ML20086L298
ML20086L298 | |
Person / Time | |
---|---|
Site: | Sequoyah ![]() |
Issue date: | 06/30/1995 |
From: | Hollomon T, Shell R TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
NUDOCS 9507210139 | |
Download: ML20086L298 (11) | |
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~ RA tenressee vaney Aumory 1101 Market Street Chattanooga. Tennessee 37402 July 14, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - JUNE 1995 MONTHLY OPERATING REPORT Enclowed is the June 1995 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.
If you have any questions cone-rning this matter, please call J. W. Proffitt at (615) 843-665 .
Sincerely, R. H. Shell Manager SQN Site Licensing Enclosure cc: See page 2 1
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9507210139 950630 PDR R
ADDCK 05000327 PDR
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U.S. Nuclear Regulatory Commission Page 2 July 14, 1995 cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission l
One White Flint, North 11555 Rockville Pike I
Rockville, Maryland 20852-2739 Mr. Joseph Santucci, Manager Advanced Reactor Department ,
I Electric Power Research Institute l 3340 Hillview Avenue Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 i
Regional Administrator l
l U.S. Nuclear Regulatory Commission j Region II 101 Marietta Street, NW, suite 2900 Atlanta, Georgia 30323 'f711 l
Mr. F. Yost, Director Research Services
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l Util 4y Data Institute j 1200 G Street, NW, Suite 250 l Washington, D.C. 20005 l
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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PIANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION JUNE 1995 UNIT 1 ,
DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 a ,
UNIT 2 DOCKET NUMBER 50-328 ;
LICENSE NUMBER DPR-79
. OPERATf0NAL
SUMMARY
JUNE 1995 UNIT 1 Unit 1 generated 701,510 megawatthour? (MWh) (gross) electrical power during June with a capacity factor of 84.65 percent.
At 0327 Eastern daylight time (EDT) on June 23, a reactor trip occurred as a result of a lo-lo level on a steam generator. During the process of establishing a clearance for a maintenance activity on a radiation monitor, an auxiliary unit operator (AUO) opened the wrong breaker. This resulted in a loss of power to Reactor Protection Set 1. The loss of power to the protection set caused a reduction in feedwater flow, resulting in decreasing levels in the steam generators and a subsequent reactor trip. Unit I was taken critical on June 24 at 0600 EDT and was tied online at 1329 EDT that same day.
At 1308 EDT on June 29, with Unit 1 operating at 98 percent reactor power, a power decrease was initiated as a result of problems with the 1B main feedwater pump. Reactor power was reduced to approximately 65 percent to allow the pump to be removed from service for repairs. At 1945 EDT, after receiving frequent alarms on quadrant power tilt ratio, further power reduction was initiated to 48 percent reactor power.
Unit I was operating at 48 percent at the end of June.
UNIT 2 Unit 2 generated 771,830 megawatthours (MWh) (gross) electrical power during June with a capacity factor of 93.5 percent. Unit 2 was offline because of a turbine trip / reactor trip that occurred on May 31. Unit 2 returned to operation on June 2 at 0722 EDT.
Unit 2 was operating at 99.5 percent reactor power at the end of June.
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AVERAGE DAILY UNIT POWER LEVEL 1
P DOCKET NO. 50-327 UNIT No. One DATE: 07-05-95 COMPLETED BY T. J. Hollomon TELEPHONE: (615) 843-7528
' MONTH: JUNE 1995 i
l AVERAGE' DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL ,
DAX (MWe-Net) 281 (MWe-Net) ,
1 1137 17 1094 2 1138 18 1035 ,
3 1137 19 1118 4
4 1135 20 1124 5 1129 21 1127 i I
6 1128 22 1127 ;
7 1131 23 133 ;
-8 1115 24 56 l 9 1128 25 416' ,
1 10 1129 26 495 11 1129 27 519 T
- 12 1127 28 826 ,
t
'13 1065 29 891 14 1036 30 499 15' 1028 31 N/A
, 16 1012 l t
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AVERACE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT No. Two DATE: 07-05-95 COMPLETED BY: T. J. Ho11omon TELEPHONE: f615) 843-7528 MONTH: JUNE 1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL Dal (MWe-Net) phl (MWe-Net) 1 -37 17 1047 2 193 18 1082 3 922 19 1105 4 1109 20 1106 5 1117 21 1100 _
6 1115 22 1107 ,
7 1113 23 1107 8 1115 24 1108 9 1117 25 1109 a
10 1114 26 1109 11 1115 27 1109 12 1109 28 1104 13 1104 29 1100 14 1109 30 1103 15 1108 31 N/A 16 1109
OPERATING DATA REPORT DOCKET NO. 50-327 DAT i7/05/95 COMPLETED E J. Ho1 1omon TELEPHONL 015) 843-7528 OPERATING STATUS l Notes l
- 1. Unit Name: Seouovah Unit One l l
- 2. Reporting Period: June 1995 l l
- 3. Licensed Thermal Power (MWt): 3411.0 l l
- 4. Nameplate Rating (Gross IWe): 1220.6 l l
- 5. Design Electrical Rating (Net MWe): 1148.0 l l
- 6. Maximum Dependable Capacity (Gross NWe): 1151.0 l l
- 7. Maximum Dependable Capacity (Net HWe): 1111.0 l l
- 8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Not MWe): N/A
- 10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 _,,,,
3.623 121.992
- 12. Number of Hours Reactor Was Critical 693.5 3.426.6 65.476
- 13. Reactor Reserve Shutdown Hours 0 0 0
- 14. Hours Generator On-Line 686.0 3.412.2 64.016.5
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (PMi) 2.063.579.5 11.417.331.1 208.993.328
- 17. Gross Electrical Energy Generated (MWH) 701.510 3.970.360 71.021.244
- 18. Net Electrical Energy Generated (MWH) 675.044 3.837.001 68.100.414
- 19. Unit Service Factor 95.3 94.2 52.5
- 20. Unit Availability Factor 95.3 94.2 52.5
- 21. Unit Capacity Factor (Using MDC Net) 84.4 95.3 50.2
- 22. Unit Capacity Factor (Using DER Net) 81.7 92.3 48.6
- 23. Unit Forced Outage Rate 4.7 6.7 35.5
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Unit 1 Cvele 7 refuelina outaae is scheduled to becin September 9.1995, with a duration of 50 days.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
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+ OPERATING DATA REPORT DOCKET NO. 50-328 DATE 07/05/95 COMPLETED BY T . J . Holl omon TELEPHONE (615) 843-7528 OPERATING STATUS l Notes l
- 1. Unit Name: Seavovah Unit Two l l
- 2. Reporting Period: June 1995 l l
- 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. Maximum Dependable Capacity (Gross MWe): 1146.0 l l
- 7. Maximum Dependable Capacity (Net Mde): 1106.0 l I
- 8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
- 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 3.623 113.952
- 12. Number of Hours Reactar Was Critical 697.8 3.147.9 67.504
- 13. Reactor Reserve Shutdown Hours 0- 0 0
- 14. Hours Generator On-Line 688.6 3.042.5 65.752.2
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 2.276.770.1 10.024.569.1 207.552.032'
- 17. Gross Electrical Energy Generated (MWH) 771.830 3.442.573 70.450.182
- 18. Net Electrical Energy Generated (MWH) 744.334 '3.311.841 67.426.023
- 19. Unit Service Factor 95.6 84.0' 57.7
- 20. Unit Availability Factor 95.6 ___
84.0 57.7
- 21. Unit Capacity Factor (Using MDC Net) 93.q___ 82.7, 53.5
- 22. Unit Capacity Factor (Using DER Net) 90.1 __ 79.f2_ 51.5
'23.' Unit Forced Outage Rate 4.4 __ 16 1, 34.4
- 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:
DCCRET NO: 50-327
- UNIT SKUTDOWNS AND POW M REDtCTIONS UNIT NAME: One DA7E: 07/07/95 - '
REPORT MONTH: June 1995 COMPLETED BY:T. J. Hollomon TELEPHONE:(615) 843-7528 . .
Method of Licensee Cause and Corrective -
Durati on Shutting Down Event Systgm Compgnent Action to No. Date Type (Hours) Reason Reactor Report No. Code Code Prevent Recurrence 2 950623 F 34.0 G 3 50-327/ EF BKR At 0327 EDT on June 23, a reactor 95008 trip occurred as a result of a lo-lo level on a steam generator.
During the process of establishing a clearance for a maintenance i activity on a radiation monitor, j
- an AUO opened the wrong breaker. l This resulted in a loss of power i l
i to Reactor Protectior. Set 1. The l loss of power to the protection set caused a reduction in feedwater flow, resulting in decreasing i levels in the steam generators and ;
a subsequent reactor trip.
l Corrective action for this event i includes the appropriate discip-linary action.
3 950629 F A 5 N/A N/A N/A At 1308 EDT on June 29, with Unit 1 operating at 98 percent reactor power, a power decrease was initiated as a result of problems with the 18 main feedwater pump.
Reactor power was reduced to approximately 65 percent to allow the pump to be removed from service for repairs. At 1945 EDT. after receiving frequent alarms on quadrant power tilt ratio (QPTR),
further power reduction was init-iated to 48 percent reactor power.
The QPTR alarms were caused from 2 Reason: 3 4 I:F Forced 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 D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other 5
G-Operational Error (Explain) Exhibit I-Same Source H-Other (Explain) l l
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DOCKET NO:' 50-327"
- UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT.NAME: -One -f 07/07/95-
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DATE: ~
REPORT MONTH: June 1995 COMPLETED BY:T. J. Hollomon_-
TELEPHONE:f615) 843-7528 . .
Method of Licensee Cause and Corrective *
' Duration Shutting Down Event System Compgnent Action to No. Date Type l (Hours) Reason 2
Reactor3 Report No. Code 4
Code Prevent. Recurrence
- 3. .950629 F A 5 N/A N/A N/A (continued) shif ts in the core flux and non-uniform Nuclear Instrumentation System (NIS) response resulting.
from the reduction in power. The' unit was stabilized, a fluu map was perfonned, and the NIS channels were recalibrated..
2 Reason: 3 4 I:F Forced 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 D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain) 5 Exhibit I-Same Source H-Other (Explain)
q DOCKET NO: 50-328 UNIV SHUTDOWNS AND PCWER REDUCTIONS UNIT NAME: Two .
DATE: 07/07/95 -
REPORT MONTH: June 1995 COMPLETED BY:T. J. Ho' lemon TELEPHONE:(615) 843-7528 .
Method of Licensee Cause and Corrective
- Duration Shutting Down Event Systp Comognent Action to No. Date Type (Hours) Reason Reactor Report No. Code Code Prevent Recurrence 6 950601 F 31.4 N/A 4 50-328/ TJ TS Unit 2 was offitne because of a 95003 turbine trip / reactor trip that occurred on May 31. Unit 2 returned to operation on June 2 at 0722 EDT.
2 Reason: 3 Method: 4 I:F Forced 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 Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain) 5 Exhibit I-Same Source H4ther (Explain)
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