Reactor Was Critical 522.5 _
1,538.6 0 o o
- 13. Reactor Reserve Shutdown Hours 843.99
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- 14. Hours Generator On-Line sn6.9 843.99 0 0 0
- 15. Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH) 1.7n4.770 1.679.n1n 1 A79.nto
- 16. ~ 557,321 Gross Electrical Energy Generated (MWH) ~ 447,821 '557,321 17.
l 18. Net Electrical Energy Generated (MWH) 426.516 518.840 518.840 un up
- 19. Unit Service Factor mn
- 20. Unit Availability Factor NR NR NR Unit Capacity Factor (Using MDC Net) NR NR NR 21.
Unit Capacity Factor (Using DER Net) NR NR NR 22.
NR NR
- 23. Unit Forced Outage Rate 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:
l Units In Test Status (Prior to Commercial Operation):
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Forecast Achieved INITIAL CRITICALITY 7-04-80 7-05-80 INITIAL ELECTRICITY
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8-21-80 7-22-80 COMMERCIAL OPERATION 1-18-81 l
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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
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e -,, u o eo 8 Licensee U Cause & Corrective No. Date "o S0 E oS$ Event @ 'l E*o Action to R US E .8 U $ Report # $3 0.3 Prevent Recurrence '
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1 12-18-80 F 12 Ilr A Derated for maintenance on the feedwater flow '
19 Min system.
2 12-22-80 F 6 Hrs F Derated for chemistry adjustments.
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54 Min
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s 3 12-23-80 F 2 Hrs A Derated for maintenance on I-A maih feed 7 34 Min pump turbine.
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1 3 4 F: Forced Reason: ?!cthod:
S: Scheduled Exhibit G-Instructions A-Equipment Failure (Explain) 1-flanual for Preparation of Data B-Maintenance or Test 2-flanual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Admini s t ra tive
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G-Operational Error (Explain) 5 ;
(9/77) II-Other (Explain) Exhibit I-Same Source
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i UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 !
UNIT NAtIE Sequoyah_0ne !*
DATE l-2-81 C0t!PLETED BY David Du REPORT t!ONTli December TELFPHONE (615D42dree 295
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c^ N o co 8 Licensee l U Cause & Corrective No. Date "b d0 .o d % Event
@ @% E*e Action to 4
I R %$ E .8 ti y Report # %1 8,2 Prevent Recurrence I H
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26 12-2-80 F k 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. .
27 12-3-80 F i A 3 Reactor Trip: Trip was caused by a low level l in the steam generator #1. '
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28 12-3-80 F 13 lir, H 3 i ,
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
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- Combi ne duration for i rips 26 and 2 7. h
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1 2 3 4 F: Forced Reason: li S: Scheduled A-Equipment Failure (Explain) tiethod: Exhibit G-Instructions 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)
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E-Operator Training & License Examination {
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G-Operational Error (Explain) 5 (9/,77) H-Other (Explain) Exhibit I-Same Source ,
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Plant Maintenance Summary The following significant maintenance items were completed during the month l of December, 1980:
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- 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.
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i Outage Maintenance Summary The following significant maintenance items were completed by Outage Maintenance during the month of December,1980.
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- 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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TENNESSEE VALLEY AUTHORIII
- DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT
MONTHLY OPERATING REPORT DECEMBER 1 - DECEMBER 31, 1980
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DOCKET NUMBER 50-327 i LICENSE NUMBER DPR-77 l
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TABLE OF CONTENTS
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l Operations Summary . . . . . . .... .. . .. .......... . . . 1 Significant Operational Events . . .. . . . . . . .. . . . . . . . . . . 2 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . . 3
. Operating Data Report . . . . ... .. ... .. ......... . . . 4
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l Unit Shutdown and Power Reduction .... ... . ........ . . . . 5-6 t
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Plant Maintenance Summary . . . ..... . .. ......... . . . . 7
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i Outage Maintenance Summary . . ... .. . . ... ... . . . . . . . . . 8 i
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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
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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.
i 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.
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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.
l l 12/31/80 2400 Reactor at 90% power, 1030 MW's.
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l 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
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858 9 o 25 966 10 0 26 ~988 11 o 27 1039 12 0 28 918 13 0 29 1027 14 0 30
__ 1027 15 352 31 994 16 458
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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.
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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:
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- 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
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- 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
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em a 'o ao 3 Licensee % Cause & Corrective No. Date % S0 E ojy Event Oiu E*e Action to R %$ E .8 0 g Report # M] 8,~8 Prevent Recurrence
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05 e %3e & 8" o xmg u o
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 3 12-23-80 F 2 11rs A Derated for maintenance on I-A ma?h feed di 34 Min pump turbine, i
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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
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(9/77) H-Other (Explain) Exhibit I-Same Source l t
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UNIT SilDTDOWNS AND P0bT.R REDUCTIONS DOCKET NO.
i 50-327 UNIT NAME Seguayah_Dnn DATE l-2-81 COMPLETED BY David Du REPORT t!ONTII December TELEPIIONE (615FBE2:pree 0295
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m I ke cm n o ao 8 Licensee I.
U Cause & Corrective '
No. Date ". SC @ .o 3 % Event @% E*e Action to 1 R y@ g j ij j Report # %3 8,3 H Prevent Recurrence M5 a & 8" o
"a{o xm u 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
- 28 12-3-80 F 13 Hr, H 3 Reactor Trip: Unit tripped due to a high Tj S2 Min generator stator temperature.
29 12-6-80 F 204 Hrs 3 11 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:
S: Scheduled A-Equipment Failure (Explain) tiethod: Exhibit G-Instructions f 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-
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D-Regulatory Restriction 4-Other (Explain) 0161)
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E-Operator Training & License Examination 4
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F-Administrative
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G-Operational Error (Explain) 5
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(9/,77) II-Other (Explain) Exhibit I-Same Source 1,
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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
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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.
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- 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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