ML20043A181
| ML20043A181 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/30/1990 |
| From: | Hollomon T, Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9005180168 | |
| Download: ML20043A181 (9) | |
Text
1 TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 5N-157B Lookout Place MAY 151990 U.S. Nuclear Regulatory Commission i
ATTN: Document Control Desk Washington, D.C. -20555 i
Gentlemen:
'In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
'50-328 SEQUOYAH NUCLEAR PLANT (SQN) - APRIL 1990 MONTHLY OPERATING REPORT Enclosed is the April 1990 Monthly Operating Report as required by SQN Technical Specification-6.9.1.10.
If you have any questions concerning this matter, please call R'. R. Thompson-T at (615) 843-7470.
I Very truly yours, TENNESSEE VALLEY AUTHORITY j
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G. Wallace, Manager Nuclear Licensing and Regulatory Affairs.
-i Enclosure i
cc (Enclosure):
INP0 Records Center Regional Administration Institute of Nuclear Power Operations U.S. Nuclear Regulatory Commission j
1100 Circle 75 Parkway, Suite 1500 Office of Inspection and Enforcement Atlanta, Georgia 30389 Region II 101 Marietta Street, NW, Suite 2900 Mr. B. D. Liaw, Director-Atlanta, Georgia 30323 TVA Projects Division-One White Flint, North Mr. B. A. Wilson, Assistant Director-11555 Rockville Pike for Inspection Programs i
Rockville, Maryland 20852 TVA Projects Division U.S. Nuclear Regulatory Commission Mr. Ted Marston, Director Region-II' s
Electric Power Research Institute 101 Marietta Street, NW, Suite 2900 P.O. Box 10412 Atlanta, Georgia 0323 Palo Alto,.Callfornia 94304 8
NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 l
900518016e 900430
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PDR ADOCK 05000327 L'
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SEQUOYAH NUCLEAR PLANT j
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/ MONTHLY OPERATING.' REPORT-'
TO THE' S
NUCLEAR-REGULATORY. COMMISSION i
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APRIL 1990 j
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't 4 UNIT 1 DOCKET NUMBER 50-327'
. LICENSE NUMBER DPR-77
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4-UNIT 2.
DOCKET NUMBER 50-328 ~
LICENSE NUMBER'DPR "
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OPERATIONAL
SUMMARY
APRIL 1990-UNIT-1 Unit 1 entered its Cycle _4 refueling outage on March 17, 1990.
The outage continued.throughout the month of April, with Unit 1 in Mode 6 at the beginning of the month.- On' April'2, 1990, Unit-1 entered an undefined
- mode when all fuel had been removed from the core.
Fuel reloading began on April 17, 1990, and the unit entered Mode 6 at l'17 (EDT). Unit 1 entered 0
Mode'5 on April 27, 1990, at 0620 (EDT), and remained in Mode 5 through the end of April.
UNIT 2 Unit 2 generated 769,810 MWh (gross) electrical power during April, with a capacity factor of 90.5 percent. Unit 2 reactor power level was reduced t'o 95 percent on April _8, 1990, for maintenance on FW Heater 28-1, and was returned to 100 percent reactor power level on April'9,1990.
Unit 2 also experienced an unplanned' reactor scram from 100 percent power level on April 10, 1990, at 0134 (EDT), when-steps of 51-90.82, " Reactor Trip Instrumentation Monthly Functional Test (SSPS) - Unit 2," were-performed out of sequence.
The unit tied online on April 11, 1990, at 1612 (EDT), and was again at 100 percent reactor power-level on April 13, 1990, at 1551 (EDT).
l POWER-0PERATED~ RELIEF VALVES (PORVs) AND-SAFETY VALVES
SUMMARY
l There were no challenges to PORVs or safety-valves.in the month of April.
OFFSITE DOSE CALCULATION MANUAL (00CM) CHANGES There were no changes to the ODCM during the month of April.
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t AVERAGE DAILY UNIT POWER LEVEL DOCKEi NO.
50-327' UNIT One DATE 05-01-90 COMPLETED BY T. J. Ho11omon TELEPHONE (615) 843-7528 r
r MONTH APRIL 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 2
17 2
2 2
18 2
3 2
.19 2
4
- 2 20
- 2 5
1 21 2
6 2
22 1
7 2
23 2
8 2
24 2
9
- 2 25 2
i 10
- 16 26 2-F 11
- 18 27 2
12
- 2 28 2
i 13
- 3 29-2 14
- 1 30
-2 15
- 2 31 N/A
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i 16
- 2 1
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AVERAGE DAILY UNIT POWER LEVEL I
DOCKET NO.
50-328 Unit' Two DATE' 05-01-90
-COMPLETED BY T. J. Ho11omon i
TELEPHONE (615) 843-7528 t
MONTH APRIL 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1132 17 1133 2
1135 18 1132 f
3 1135 19 1132' 4
1135 20 1131 5
1134 21 1132 i
6 1134 22 1135 7
1133 23'
-1134 8
1084 24 1135 9
1093 25 1134 10 57 26 1136 11 39 27 1133 12 437
-28 1133 13 1082 29 1132 14 1126 30 1131 I
15 1132 31 N/A 16 1133 i
OPERATING DATA REPORT
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DOCKET NO.
50-327 DATE Hav 1. 1990 COMPLETED BY T. J. Hollomon TELEPHONE (6151 843-7528 OPERATING STATUS Notes
.1.
Unit Name:
Seouovah Unit One 2.
Reporting Period:
April 1990 3.
Licensed Thermal Power (HWt): 3411.0 4.
Nameplate Rating (Gross HWe): 1220.6 5.
Design Electrical Rating (Net HWe): 1148.0
- 6. 'Haximum Dependable Capacity (Gross HWe): 1183.0 7.
Maximum Dependable Capacity (Net HWe): 1148.0 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level To Which Restricted, If Any (Net HWe):
N/A
- 10. Reasons For Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 719 2.879 77.424
- 12. Number of Hours Reactor Was Critical 0
1.803.2 35.299
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 0
1.803.0
-34.492.4
- 15. Unit Reserve Shutdown Hours 0-0 0
- 16. Gross Thermal Energy Generated (HWH) 0 5.839.530.2 112.175.410
- 17. Gross Electrical Energy Generated (HWH)
.0 2.026.980 38.050.736
- 18. Net Electrical. Energy Generated (HWH)
-2.769 1.957.400 36.429.429
- 19. Unit Service Factor 0.0 62.6 44.6
- 20. Unit Availability Factor 0.0 62.6 44.6
- 21.. Unit Capacity Factor (Using HDC Net) 0.0 -
59.2 41.0
' 22. Unit Capacity Factor (Using DER Net)
' 0.0 59.2 41.0
- 23. Unit Forced Outage Rate ~
0.0 -
0.0 48.0
- 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:
Hav 22. 1990
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OPERATING DATA REPORT DOCKET N0, _S0-328 DATE.Elv 1. 1990 COMPLETED BY. T. 3. Hollomon TELEPHONE (615) 843-7528 OPERATING STATUS Notes 1.'
Unit Name:
Seouovah Unit Two 2.
Reporting Period:
April 1990 3.
Licensed Thermal Power (MWt): 341).O 4.
Nameplate Rating (Cross MWe): 1220.6 5.
Design Electrical Rating (Net MWe): 1148.0 6.
Maximem Dependable Capacity (Gross MWe): 1183.0 7.
Maxiaum Dependable Capacity (Net MWe): 1148.0
' 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Rep >rt Give Reasons:
N/A 9.
Power Level To Which Restricted. If Any (Net MWe):
N/A
- 10. Reasons-For Restrictions. If Any:
N/A' This Month Yr-to-Da te Cumulative
- 11. Hours in Reporting Period 719 2.879 69.384
- 12. Nurnber of Hours Reactor Was Critical 691.9 2.851.9 36.382
- 13. Reactor Reserve Shutdown Hours 0
0 0
- 14. Hours Generator On-Line 680.4 2.840.4 35.536.2
- 15. Unit Reserve' Shutdown Hours '
O.0 0-0
- 16. Gross Thermal Energy Generated (MWH)
_Z.242.120.8 9.390.304.5 109.800.564
- 17. Gross Electrical' Energy Generated (MWH) 769.810-3.233.630 37.254.426 -
- 18. Net Electrical Energy Generated (MWH) 742.585 3.121.273 35.569.607
- 19. Unit Service Factor 94.6 98.7 51.2
- 20. Unit Availability Factor 94.6 98.7 51.2
- 21. Unit Capacity Factor (Using MDC Net) 90.0 94.4 44.7
- 22. Unit Capacity Factor (Using DER Net) 90.0 94.4 44.7
- 23. Unit Forced Outage Rate s.4 1.3 43.0
- 24. Shutdowns Scheduled Over Next 6 Nonths (Type. Date, and Duration of Each):
Unit 2 Cvele 4 refuelino outaae is scheduled for September 1990 with a duration of 70 davs.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
N/A
- - - = - - -
DOCKET NO:
50-327-
- 3.. 2 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT.NAME:
- One DATE:
05/08/90 REPORT MONTH: Acril 1990 COMPLETED BY:T. J. Hollomon.
. TELEPHONE:16151 843-7528
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Method of Licensee Cause and Corrective Duration Shutting Down Event'
. System Component Action to No.
Date-Type' (Hours)
Reason' Reactor Report No.
Code
- Code
' Prevent Recurrence:
3 2
900317..
S-1076.02 C
-1 Unit.1 Cycle 4 refueling outage continues.
'5 : Forced Reason-
'Methodi.
- Exhibit'G-Instructions-2 F
S: Scheduled
- A-Equipment Failure (Explain) 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 -
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D-Regulatory Restruction...
4-Continuation of Existing Outage
'(NUREG-061):
' E-Operator-Training and License Examination -
5-Reduction F-Administrative.
'9-Other-Exhibit I-Same'Sosrce
'5 G-Operational Error -(Explain)
H-Other (Explain)'-
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DOCKET NO:
50-328 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
Two DATE:
05/08/90 A
REPORT HONTH: Aoril 1990 COMPLETED BY:T. -J. Holloecn
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. TELEPHONE:I6151 843-7528.
e si Method of Licensee Cause and Corrective Duration Shutting'Down Event System Component Action to No.
Date Type' (Hours)
Reason
- Reactor Report No.
Code' Code' Prevent Recurrence-.
3
'4/8/90 F
B 5
Power levet was reduced to 95 percent on 4/8/90 at 0339 (EDT).. for maintenance on FW Heater 2B-1.
Unit 2 was again at 100 percent power on 4/9/90 at 1920 (EDT).
4 4/10/90.
F 38.6 B-3 2-90008 Unit 2 tripped at 0134 (EDT), on 4/10/90, when steps of SI-90.82,
" Reactor Trip Instrumen-tation Monthly functional Test (SSPS)
- Unit 2." were performed out of-sequence. The unit
' tied online on 4/11/90 at 1612 (EDT), and was again at.iOO percent reactor power level on 4/13/90 at 1551 (EDT).
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'F: Forced Reason:
Hethod:
- 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 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continuation of Existing Outage (NUREG-061)
D-Regulatory Restruction E-Operator Training and License Examination 5-Reduction F-Administrative
'9-Other G-Operational Error (Explain)
' Exhibit I-Same Source H-Other (Explain)
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