ML20133K486

Monthly Operating Repts for Dec 1996 for Sequoyah Nuclear Plant Units 1 & 2

ML20133K486
Person / Time
Site:	Sequoyah
Issue date:	12/31/1996
From:	Hollomon T, Shell R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9701210245
Download: ML20133K486 (10)

Text

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nn Tennessee vaney Autwity FY;st 0"ce BaGXA fMdhsy femienee 3GN January 9,1997 I

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 (SON) - DECEMBER 1996 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report as required by SON Technical Specification 6.9.1.10.

If you have any questions concerning this matter, please telephone J. W. Proffitt at (423) 843-6651.

Sincerely, A

R. H. Shell Manager SON Site Licensing and Industry Affairs Enclosure cc: See page 2

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9701210245 961231 PDR ADOCK 05000327 R

PDR

U.S. Nuclear Regulatory Commission Page 2 January 9,1997 cc (Enclosure):

Mr. R. W. Hernan, 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 30339-5957 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 U.S. Nuclear Regulatory Commission Region ll 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 Mr. F. Yost, Director Research Services Utility Data Institute 1200 G Street, NW, Suite 250 Washington, D.C. 20005 i

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TENNESSEE VALLEY AUTIIORITY SEQUOYAII NUCLEAR PLANT MONTIILY OPERATING REPORT TO TIIE NUCLEAR REGULATORY COMMISSION DECEMBER 1996 4

UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 I

1 OPERATIONAL

SUMMARY

DECEMBER 1996 UNIT 1 Unit I generated 882,366 megawatthours (MWh) (gross) electrical power during December with a capacity factor of 102.7 percent. There were no outages or power reductions of greater than 20 percent to report during December. Unit I was operating at 100 percent power at the end of December.

UNIT 2 Unit 2 generated 790,725 megawatthours (MWh) (gross) electrical power during December with a capacity factor of 92.0 percent. On December 6,1996 at 0033 EST, with Unit 2 operating 100 percent reactor power, l

an unplanned automatic trip occurred as a result of a loss of power to Start Bus 2A. When the 2A start bus lost power, a reactor trip signal was initiated as a result of a bus undervoltage condition for Reactor Coolant Pumps 1 and 3. Start Bus 2A lost power because the alternate source feeder breaker opened without a legitimate trip signal and the normal feeder breaker was out of service for maintenance pertaining to Common Station Service Transformer A. All four diesel generators started and 28 diesel generator tied on to supply the 6.9 kV shutdown board. Plant systems and equipment performed as expected. The root cause of the event could not be determined. Investigation into the trip circuitry did not identify any trip signals that should have caused the breaker to open. No equipment failure was identified. A spare breaker was installed into the 2A start bus normal feeder breaker compartment. The breaker was tested and placed in service. Unit 2 was taken critical on December 7 at 1956 EST and was tied online on December 8 at 1457 EST. Unit 2 was again operating at 100 percent reactor power on December 9 at 1513 EST.

Unit 2 was operating at 100 percent reactor power at the end of December.

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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT NO.

One DATE:

01-07-97 COMPLETED BY: T. J. IIollomon TELEPHONE: (423) 843-7528 MONTH: DECEMBER 1996 2

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j AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l

DAY (MWe-Net)

DAY (MWe-Net) l 1

1149 17 1147 2

1149 18 1124 3

1149 19 1147 i

i j

4 1149 20 1149 i

1 5

1151 21 1149

)

i 6

1148 22 1150 7

1147 23 1149 8

1149 24 1149 i

9 1149 25 1149 t

10 1150 26 1149 i

11 1147 27 1151 j

12 1149 28 1147 i

j 13 1147 29 1147 i

i 14 1126 30 1149 15 1149 31 1148 16 1148 i

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AVERAGE DAILY UNIT POWER LEVEL DO' KET NO. 50-328 UNIT NO.

Two DATE:

01-07-97 COMPLETED BY: T. J. Hollomon TELEPHONE: (423) 843-7528 MONTH: DECEMBER 1996 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 1145 17 1143 2

1146 18 1144 3

1146 19 1144 4

1146 20 1143 5

1147 21 1144 6

5 22 1145 7

-23 23 1144 8

42 24 1144 9

881 25 1144 10 1143 26 1145 11 1142 27 1146 12 1144 28 1145 13 1144 29 1144 i

14 1144 30 1145 15 1144 31 1144 16 1144

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OPERATING DATA REPORT l

DOCKET NO. 50 '0 7 DATE 01/07/97 4

COMPLETED BY T. J. Hollomon TELEPHONE (423) 843-7528 j

OPERATING STATUS Notes j

1. Unit Name:

Seauovah Unit One

2. Reporting Period:

December 1996 i

3. Licensed Thermal Power (MWt): 3411.0

4. Nameplate Rating (Gross (MWe): 1220.6

5. Design Electrical Rating (Net MWe): 114R0 3

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6. Maximum Dependable Capacity (Gross MWe): 1155.0 l

7. Maximum Dependable Capacity (Net MWe): 1117.0

8. If Changes Occur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:

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9. Power Level to Which Restricted, If Any (Net MWe):

N/A j

10. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative i1. Hours in Reporting Period 744 8,784 135,913

12. Number of Hours Reactor Was Critical 744.0 8,428.2 77,323

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 744.0 8,345.2 75,571.6

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWh) 2,531,680.8 28,023,571.3 246,354,987

17. Gross Electrical Energy Generated (MWh) 882,366 9,626,795 83,792,140

18. Net Electrical Energy Generated (MWh) 854,072 9,293,491 80,377,638

19. Unit Service Factor 100.0 95.0 55 6

20. Unit Availability Factor 1000 95.0 55.6

21. Unit Capacity Factor (Using MDC Net) 102.8 94.7 52 9

22. Unit Capacity Factor (Using DER Net) 100.0 92.2 51.5

23. Unit Forced Outage Rate 0.0 0.6 32.1

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Unit 1 is scheduled to enter a refueline outane on March 21.1997 with a duration of 50 days.

25. If Shut Down At End of Report Period, Estimated Date of Startup:

N/A

OPERATING DATA REPORT DOCKET NO. 50-328 DATE OI/07/97 COMPLETED BY T. J. Hollomon TELEPHONE (423) 843-7528 OPERATING STATUS Notes

1. Unit Name:

Seouovah Unit Two

2. Reporting Period: December 1996

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): 1155.0

7. Maximum Dependable Capacity (Net MWe): 1117.0

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 744 8,784 127,873

12. Number of Hours Reactor Was Critical 700.6 7,008.4 79,602

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 681.6 6,896.3 77,672.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWh) 2,288,480.3 23,198,057.7 247,739,654

17. Gross Electrical Energy Generated (MWh) 790,725 7,975,285 84,199,057

18. Net Electrical Energy Generated (MWh) 763,344 7,677,850 80,679,719

19. Unit Service Factor 91.6 78.5 60.7

20. Unit Availability Factor 01 6 78.5 60.7

21. Unit Capacity Factor (Using MDC Net) 91.9 78.3 56.5

22. Unit Capacity Factor (Using DER Net) 89.4 76.1 55.0

23. Unit Forced Outage Rate 8.4 8.7 31.3

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:

N/A

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DOCKET NO_: 50-327 UNIT NAME: One UNIT SHUTDOWNS AND POWER REDUCTIONS DATE: 01/07/97 COMPLETED BY:

T. J. Hollomon REPORT MONTH: DECEMBER 19%

TELEPHONE: (423) 843-7528 l

I No.

Date Type' Duration Reason Method of Licensee System Component Cause and Correctise Action to Prevent

[

2 (Hours Shutting Event Report Code Code' Recurrence d

Down No.

Reactor'

{

There were no outages or pourr reductions of greater than 20 percent to report during December e

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'F: Forced Reason:

' Method

' Exhibit G-Instructions 2

i 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 Restriction 4-Continuation of Existing Outage (NUREG-1022)

E-Operator Training and License Exam 5-Reduction F-Administrative 9-Other

' Exhibit I - Same Source G-Operational Error (Explain) t i!Other (Explain) i 1

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DOCKET NO.: 50-323 UNIT NAME: Tun UNIT SHUTDOWNS AND POWER REDUCTIONS DATE: 01/07/97

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COMPLETED BY:

T. J. Hollomon REPORT MONTil: DECEMBER 1996 TELEPHONE: (423) 843-7525 2

No.

Date Type' Duration Reason Method of Licensee System Component Cause and Corrective Action to Prevent (Hours)

Shutting Event Report Code' Code' Recurrence Down No.

l Reactor' 4

% 1206 F

62.4 H

3 50-328/96006 EA BKR On December 6,1996 at 0033 EST, an f

unplanned automatic trip occurred as a l

result of a loss of power to Start Bus 2A.

When the 2A start bus lost power, a reactor trip signal was initiated as a result of a bus l

undervoltage condition for Reactor Coolant Pumps I and 3. Start Bus 2A lost power l

because the alternate source feeder breaker

[

opened without a legitimate trip signal and I

the nornul feeder breaker was out of senice for maintenance pertaining to Common f

Station Senice Transformer A. The root t

cause of the event could not be determined.

i Investigation into the trip circuitry did not l

identify any trip signals that should have caused the breaker to open. No equipment failure was identified. A spare breaker uns installed into the 2A start bus normal feeder breaker companment. The breaker uns l

tested and placed in senice. Unit 2 uns tied online on December 8.

'F: Forced Reason:

' Method

' Exhibit G-Instructions 2

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data f

B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee i

C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-1022)

E-Operator Training and License Exam 5-Reduction 5

F-Administrative 9-Other Exhibit 1 - Same Source G-Operational Error (Explain)

H-Other (Explain) t i

P

.