ML20197K116

Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With

ML20197K116
Person / Time
Site:	Sequoyah
Issue date:	11/30/1998
From:	Holloman T, Salas P TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9812160088
Download: ML20197K116 (10)

Text

a > ... v

.e .

Tennessee Vaney Authority Post Othce Box 2000. Soddy Daisy. Tennesrae 37379 December 10, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 l

Gentlemen: i l

In the Matter of ) Docket Nos. 50-327 l Tennessee Valley Authority ) 50-328  !

l SEQUOYAH NUCLEAR PLANT (SQN) - NOVEMBER MONTHLY OPERATING l REPORT l The enclosure provides the November Monthly Operating Report as required by SON Technical Specifications Section 6.9.1.10.

If you have any questions concerning this matter, please call me at (423) 843-7170 or J. D. Smith at (423) 843-6672.

Sincerel ,,

/

fW \

ro o sing and Industry Affairs Manager Enclosure g cc: See page 2 q D

/

, 9812160008 981130 m PDR 4 R ADOCK 05000327[a PDR

U.S.,Nu, clear Regulatory Commission Page 2

• December 10, 1998 JDS:JWP:PMB cc (Enclosure):

Mr. R. W. Hernan, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5947 Ms. Barbara Lewis, Assistant Editor, Database McGraw-Hill, Inc.

1200 G Street, NW, Suite 1100 Washington, D.C. 20005 Mr. James Lang, Manager Advanced Reactor Department Electric Power Research Institute 3340 Hillview Avenue Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator l U.S. Nuclear Regulatory Commission l Region II Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-3415 l

i 1

I

. __ _ _ _. . . . _ . . . _ _ - . _ . . _ _ . . _ _ . _ _ . _ _ _ . . . . _ . _ . . _ . _ _ . _ . ~ . . _ . _ . _ _ _ _ _ . _ _ . . _ _ - _ . -

1 i

ENCLOSURE 1

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN) l' MONTHLY OPERATING REPORT

NOVEMBER 1998 i.

UNIT 1 3

DOCKET NUMBER 50-327 s

! LICENSE NUMBER DPR-77 i

UNIT 2

^

DOCKET' NUMBER 50-328 i

LICENSE NUMBER DPR-79 i

4 1

,. .. l OPERATIONAL

SUMMARY

NOVEMBER 1998 I. SEQUOYAH OPERATIONAL

SUMMARY

)

UNIT 1 ,

i Unit 1 generated 789,533 megawatthours (MWh) (gross) electrical power during November with a capacity factor of i 94.45 percent. On November 9, 1998, at 1139 Eastern standard time (EST), with Unit 1 operating at 100 percent power, the failure of Vital Inverter 1-IV resulted in the loss of 120-Volt alternating current (VAC) Vital Instrument Power Board 1-IV. The instrumentation loss resulted in a reactor trip because Channel II of power l range instrumentation was out of service for testing. The l inverter was repaired and Unit 1 was tied online on ,

November 11 at 0454 EST and returned to 100 percent power. I Unit 1 was operating at 100 percent power at the end of i November.

UNIT 2 j Unit 2 generated 849,733 MWh (gross) electrical power i during November with a capacity factor of 102.09 percent.  ;

Unit 2 was operating at 100 percent at the end of November.

II. CHALLENGES TO THE PRESSURIZER POWER-OPERATED RELIEF VALVES (PORVs) OR PRESSURIZER SAFETY VALVES On November 9, 1998, when the reactor trip occurred, the failure of Vital Inverter 1-IV resulted in the loss of 120-VAC Vital Instrument Power Board 1-IV. Pressurizer pressure decreased as expected, then increased until a pressurizer power operated relief valve automatically actuated. The increase in pressurizer pressure was primarily the result of the loss of the pressurizer spray capabilities because of the loss of power to 120-VAC Vital Instrument Power Board 1-IV.

E-1

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT NO. ONE DATE: December 8, 1998 COMPLETED BY: Tanya J. Hollomon TELEPHONE: (423) 843-7528 MONTH: NOVEMBER 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net)

1. 1137 17. 1147

2. 1136 18. 1147

4. 1136 19. 1146

4. 1138 20. 929

5. 1139 21. 1032 ,

6, 1142 22. 1151

7. 1140 23. 1153 8, 1143 24. 1151

9. 532 25. 1151

10. 0 26. 1153

11. 596 27. 1153 12 1140 28. 1153

13. 1142 29. 1154

14. 1145 30. 1155

15. 1151 31. NA

16. 1148-E-2 r

I l

,o .- i

. I AVERAGE DAILY UNIT POWER LEVEL  ;

i DCCKET NO. 50-328 UNIT NO. TWO DATE: December 8, 1998 COMPLETED BY: Tanya J. Ho11omon TELEPHONE: (423) 843-7528 l MONTH: NOVEMBER 1998 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net)

1. 1134 17. 1145

2. 1133 18. 1145

3. 1133 19. 1143  !

I

4. 1131 20. 1146 l

5. 1134 21. 1148

6. 1139 22. 1148

7. 1136 23. 1150

8. 1140 24. 1146 i

9. 1139 25. 1148

10. 1140 26. 1149

11. 1138 27. 1149 12 1139 28. 1149  ;

13. _

1139 29. 1150

14. 1141 30. 1152

15. 1148 31. NA

16. 1146 E-3

.. .~

. e, *

. . OPERATING DATA REPORT a

Docket No. 50-327 Date: December 8,1998 Completed By: , T. J. Hollomon Telephone: (423) 843-7528

1. Unit Name: SQN Unit 1

2. Reporting Period: November 1998

3. Licensed Thermal Power (MWt): 3411.0

4. Nameplate Rating (Gross Mwe): 1220.6

5. Design Electrical Rating (Net Mwe): 1148.0

6. Maximum Dependable Capacity (Gross MWe): 1161

7. Maximum Dependable Capacity (Net MWe): 1122 4 .

8. If changes Occur in Capacity Rating (Item Numbers 3 & 7) Since Last Report, Give Reasons: N/A 4

9. Power Level To Which Restricted, If any (net MWe): N_M_

10. Reasons for Restrictions,If any: N/A i-This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720 8,016 15 1 689

12. Number of Hours Reactor was Critical ,690.8 7,277.4 92,133

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On-Line 678.8 7,223.7 90,283.3

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 l 24,141,347.5 295,385,342

16. . Gross Thermal Energy Generated (MWh) _2,277,357.3

17. Gross Electric Energy Generated (MWh) 789,533 8,330,524 100,731,651

18. Net Electrical Energy Generated (MWh) 760,357 8,049,036 96,748,933

- 19. Unit Service Factor 94.3 90.1 59.1

20. Unit Availability Factor 94.3 90.1 59.1

21. Unit Capacity Factor (Using MDC Net) 94.1 89.5 56.5-

22. . Unit Capacity Factor (Using DER Net) 92.0 87.5 55.2

23. Unit Forced Outage Rate 5.7 1.2 28.4

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): This information is no

' longer reauired by NRC.

~ 25. If Shutdown at End of Report Period, Estimate Date of Startup. N/A E-4

.. w .~

, OPERATING DATA REPORT Docket No. 50-328 Date: December 8,1998 Completed By: T. J. Hollomon Telephone: (423) 843-7528

1. ' Unit Name: SQN Unit 2

2. Reporting Period: November 1998

3. Licensed Thermal Power (MWt): 3411.0

4. Nameplate Rating (Gross Mwe): 1220.6

5. Design Electrical Rating (Net Mwe): 1148.0

6. . Maximum Dependable Capacity (Gross MWe): 1156

7. Maximum Dependable Capacity (Net MWe): 1117

= 8. If changes Occur in Capacity Rating (Item Numbers 3 & 7) Since Last Report, 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-Date Cumulative

. I l'. Hours in R.eporting Period 720 8,016 144,649

12. . Number of Hours Reactor was Critical 720.0 7,930.4 95,586

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 __

14. Hours Generator On-Line 720.0 7,913.3 93.587.8

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWh) . 2,454,100.8 26,894,409.9 300,871,747

17. Gross lilectric Energy Generated (MWh) 849,733 9,226,812 102,452,176

18. Net Electrical Energy Generated (MWh) 822,237 8,945,444 98,350,806

19. Unit Service Factor 100.0 98.7 64.7

20. Unit Availability Factor 100.0 98.7 64.7

-21. Unit Capacity Factor (Using MDC Net) 102.2 99.9 60.9

. 22. Unit Capacity Factor (Using DER Net) 99.5 97.2 59.2

23. Unit Forced Outage Rate 0.0 1.3 27.5

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): This information is no longer reauired by NRC.

25. If Shutdown at End of Report Period, Estimate Date of Startup. N/A E-5

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: NOVEMBER 1998 '

DOCKET NO: 50-327 UNIT NAME: SQN-1 DATE: December 9,1998 COMPLETED BY: T. J. Hollomon TELEPHONE: (423) 843-7528-No. Date Type- Duration Reason 2 Method of- Licensee Event - System Component Cause and Corrective Action to -

'- d (Hours)' .y Shutting Report No.' Code Code5 Prevent Recurrence-Down. .

Reactor3 4 981109 F 41.3 A 3 50-327/1998003 EF INVT On November 9,1998, at 1139 EST, failure of Vital Inverter 1-IV resulted in a reactor trip. The root cause of the unit trip was a failure of a vital inverter resulting from a degraded component in the inverter bridge circuit. The inverter bridge circuit was replaced and the vital inverter was returned to service.

i i

2

' F: Force Reason: 3 Method S: Scheduled

• Exhibit G-Instructions for (NUREG A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File - NUREG - 1022 D-Regulatory Restriction 4-Continuation ofExisting E-Operator Training and License Outage Examination 5-Reduction 8 Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain) 11- Other (Explain)

E-6

+.*

UNIT SHUTDOWNS AND POWER REDUCTIONS ,;

REPORT MONTH: NOVEMBER 1998 DOCKET NO: 50-328 UNIT NAME: SQN-2 DATE: December 9,1998 COMPLETED BY: T. J. IIollomon TELEPHONE: (423) 843-7528 -

2 No. Date ; Type Duration Reason Method of Licensee Event _ System Component Cause and Corrective Action to Prevent

Shutting Report No. Code d

Code 5

Recurrence (Hours)I _ .

Down. -.,

3 Reactor There were no outages or power reductions of greater than 20 percent in the average daily power level during November.

l 2 3

' F: Force Reason: Method

• Exhibit G - Instructions for (NUREG S: Scheduled A-Equipment Failure (Explain) 1-Manual Preparation of Data Entry sheets B-Maintenance or Test 2-Manual Scram for Licensee Event Report (LER)

C-Refueling 3-Automatic Scram File - NUREG - 1022 D-Regulatory Restriction 4-Continuation of Existing E-Operator Training and License Outage Examination 5-Reduction s Exhibit I-Same Source F-Administrative 9-Other G-Operational Error (Explain) 11- Other (Explain)

E-7

- _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ - _ _