ML20059P069
| ML20059P069 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/30/1990 |
| From: | Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9010250102 | |
| Download: ML20059P069 (10) | |
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o, m.. TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place Chattanooga, Tennessee 37402-2R01 l
October 15, 1990 .
U.S. Nuclear Regulatory Commission ATTN Document Control Desk Washington, D.C. 20555 Centlement In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - SEPTEMBER 1990 MONTHLY OPERATING REPORT Enclosed is the September 1990 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.
If you have any questions concerning thiv matter, please call M. A. Cooper at (615) 843-6422.
Very truly yours.
TENNESSEE VALLEY AUTHORITY DL f
kNE.G.Wallace, Manager f Nuclear Licensing and Regulatory Affairs Enclosure cc (Enclosure):
Mr. J. N. Donohew, Project Manager NRC Resident Inspector U.S. Nuclear Regulatory Commission Sequoyah Nuclear Plant One White Flint, North 2600 Igou Ferry Road 11555 Rockville Pike Soddy-Daisy. Tennessee 37379 Rockville, Maryland 20852 Regional Administration INPO Records Center U.S. Nuclear Regulatory Commission Institute of Nuclear Power Operations Office of Inspection and Enforcement 1100 circle 75 Parkway Suite 1500 Region II Atlanta, Georgia 30389 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Ted Marston, Director Electric Power Research Institute Mr. B. A. Wilson, Project Chief P.O. Box 10412 U.S. Nuclear Regulatory Commission Palo Alto, California 94304 Region II 101 Marietta Street, NW, 'ulte 2900
-Atlanta, Georgia 30323
, ont nw.m ne con 930 DR ADOCK 0500 {g'/ An Equal Opportunith EmpI yer T[Q%
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l MONTHLY OPERATING REPORT
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- , NUCLEAR REGULATORY C0!W SSION ts SEPTEMBER 1990 L, ...
UNIT 1-I OC0KET NUMBER $0-327 LICENSE NUMBER DPR-77 L- UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 jo
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OPERATIONAL S M l SEPIEEER1990 WII 1 Unit 1 generated 651,220 megawatthours (MW h ) (gross) electrical power during September, with a capacity factor of 76.46 percent. Unit 1 began the month .
still operating under instructions to maintain the one-hour megawatt (thermal)
(MW t ) limit of 3397 because of possible downspiking on the P-250 plant computer U1118. Reactor Thermal Output. This restriction was removed on September 2, 1990, and Unit I was returned to 100 percent reactor power level.
On September 13, 1990, at 1500 Eastern daylight time (EDT), a reactor power level decrease was initiated to reduce the power level to approximately 98 percent because of No. 3 heater drain tank problems. On September 14,
'1990, Unit 1 experienced a reactor trip from 98 percent level as a result of a steam generator (S/G) low-low level signal on S/G Loop 2. The unit entered Mode 3. The reactor trip was attributed to the failure of Vital Inverter 1-II that had been removed from service earlier in the day to replace Output Voltmeter SQN-1-EI-250-QN2-E.
Unit 1 entered Mode 2 on September 16, 1990, at 0552 EDT, and entered Mode 1 at 1830 EDT. With the unit holding at approximately 14 percent reactor power level and turbine tests being performed, Unit 1 turbine tripped at 2235 EDT.
The unh remained in Mode 18 the turbine was resett and Unit 1 tied online at ;
1852 EDT on September 17, 1990. l Unit l's second reactor trip for the month occurred at 0357 EDT on September 19, 1990, from approximately 62 percent power level. Unit 1 again ,
entered Mode 3. The Unit 1 turbine tripped as a result of a main transformar differential (sudden pressure) relay operation. The reactor trip occurred because of the turbine trip. A special task force was established to investigate the transformer probleui; It was determined that the Unit 1 turbine generator trip resulted from the corroded and shorted terminals on the ,
spare (Phase A) main transformer's gas relay.
Unit 1 entered Mode 2 on September 19, 1990, at 2113 EDT, and entered Mode 1 on September 20, 1990, at 1136 EDT. Unit 1 tied online on September 20, 1990,-
at 1446 EDT, and was operating at 100 percent reactor power level at 1900 EDT on September 21, 1990.
Unit I was operating at 100 percent reactor power level at the end of September. ,
0 PERIL 0NAL SIM M SEPIEMBER1990 i
UNII2 Unit 2 generated 128,000 MWh (gross) electrical power during September, with a'capecity factor of 15.03 percent. Unit 2 began the month at 70 percent reactor power level and continuing coastdown to Unit 2 Cycle 4 (U2C4) refueling outage.
The U204 refueling outage began on September 8, 1990, at 0259 EDT, when the e turbine was manually taken offline. Unit 2 entered Mode 6 on September 17, i 1990, at 0836 EDT, and fuel movement began on September 21, 1990, at .i 0930 EDT. On September 23,1990, at 1700, all fuel had been removed f rom the '
core. Unit 2 entered "no mode " and U204 outage work continues.
POWER-OPERATED RELIEF VALVES (PORVs) AND SAFETY VALVES
SUMMARY
There were no challenges to PORVs or safety valves in the month of September.
OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES There were no changes to the ODCM during the month of September. l i
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pl t AVERAGE DAILY. UNIT POWER LEVEL 4
. DOCKET NO., 50-327 UNIT No. One DATE: 10-03-90 C COMPLETED BY: T. J. Ho11omon TELEPHONE: (615) 843-7528-
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MONTH: SEPTEMBER 1990 I AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net)
.I' 1093 17 24 2 1097 18 314 3 1096 19 95 c
4 1094 20 63 5: , '1095 21 716 6 ~1090 22 1097 7 1097 23 1105-8 4 1097 24 1106
-9 1097 25 1108 10 1098 26 1110 11 __; '1103 27 1113 12 1104' 28 1112 13- 1098 29 1116 14 732 30 1112 15 0* 31 16 -0*:
- P250 information not available when unit is offline..
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. u AVERAGE' DAILY UNIT POWER LEVEL.
!W DOCKET NO. 50-328 UNIT No. Two DATz 10-03-90
, COMPLETED BY: T. J. Hollomon. TELEPHONE: (615) 843-7528 MONTH: SEPTEMBER 1990 1
AVERACE DAILY POWER LEVEL AVF. AGE DAILY POWER LEVEL DAY (MWe-Net) DAY -(MWe-Net)
, l' 758 17 0 2 752 18 0' 3 743 19 0
-4 733 20 0 5 726 21 0 6 713 22 0-7 680 23 0 8 24 24 -0 9 0* 25 0 10 0 26 0-
- 11 0 27 0 l
12 0 28 0 13 0 29 0
. 14 0' 30 0 15' 0 _ _ ,
31 i
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- Unit 2 is offline for Cycle-4 refueling outage.
P250 information is not available.
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. OCfDAfihG DATA RfPORT {
DOCKET NO. 50-327 DATE Oct. 1. 1990 COMPLETED BY T. 3. Mn11 nann l TELEPHONE (615) 843-752B QEERATING STATUS j l Notes l
- l. Unit Name: _ inauovah Unit One l l
- 2. Reporting Period: batomber 1990 l l
- 3. Licensed Thermal Powe r (MWt): 3411.0 l l
- 4. ' Nameplate Rating (Grass MWe): 1220.6 l l
- 5. Design Electrical Pating (Net MWe): 1148.0 l l
- 6. Maximum Dependabit, Capacity (Gross MWe): 1183.0 l l
- 7. Maximum Dependable Capacity (Net MWe)t 1148.0 l l
- 8. If Changes Occur. in Capacity Ratings (Items Number 3 Through 7) $1nce last Report. Give Reasons: !
N/A i
- 9. Power Level To Which Restricted. If Any (Net MWe): N/A
- 10. Reasons For Restrictions. If Any: N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 6.551 81.096
- 12. N6ber of Hours Reactor Was Critical 665.0B 4.676.g. 38.172 ?
- 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Hours Generator On-Line 610.5 4.521_.6 37.211.0
- 15. Unit Reserve Shutdown Hours 0.0 0 0 -i
- 16. Gross Thermal Energy Generated (MWH) 1.964.941.4 14.637.743.7 120.973.663 '
- 17. Gross Electrical Energy Generated (MWH) 651.220 4.946.290- 40.970.046 ,
- 18. Net Electrical Energy Generated (MWH) f2L3QQ 4.762.20B__ 39.234.237 !
i 19. Unit Service Factor 84.8 69.0_ 45.9 L 20. Unit Availability Factor 84.8 69.0 45.9
? 21. Unit Capacity Factor (Using MDC Net) 75.3 63.3 42.1
- 22. Unit Capacity factor (Using DER Net) 75.3 63.3 42.1
- 23. Unit ' Forced Outage Rate 15.2 1.9 46.3
- 24. Shutdowns f cheduled Over Next 6 Months (Type. Date, and Duration of Each): ,
- 25. If $ hut Down At Ei.d Of Report Period. Estimated Date of Startup: ML t
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. OPIRATING DATA #FPORT ,
DOCKET NO. 50-328
- DATE cet. 3. 1990
- ' COMPLETED BY T. 1. Hollomon ;
TELEPHONE (615) 843-7528 .
6 OPERATING STATUS l Notes l 1
- 1. Unit Name: Senuovah Unit Two l l l
- 2. Reportina Period: Sentember 1990 l l s
- 3. Licensed Thermal Power (MWt): .3411.0 l l ,
- 4. Nameplate Rating (Gross MWe): 1220.6 l l ,
- 5. Design Electrical Rating (Net MWe): 1148.0 l l
- 6. _ Maximue Dependable Capacity (Gross MWe): 1183.0 l l
- 7. Maximum Dependable Capacity (Net MWe): 114B.0 _
l l
- 8. If Changes Occur in Capacity Ratings (! tees Number 3 Throsgh 7) Since Last Report Give Reasons:
N/A t
- 9. Power Level To Which Restricted, If Any (Net MWe): N/A '!
- 10. Reasons for Restrictions, If Any: N/A
{
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 6.551 73.056
- 12. Number of Hours Reactor Was Critical 171.1 5.975.0 39.505 .
- 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Hours Generator On-Line 171.0 5.963.4 38.659.2
- 15. Unit Reserve Shutdown Hours 0.0 0 0
- 16. Gross Thermal Energy Generated (MWH) 397.459.2 19.268.794.2 119.679.054
- 17. Gross Electrical Energy Generated (MWH) 128.000 6.588.500 40.609.296 18 ' Net Electrical Energy Generated (MWH) 119.388 6.340.818 . 38.781J52
- 19. Unit Service Factor 23.7 91.0 52.9
- 20. Unit Availability Factor 23.7 91.0 52.9 .,
21, Unit Capacity Factor (Using MDC Net) 14.4 84.3 46.3 f 22.' Unit Capacity factor (Using DER Net) 14.4 84.3 46.3
23. Unit Forced Outage Rate 0.0- 0.6 40.9- *
- 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: unvember 9. 1990 4
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DOCKET NO: 50-327 LMIT SHUTDOWNS AND POWER REDUCTIONS tmIT NAME: Doe .__ ~. ,
DATE: 10/03/90 -
REPORT MONTH: Seetember 1990 COMFtETED BY:i._.!. Hallmang TELEFHONE:16151 843-7528 ,,
Method of Licensee Cause and Corrective Duration Shutting Down Event Systy Compgnent Action to Type l Reason 2 Reactor3 No. Date (Hours) Report No. Code Code Prevent Recurrence 8 900913 A 5 At 1500 (EDT), initiated load decrease to approximately 98 percent because of No. 3 HDT problems.
9 900914 F- 74.65' A 3 At 1613 (EDI), with Unit I operating at 96 percent reactor power level, the reactor tripped as a result of a S/G 1o -low level signal on 5/G toop 2.
Unit I entered Mode 3. The reactor trip was attributed to the failure of Vital Inverter II when it was returned to service after maintenance. Unit I tied online at 1852 (EDT) on 9/17/90.
10 900919- F 34.8Z A 3 At 0357 (EDT), while Unit I reactor power level was being increased and the unit was recovering from 9/14/90 trip, the unit experienced another turbine trip / reactor trip from approximately 62 percent power.
Unit I entered Mode 3. The turbine trip was a result of a main transformer differential (sudden pressure) relay operation. 7'ne reactor trip followed the turbine trip. The transformer problem is being investigated. Unit I tied online again at 1446 (EDT) on 9/20/90, and was at 100 percent reactor power level at 1900 (EDT) on Semtember 21. 1990.
I F: Forced 2 p,,,,n 3Method: 4 Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for t.icensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Outage (NURE W I)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Emplain) SExhibit I-Same Source ti-Other (Emplain)
DOCKET NO: 50-328 .
- LMIT SHtJTDOWS AND POWER REDUCTIONS IMIT NAME: Two -
DATE: 10/03/90 REPORT MONTH: September 1990 COPFLETED BY:I. J. HolTamon
- TELEPHONE:(615) 843-15 N Method of Licensee Cause and Corrective Duration shutting Down Event Systp gde nent Action to No. Date Type I (Hours) Reason 2 Reactor 3 Report No. Code Co Prevent Recurrence 5 900908 5 549.02 C 1 Unit 2 Cycle 4 refueling outage began. Unit 2 was taken offline at 0259 (EDT), entered Mode 2 at 0301 (EDT),
entered Mode 3 at and entered 0306(EDT)ITIO(EDT).
Mode 4 at Unit 2 entered Mode 5 on 9/9/90 at 0743 (EDT),
and entered Mode 6 at 0836 (EDT) on 9/17/90.
Fuel movement began at 0930 (EDT) on 9/2I/90.
All the fuel was removed from the core as of 1700 (EDT) on 9/23/90, and Unit 2 entered
- no mode."
I:F Forced 2 geason: 3 Method: 4 Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for P ration of Data B-Maintenance or Test 2-Manual Scram Entry s is for Licensee C-Refueling 3-Autonutic Scram Event Report (LER) File D-Regulatory Restruction A-Continuation of Existing Outage (NtREG-061)
E-Operator Training and License Examination 5-Reduction F-Adninistrative 9-Other G-Operational Error (Explain) 5 Exhibit I-Sane Source H-Other (Explain) 1194K-8
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