ML20035E854
| ML20035E854 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/31/1993 |
| From: | Fenech R, Hollomon T TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9304190329 | |
| Download: ML20035E854 (10) | |
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Tennessee Valley Authouty. Post Offce Box 2000. S:>ccy-Daisy. Tennessee 37379 2000 Robert A. Fenech Vce Prescent. Seavoya5 Nuclear Plan April 14, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 SEQUOYAH NUCLEAR PIANT (SQN) - MARCH 1993 MONTHLY OPERATING REPORT Enclosed is the March 1993 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.
If you have any questions concerning this matter, please call M. A. Cooper at (615) 843-8924.
Sincerely,
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>A Robert A. Fenech j
Enclosure cc: See page 2 i
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1 9304190329.930331
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DR:. ADOCK O 7
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U.S. Nuclear Regulatory Commission l
Page 2 April 14, 1993
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cc (Enclosure):
INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339-3064 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission I
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412 i
Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 Regional Administrator U.S. Nuclear Regulatory Commission Region II l
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-0199 Mr. F. Yost, Director Research Services
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Utility Data Institute 1700 K Street, NW, Suite 400 Washington, D.C. 20006-3800 l
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TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP j
SEQUOYAH NUCLEAR PIANT l
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MONTHLY OPERATING REPORT TU THE NUCLEAR REGUIATORY CGWIISSI(BI l
MAR _Cp 1993 UNIT 1-i DOCKET NIMBER 50-327 i
i LICENSE NIMBER DPR-77 t
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UNIT 2 DOCKET NUMBER 50-328
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LICENSE NUMBER DPR-79 l
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OPERATIONAL
SUMMARY
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MARCH 1993 UNIT 1 Unit 1 generated 32,680 megawatthours (MWh) (gross) electrical power during March with a capacity factor of 3.78 percent.
On March 2 at 0016 Eastern standard time (EST), Unit I was shut down to evaluate the piping condition, following an extraction steam pipe rupture event on Unit 2.
Unit I was removed from the grid at 0718 EST that day. A decision was subsequently made to take the reactor to Mode 5 and begin preparations for the scheduled Unit 1 l
refueling outage. Unit 1 entered Mode 5 on March 15 at 2036 EST and remained in the forced outage through the end of March.
UNIT 2 Unit 2 generated 15,702 MWh (gross) electrical power du:ing March with a capacity factor of 1.82 percent.
On March 1 at 1423 EST, the Unit 2 reactor was manually tripped as a result of an overvoltage condition induced from the
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effects of a rupture of the extraction steam pipe on the cubicle of the l
generator voltage regulator. As a result of the high voltage on the system and the inability to reduce the voltage, the reactor was manually tripped when the generator voltage increased to approximately 27 kilovolts. Unit 2 remained in the forced outage through the end of March to support ongoing piping evaluations and repairs / replacements.
EDWER-OPERATED RELIEF VALEE_(10RVs) AND SAFETY VALVES
SUMMARY
There were no challenges to PORVs or safety valves in March.
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l AVERAGE DAILY UNIT POWER LEVEL i
i DOCKET NO.
50-327 UNIT No.
One DATE:
04-01-93 l
l COMPLETED BY:
T. J. Hollomon TELEPHONE:
(615) 843-7528 MONTH: MARCH 1993 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DM (tMe-Ne t )
DAY (MWe-Nat) 1 1
1136 17
-16 2
151 18
-19 3
-28 19
-19 4
-23 20
-19 5
-26 21
-19 6
-26 22
-14 7
-26 23
-12 8
.26 24
-14 9
-26 25
-12 10
-23 26
-12 11
-26 27
-14 12
-21 28
-12 13
-23 29
-12 14
-23 30
-9 15
-23 31
-14 16
-21 i
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AVERACE DAILY UNIT POWER LEVEL i
DOCKET NO.
50-328 UNIT No.
Two DATE:
04-01-93 COMPLETED BY:
T. J. Hollomon TELEPHONE:
(615) 843-7528 MONTH: F11RCH 1993 l
AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Nat)
DAX
(!$ie-Net )
1 627 17
-7 2
-16 18
-9 3
-9 19
-9 4
-9 20
-12 5
-9 21
-9 6
-9 22
-7 7
-9 23
-9 8
-12 24
-5 9
-16 25
-7 10
-14 26
-7 11
-9 27
-7 1
1 12
-9 23
-7 13
-9 29
-7 14
-7 30
-5 15
-9 31
-7 i
16
-7 l
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l OPERATING DATA REPORT i
DOCKET NO. _50-327 DATE E(Q!}Z93 3
COMPLETED BY
- 1. J. Holloman _
TELEPHONE (615) 843-7528
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OPERATING STATUS l Notes l
1.
Unit Name:
Segunyah Unit One l
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2.
Reporting Period:
March 1993 l
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3.
Licensed Thermal Power (MWt); 3411.0 l
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4.
Nameplate Rating (Gross HWe): 1220.6 l
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5.
Design Electrical Rating (Net tiWe): 1148.0 l
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Maximum Dependable Capacity (Gross MWe): 1162.0 l
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7.
Maximum Dependable Capacity (Net 14We): 1122.0 l
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If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
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Power Level To Which Restricted. If Any (Net MWe):
N/A
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- 10. Reasons For Restrictions, If Any:
N/A l
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This Month Yr-to-Date Cumulative l
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- 11. Hours in Reporting Period 744 2.160 103.009
- 12. Number of Hours Reactor Was Critical 31.4 1.281.3 56.029 l
- 13. Reactor Reserve Shutdown Hours 0
0 0
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- 14. Hours Generator On-Line 31.3 1.220.6 54.828.5
- 15. Unit Reserve Shutdown Hours 0.0 0
0
- 16. Gross Thermal Energy Generated (MWH) 97.366.3 3.915.909.5 178.893.754 I
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- 17. Gross Electrical Energy Generated (HWH) 32.680 1.358.540 60.702.654
- 18. Net Electrical Energy Generated (MWH) 17.441 1.290.507
.58.212.729 t
- 19. Unit Service Factor 4.2 56.5 53.2 l
- 20. Unit Availability Factor 4.2 56.5 53.2 l
- 21. Unit Capacity Factor (Using HDC Net) 2.1 53.2 50.4 i
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- 22. Unit Capacity Factor (Using DER Net) 2.0 52.0 49.2
- 23. Unit Forced Outage Rate 95.8 43.5 38.6
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- 24. Shutdowns Scheduled Over Next 6 Honths (Type Date, and Duration of Each):
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- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
Jul y 1. 1993 l
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OPERATING DATA REPORT DOCKET NO.
.50-328 DATE 04/08/93 COMPLETED BY T. J. Hollomon TELEPHONE (6151 843-7528 OPERATING STATUS l Notes l
j 1.
Unit Name:
Seouoyah Unit Two l
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Reporting Period: _ March 1993 l
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3.
Licensed Thermal Power (MWt): 3411.0 l
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Nameplate Rating (Gross MWe): _1220.6 l
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Design Electrical Rating (Net MWe): 1148.0 l
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Maximum Dependable Capacity (Gross MWe): 1162.0 l
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Maximum Dependable Capacity (Net HWe): _J1Z2.0 I
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If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report. Give Reasons:
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Power Level To Which Restricted. If Any (Net MWe):
N/A
- 10. Reasons for Restrictions, If Any:
N/A l
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I This Month Yr-to-Date Cumulative l
- 11. Hours in Reporting Period 744 2.160 94.969
- 12. Number of Hours Reactor Was Critical 14.4 1.291.9 57.505
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 14.4 1.158.2 56.235.6
- 15. Unit Reserve Shutdown Hours 0.0 0
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- 16. Gross Thermal Energy Generated (MWH) 48.363.2 3.773.305.1 176.955.084
- 17. Gross Electrical Energy Generated (MWH) 15.702 1.283.783 60.006.902
- 18. Net Electrical Energy Generated (MWH) 8.484 1.226.045 57.441.320
- 19. Unit Service Factor 1.9 53.6 59.2
- 20. Unit Availability Factor 1.9 53.6 59.2
- 21. Unit Capacity Factor (Using MDC Net) 1.0 S0.6 53.9
- 22. Unit Capacity Factor (Using DER Net) 1.0 49.4 52.7
- 23. Unit Forced Outage Rate 98.1 46.4 33.5
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
June 15. 1993 l
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DOCKET NO:
N1-P7 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
One l
DATE:
04/05/9L._.
REPORT MONTH:. MARCH 1993 COMPLETED BY:T. J, Hqllgmpa TELEPHONE:(615) 843-7528 Method of Licensee Cause and Corrective Duration Shutting Down Event System Component Action to l
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No.
Date Type (Hours)
Reason Reactor Report No.
Code Code Prevent Recurrence 3
930302 F
712.7 B
1 On March 2 at 0016 Eastern standard time (EST), Unit I was shut down to evaluate the piping condition, following an extraction steam pipe rupture event on Unit 2.
The cause of this event was a programmatic failure of the erosion / corrosion (E/C) program, resulting from insufficient management oversight and review of the program.
Corrective actions include E/C program review and engineering evaluation of other piping suscept-ible to erosion, including inspect-ions and repairs / replacements and review of other site technical programs. Unit i entered Mode 5 on March 15 at 2036 EST to begin preparations for the scheduled refueling outage and remained in the forced outage through the end of the month.
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I: Forced Reason:
Method:
Exhibit G-Instructions F
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-Sare Source H-Other (Explain) i l
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_. -, - - - - -, - - _,, -..,, -.. ~. -.,. _
a DOCKET NO:
50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
Two DATE:
04/05/93 REPORT MONTH:J ECH 1993 COP!PLETED BY:T. J. Hollomon
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TELEPHONE:(615) 843-7523 Method of Licensee Cause and Corrective Action to Duration Shutting Down Event System Compgnent I
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d No.
Date Type (Hours)
Reason Reactor Report No.
Code Code Prevent Recurrence 3
930301 F
729.6 A
2 328/93001 TL EXC On March 1 at 1423 Eastern standard time (EST), the Unit 2 reactor was manually tripped as a result of an overvoltage condition induced from the effects of the rupture of an extraction steam pipe on the cubi-cle of the generator voltage regu-lator. Operators manually tripped the unit when generator voltage increased to approximately 27 kilo-volts. Th cause of this event was a programmatic failure of the erosion / corrosion (E/C) program, resulting f rom insuf ficient manage-ment oversight and review of the program. Corrective actions include the repair of af fected piping and components; E/C program review and engineering evaluation of other piping susceptible to erosion, including inspections and repairs / replacements; evaluation of the impact of the overvoltage condition on plant equipment; and review of other site technical programs. Unit 2 remained in the forced outage through the end of March.
2 d
I: Forced Reason:
Method:
Exhibit G-Instructions F
5: Scheduled A-Equiprent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee 1
C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restrection 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)
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