ML20072D735

Monthly Operating Repts for Jul 1994 for Sequoyah Nuclear Plant Units 1 & 2

ML20072D735
Person / Time
Site:	Sequoyah
Issue date:	07/31/1994
From:	Hollomon T, Shell R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9408190219
Download: ML20072D735 (10)

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le,IrAuee vd f AJAAEcice 52nc sim,.ols(~TAlee 3nm August 15, 1994 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Centlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - JULY 1994 MONTHLY OPERATING REPORT Enclosed is the July 1994 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10.

If you have any questions concerning this matter, please call J. W. Proffitt at (615) 843-6651.

Sincerely, I '

R. H. Shell Manager SQN Site Licensing Enclosure cc: See page 2 100070 9408190219 940731 PDR R

ADOCK 05000327 PDR

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t U.S. Nuclear Regulatory Commission Page 2 August 15, 1994 cc (Enclosure):

INPO Records Center Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LeBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412 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 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

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGUIATORY C0fffISSION JULY 193_4 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NIMBER 50-328 LICENSE NUMBER DPR-79 l

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OPERATIONAL

SUMMARY

JULY 1994 UNIT 1 Unit 1 generated 708,920 megawatthours (MWh) (gross) electrical power during July with a capacity f actor of 82.8 percent.

On July 13 at 1350 EDT, a power level decrease was initiated as a result of exciter and voltage regulator problems associated with the main generator. On July 15 at 1101 EDT, with the reactor at approximately 20 percent power, the turbine was manually tripped, and the unit was removed f rom service to allow for exciter and voltage regulator repairs.

On July 15 at 1352 EDT, with Unit 1 operating at approximately 25 percent reactor power and the turbine offline, a manual reactor trip was initiated as a result of the loss of the No. 4 Reactor Coolant Pump (RCP). RCP No. 4 tripped as a result of the loss of power to the control circuit to the 1-D unit board. During the tagging of the Unit 1 generator for maintenance work, the bus side potential transformer fuses were pulled instead of the line side fuses. When the fuses were pulled, the board bus sensed a loss of voltage and subsequently tripped off loads on the 1-D unit board. Operators stabilized the unit in Mode 3.

The Unit i reactor was taken critical on July 17 at 2243 EDT and was tied to the grid on July 18 at 2002 EDT.

Unit 1 was operating at approximately 96 percent reactor power at the end of July.

UNIT __2 Unit 2 generated 80,069 megawatthours (MWh) (gross) electrical power during July with a capacity factor of 9.4 percent. Unit 2 was operating at approximately 79 percent reactor power at the beginning of the month and was in coastdown to the Unit 2 Cycle 6 refueling outage. On July 4 at 2106 EDT, Unit 2 was taken offline, and the refueling outage began.

On July 19 at 1438 EDT, the first fuel assembly was removed from the core. The core was offloaded by 1846 EDT on July 21. Unit 2 remained in "no mode" with the core offloaded at the end of July.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __SQ:31Z. UNIT No. One DATE: _QB-Q2-2_4 COMPLETED BY: I. J. Hollomon TELEPHONE: 1615) 843-7528 MONTH: J LY_1194 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe: Net) DAX (MWe-Net) 1 1123 17 -21 2 LL23 18 -3 3 1120 19 357 4 1121 20 627 5 1LQ3 21 1076 6 1102 22 1118 7 _1071 23 1120 8 1106 24 1114 9 1108 25 1LL6 10 1116 26 1113 l

11 1Q28 27 1116 12 975 28 1116 13 1018 29 1120 l 14 940 30 1023 15 119 31 1059 1

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AVERACE DAILY UNIT POWER LEVEL DOCKET NO. __10-328 UNIT No. Two DATE: _D8-02-94 COMPLETED BY: T. JJiollomon TELEP110NE: 1615) 843-712H MONTH: JULY 1994 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (tMe-Ne t ) DAY (t1We-Ne t )

1 885 17 -16 2 877 18 -16 3 867 19 -5 4 571 20 -5 5 -14 21 -7 6 -H 22 -4 7 -8 23 -6 8 -6 24 -4 9 -4 25 -6 10 -4 26 -5 11 -4 27 -6 12 -6 28 -4 13 -7 29 -4 14 -6 30 -4 15 _12 31 -6 16 -19

8 OPERATING DATA REPORT DOCKET NO. _50-327 DATE _QBl01/.24 COMPLETED BY L_J. Hollomon _

TELEPHONE (615) 843-7528 QPERATING SIAIUS l Notes l

1. Unit Name: __Se.qunyah_llnLL0ne l l

2. Reporting Period: __Jylv 1994 l l

3. Licensed Thermal Power (MWt): 3411.0 l l

4. Nameplate Rating (Gross MWe): .J22D26 l l

5. Design Electrical Rating (Net MWe): 1148.0 l l

6. Maximum Dependable Capacity (Gross MWe): 1151.0 l l

7. Maximum Dependable Capacity (Net MWe): 1111.0 I 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 (Net MWe): N/A

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

11. Hours in Reporting Period 744 5,007 114&596

12. Number of Hours Reactor Was Critical 687.2 2.501.0 58.530

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 663.0 2.274.7 57.103.2

15. Unit Reserve Shutdown Ho*urs 0 0 0

16. Gross Thermal Energy Generated (MWH) 2.153.549,0 ___62182.009.3 185.875.763

17. Gross Electrical Energy Generated (MWH) __2.08.920 2.330.480 63.033.134

18. Net Electrical Energy Generated (MWH) 679.917 2.222.230 .. 60.386.267

19. Unit Service factor _E9.1 44.7 49.8

20. Unit Availability factor 89.1 44.7 49.8

21. Unit Capacity Factor (Using MDC Net) 82.3 39.3 47.4

22. Unit Capacity factor (Using DER Net) 79.6 38.1 45.9

23. Unit forced Outage Rate 10.9 7.8 37.9

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:

4 OPERATING DATA REPORT DOCKET NO. 50-326 DATE _EBLQ2/94 COMPLETED BY T. J. Hollomon TELEPHONE (615) 843-7528 QEGA11NG STATUS l Notes l

1. Unit Name: __JesupyA_h Uni t Two l l

2. Reporting Period: _ July 1994 l l

3. Licensed Thermal Power (MWL): 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 MWe): _110610 1 1

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): ___H/A

10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 5.087 106.656

12. Number of Hours Reactor Was Critical 94.3 4.377 Z_ 63.136

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 93.1 4.322.5 61.6162a__

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 243.427.2 14.285.939 3_ 194.048.891

17. Gross Electrical Energy Generated (MWH) . 00.R69 4.913 R $ _ J 1 M Q.970

18. Net Electrical Energy Generated (MWH) 72.036 4.730.795 63.009.081

19. Unit Service Factor 12.5 85.0 57.8

20. Unit Availability Factor 12.5 85.Q_ 57.8

21. Unit Capacity factor (Using MDC Net) 8.8 84.1 53.4

22. Unit Capacity Factor (Using DER Net) 8.4 81.0 51.5

23. Unit forced Outage Rate 0.0 2.6 35.5

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: _ November 1. 1994

s DOCKET NO: 50-328 UNIT SHUTDOWh5 AMO POWER REQUCTICMS UNIT NAME: Two .

DATE: 08/02/94_ ,

REPORT MONTH: Jul y 1994 COMPLETED BY:T. J. Hollocon TELEPHONE:f615) 843-7528 ,

Method of Licensee Cause and Corrective Duration Shutting,Down Event Systgm Compgnent Action to No. Date Type' (Hours) Reason Reactor" Report No. Code Code Prevent Recurrence 3 940704 5 650.9 C 1 The Unit 2 Cycle 6 refueling outage began on July 4 at 2106 EDT.

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I:F Forced Reason: 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 0perator Training and License Examination 5-Reduction F-Administrative 9-Other S

G-Operational Error (Explain) Exhibit I-Same Source H-Other (Explain)

DOCKET NO: 50-327 UNIT SHUTOOWNS AND POWER REDUCTIONS UNIT MAME: One .

DATE: 08/02/94. .

REPORT MONTH: ' July 1994 COMPLETED BY:T. J. Hollomon TELEPHCNE:f615) 843-7528 ,

Method of Licensee Cause and Corrective Duration Shutting Down Event System Component Action to I 2 5 No. Date Type (Hours) Reason Reactor 3 Report No. Code # Code Prevent Recurrence 3 940713 F 2.8 B 5 On July 13 at 1350 EDT, a power level decrease was initiated as a result of problems with the main generator's voltage regulator. On July 15 at 1101 EDT, the turbine was manually tripped to perform voltage regulator repairs. The voltage regulator pulse generator card had f ailed. The card was subsequently replaced and returned to service.

4 940715 F 78.2 G 2 50-327/94011 202 On July 15 at 1352 EDT, Operations initiated a manual reactor trip as a result of the loss of the No. 4 RCP. RCP No. 4 tripped as a result of the loss of power to the control circuit. During the tagging of the Unit 1 generator for maintenance work, an operator incorrectly removed the bus side potential transformer fuses, resulting in a loss of voltage and subsequent tripping of loads on the 1-0 unit board. The cause of the event was operator error. The appro-priate disciplinary actions have been taken.

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F: Forced Reason: 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)

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