ML19343B232
ML19343B232 | |
Person / Time | |
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Site: | Sequoyah |
Issue date: | 12/03/1980 |
From: | Dupree D TENNESSEE VALLEY AUTHORITY |
To: | |
Shared Package | |
ML19343B231 | List: |
References | |
NUDOCS 8012160333 | |
Download: ML19343B232 (14) | |
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER
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SEQUOYAH NUCLEAR PLANT
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MONTHLY OPERATING REPORT NOVEMBER I - NOVEMBER 31, 1980 DOCKET NUMBER 50-327 LICENSE NL?fBER DPR-77 t
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Submitted By: ~ Aa t hi till-Plantpanager i,
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1 TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Significant Operational Events . . . . . . . . . . . . . . . . . . . . . 2-6 Average Daily Unit Power Level . . . . . . . . . . . . . . . . . . . . . 7 Operating Data Report . . . . ...,... . . . . . . . . . . . . . . . 8
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l Unit Shutdown and Power Reduction ... , , . . . . . . . . . . . . . . 9-10
- 1 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . 11 Outage Maintenance Summary . . . . . . . . . . . . . . . . . . . . . . . 12
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1 Operations Summary November, 1980 The following summary describes the significant operational activities for the month of November. In support of this summary, a chronological log of significant events is included in this report.
There were nineteen Licensee Event Reports and no Special Reports.
There were eleven reactor trips during November.
November 1, Unit I was at 30% power, producing 280 megawatts. The reactor was placed in mode 45 twice during the scath for maintenance.
A power operated relief valve opened during a reactor trip on November 29.
Reactor ausber oce reached 751 (860 segawatts) and was at this power level at the end of the month.
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Significant Operational Events.
Date Time Event 11/04/80 0358 Turbine load raised from 4%~to 29.7% per SU-8.1.
0540 Dropped turbine and Rx power 5% at 1%/ min per SU-8.1.
0620 Raised power fra 22.7 to 32.7 at 1%/ min.
0728 Started load reduction.
0740 Turbine stopped at 22.7%.
0807 Turbine set up on a 51/ sin increase.
0810 Start turbine increase to 27.7%.
1100 Turbine test completed (SU-8.1).
-11/05/80- 1202 Started a 10*. load reduction free 33% at 200*./ min.
1203 Test complete at 23%.
226 Turbine load increase from 23% at 2007/
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1227 Test cceplete.
1255 Turbine powr reduced to 29% at 1%/etc.
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1525 Rm at W.. tartime lead at 2R KC W.
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Significant Operational Events 2
(Continued)
Date Time Event 11/10/80 1358 -Start pulling shutdown banks.
1417 All S/D-rods full out.
1744 Mode #3.
2200 Heat up 435'F.
11/11/80 0600 RCS 546.8'F.
0853 All S/D banks rod withdrawn.
0843 Pulling control banks.
l 0856 Rx critical
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) 0951 Rx at 5%.
4 1100 Rolling main turbine.
1423 Rx trip.
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1512 Closed Rx trip breakers.
1639 Start pulling S/D banks.
2000 All shutdown rods fully withdrawn.
2001 Start pulling control rods.
2022 Rx critical.
11/12/80 0333 Rx trip.
1704 Began pulling shutdown banks.
1720 Banks fully withdrawn.
2200 Mode #3 544*F.
11/13/80 0124 Ex critical.
11/14/80 0036 Rx trip.
0253 S/D banks withdrawn.
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t Significant Operational Events (Continued)
Date Time Event 1025 Started cooldova of RCS.
1400 RCS at 577'F.
i 1532 Mode #4.
11/15/80 0029 Inserting shutdown rods.
0053 Rods in.
0503 Mode #5.
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11/16/80 0600 Mode #5.
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1700 Began heating up to Mode #4.
t 1746 Mode #4.
2116 Began pulling shutdown banks.
2131 Banks withdrawn.
2323 Mode #3.
11/17/80 1130 All shutdown rods out.
1148 Start pulling control rods.
1201 RA critical.
2200 Rx at 50%/525 MWE.
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11/20/80 1628 Start pulling S/D bank A.
11/21/80 0258 Stopped MFPT "A". H.P. valves still open.
Pump could not be controlled. The valve was swinging from 0% to 50%.
0615 Mode #2.
0935 Mode #1.
1105 Rx trip HiHi S/G 1evel.
I 1234 Began pulling S/D banks.
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Significant Operational Events (Continued)
Date Time Event
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1253 Shutdown bank withdrawn fully.
1303 Began pulling control bank A.
1319 Rx critical.
11/22/80 0801 Rx trip, Hi flux trip.
, 0846 Began pulling shutdown banks.
0901 Bank A,B,C,D fully withdrawn.
0912 Began pulling control banks.
1416 Began pulling shutdown rods.
1431 Banks A,B,C,D fully withdrawn. ,
1501 Rx critical.
2248 Rx trip, rate trip.
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11/23/80 0100 Pulling S/D rods.
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0123 Shutdown rods out.
- 0128 Start pulling control rods.
0138 Reset main turbine.
0149 Rx critical, Tavg 549.
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0329 Generator tied on line.
i 0522 Rx trip at 30%.
0707 Began pulling S/D rods.
0722 Banks A,B,C,D fully withdrawn.
0810 Began pulling control banks.
1235 Rx trip (test and blackout) 1241 SIS actuated, Hi steam flow.
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Significant Operational Events
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Date Time Event 1400 Mode #3.
11/24/80 0610 Tavg 547'; S/D banks in; RCS pressure 2235.
1646 Start pulling shutdown banks.
2235 Started cooldown.
11/25/80 0330 Mode #4.
11/27/80 1400 Mode #4, heating up. ,
2735 Heat up stopped, repair annunciator on S/G level.
2139 Restarted heat-up.
2205 Mode #3.
11/28/80 6121 Pulling S/D rods.
0141 S/D rods fully out.
1143 Start pulling control rods.
1200 Rx critical.
1428 Turbine tied to grid.
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11/29/80 1212 Out on AI due to turbine load, load dropped to 65%.
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1236 Rx at 70%; 800 mw.
1257 AI back in limits; 46 minute penalty.
1300 Rx at 75%; 860 MW; 569*F.
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AVERAGE DAILY UNIT POWER LEVEL
DOCKET NO. 50-327 UNIT one DATE 12-3-80 __
I COMPLETED BY David Dunree
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MONTH November DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 16905 17 '3325 2 4741 18 12412
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4 6580 20 7528
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l 5 4805 21 4716 6 0 22 981 7 0 23 2 8 0 24 0
.9 0 25 0 10- 0 26 0 11 0 27 0 12 490 28 2569 13 6033 29 891 14 170 30 1608 15 0 31 N/A 16 0 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) 7
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OPERATING DATA REPORT i
DOCKET NO. 50-327 DATE 12-4-80 COMPLETED BY David Dupree TELEPHONE (615) 842-0295
OPERATING STATUS
- 1. Unit Name: Sequoyah one Notes
- 2. Reporting Period
- , November. 1980 j 3. Licensed Thermal Power (MWt): 3411
- 4. Nameplate Rating (Gross MWe): 1220.5
- 5. Design Electrical Rating (Net MWe): 1148
- 6. Maximum Dependable Capacity (Gross MWe): 1185
- 7. Maximum Dependable Capacity (New MWe): 114g
- 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):
l 10. Reasons For Restrictions, If Any:
i This Month Yr-to-Date Cumulative
- 11. Hobrs in Reporting Period 720 6601 6601
- 12. Number of Hours Reactor Was Critical 330.517 1016.1 1016.1
- 13. Reactor Reserve Shutdown Hours 0 0 0 1 14. Hours Generator On-Line 330.78 337.09 337.09
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) J104,781.3 8.591.11 467.260.4 467.260.4
- 17. Gross Electrical Energy Generated (MWH) 109,500.3 109,500.3
- 18. Net Electrical Energy Generated (MWH) 92.324.10 92.324.10 92.324.10
- 19. Unit Service Factor M/A M/A M/A
- 20. Unit Availability Factor N/A N/A N/A
- 21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A
- 22. Unit Capacity Factor (Using DER Net) N/A N/A N/A
- 23. Unit Forced Outage Rate N/A N/A N/A
- 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 7-05-80 INITIAL ELECTRICITY -
8-21-80 7-22-80 COMMERCIAL OPERATION 12-30-86 (9/77) 8
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 1
UNIT NAME Seouoyah One
- DATE 12-4-80 l COMPLETED BY navid Dunree REPORT MON'lli November TELEPHONE (615) 842-0295
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Q e ,, m oa3 Licensee U Cause & Corrective No. Date 't jl $ @ v fi % Event $ 't $"k Action to
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Prevent Recurrence
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P 15 11-5-80 F 136 Hrs H 3 An injection pressure surge on main feedwater 56 Min system caused reactor trip.
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16- 11-11-80 F 7 lirs A 3 Vital inverter voltage spikes caused indicated i low level in #2 S/G causing reactor trip.
g, 17 11-12-80 F 22 Hrs A 3 Main turbine generator back-up relay system -
51 Mir problem caused reactor trip. .
18 11-14-80 F 84 lirs A 3 Reactor trip caused by containment spray systen 7 Mir being inoperable. 4 19 11-20-80 F 12 Hrs A 3 Low level in S/G #3 caused reactor trip. !
45 Mir
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20 11-21-80 F 18 Hrs A.H 3 Swinging of MFPT controls caused High S/G 40 Mir level resulting in a reactor trip.
21 11-22-80 F 1 lir H 3 Instrumentation personnel installing test 24 Mir equipment in the NIS cabinets caused reactor trip.
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1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data
, B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee
- C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG- '
D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative G-Operational Error (Explain) 5 (9/77) H-Other (Explain) Exhibit I-Same Source l
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UNIT SHUTDOWNS AND POWER REDUCTIONS DCCKET NO. 50-327 UNIT NAME g .
DATE 8 COMPLETED BY David Dupree REPORT MONT!! November TELEPHONE (615) 842-0295
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1 em a o ao S Licensee 5 Cause & Corrective I No. Date % 3$ @ .a 3 g Event $1 $$ Action to yy y jgj Report # %3 3 Prevent Recurrence j
$5 $ US N o"
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l 22 11-22-80 F 6 Hrs H 3 Instrumentation personnel installing test 20 Min equipment in the NIS cabinets caused reactor trip.
- 23 11-22-80 F 4 Hrs H 3 A planned negative rate trip per startup test o 12 Min SU-9.5 caused two rods to drop and the trip.
24 11-23-80 F 5 Hrs 11 3 Trip caused by startup test SU-1.2A to verify the reactor can be shutdown outside the Control room.
25 11-23-80 F 119 Hrs H 3 Reactor tripped caused by startup test SU-1.lA 54 Min to prove reactor can be shutdown normally without offsite power (blackout).
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i 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee i C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination
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G-Operational Error-(Explain) 5 l (9/77) H-Other (Explain) Exhibit I-Same Source 4
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Plant Maintenance Summary The following significant maintenance items were completed during the month of November, 1980:
- 1. Repairs were made to the IC main condensor tubes which were damaged when the cap blew off of the end of the stea:n dump header during steam dump operation. (This was due to water hammer).
- 2. The main feed pump turbine condensor flexible joint between the condensor and the turbine was found to be leaking air in. The joint was tightened and air-leakage to the main condensor was reduced significantly.
- 3. The Unit i vital inverters were tested and various problems corrected including voltage spikes caused by a faulty sync. signal. This faulty signal caused the vital inverter 2-III to trip initiating a safety injection.
- 4. Centrifugal charging pump 2B-B was disassembled, inspected for damage and repairs initiated.
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Outage Maintenance Summary i.
Continued to work on pipe hangers en safety related systems in accordance with IE Bulletin 79-14.
Work continued on the installation of high density storage racks in the spent fuel pit.
Continue to repair containment isolation valves on Unit 2 that failed the TVA-2C preoperational leak rate test.
Modification began on the waste disposal system which would allow for opera-tion of a portable demineralizer system.
4 Work began on the replacement of the Unit 2 vital inverters.
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