ML20077R370

Monthly Operating Repts for Dec 1994 for J M Farley Nuclear Plant Units 1 & 2

ML20077R370
Person / Time
Site:	Farley
Issue date:	12/31/1994
From:	Hill R, Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9501200188
Download: ML20077R370 (10)

Text

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Soutnern Nuc!:ar Operating Company Post Offica Box 1295

. Birminghtm. Alabama 35201 Telephone (205) 868-5131 o..e uorey Southem Nuclear Operating Company "

Vice President Farfey Prolect the Southem electnc System j

l January 13, 1995 i Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATl'N: Document Control Desk Washington,D.C. 20555 Joseph M. Farley Nuclear Plant Monthly Oocrating Data Repor1 _

Gentlemen:

Attached are the December 1994 Monthly Operating Reports for Joseph M. Farley Nuclear Plant Units 1 and 2, as required by Section 6.9.1.10 of the Technical Specifications.

If you have any questions, please adsise.

Respectfully submitted, fh llL.w t Dave Morcy RWC:jgp(mor)

Attachments cc: Mr. S. D. Ebneter Mr. B. L. Siegel Mr. T. M. Ross 1000S5 95012001gg 941231 '

0500 8 I

j Joseph M. Farley Nuclear Plant Unit 1 1 Narrative Summary of Operations )

December 1994 l There were no unit shutdowns or major power reductions during the month.

There was no major safety related maintenance performed during the month. J l

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OPERATING DATA REPORT DOCKET NO. 50-348 DATE January 9,1995 COMPLETED BY R. D. Hill l TELEPIIONE (205) 899-5156 DEERATING STATUS

1. Unit Name: Joseph M. Farley - Unit 1 Notes

2. Reporting Period: December 1994 1) Cumulative data sincel2-01-77,

3. Licensed Thermal Power (MWt): 2,652 date of commercial operation.

4. Nameplate Rating (Gross MWe): 860 l

5. Design Electrical Rating (Net MWe): 829 l

6. Maximum Dependable Capacity (Gross MWe): 855.7 l

7. Maximum Dependable Capacity (Net MWe): 812

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since  ;

Last Report, Give Reasons: N/A i l

9. Power Level To Which Restricted, If Any (Net MWe): N/A

10. Reasons For Restrictions,If Any: N/A i

This Month Yr.to Date Cumulative l

11. Hours in Reporting Period 744.0 8,760.0 149,760.0

12. Number Of Hours Reactor Was Critical 744.0 7,592.9 119,256.8 i

13. Reactor Reserve Shutdown Hours 0.0 10 3,650.0  !

14. Hours Generator On-line 744.0 _

7,547.3 117,453.9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,972,719.6 19,643,311.8 302,135,717.0

17. Gross Electrical Energy Generated (MWH) 649,957.0 6,398,659.0 97,413,705.0

18. Net Electrical Energy Generated (MWH) 618,121.0 6,059,835.0 91,999,989.0 j

19. Unit Service Factor 100.0 86.2 78.4

20. Unit Availabilty Factor 100.0 86.2 78.4

21. Unit Capacity Factor (Using MDC Net) 102.3 85.2 75.4

22. Unit Capacity Factor (Using DER Net) 100.2 83.4 74.1

23. Unit Forced Outage Rate 0.0 0.0 6.0

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

N/A

25. If Shut Down at End Of Report Period, Estimated Date of Startup: N/A

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved Initial Criticality 08/06/77 08/09/77 Initial Electricity 08/20/77 08/l8/77 Commercial Operation 12/01/77 12/01/77

DOCKET NO. 50-348 UNIT l DATE January 9,1995 COMPLETED BY R. D. Hill TELEPHONE (205) 899-5156 MONTH December DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 834 17 832 2 831 18 832 3 827 19 834 4 827 20 833 5 825 21 831 6 829 .22 832 7 829 23 830 8 829 24 832 9 828 25 833 10 826 26 833 11 833 27 832 12 834 28- 832 13 834 29 831 14 833 30 830 15 833 31 831 16 831 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting period. Compute to the nearest whole megawatt.

UNIT SIIUTDOWNS AND POWER REDUCTIONS .

DOCKEfNO. Lt)-348 UNIT NAME J. M. Farley - Unit 1 ,

DATE' January 9,1995

, COMPLETED BY R. D. Ilill r REPORT MONTil December TELEPilONE (205) 899-5156 t MEDIOD OF LICENSEE CAUSE AND CORRECTIVE

f. DURADON SIIUTrlNG EVENT SYSTEM COMPONENT ACTION TO NO. DATE TYPE (I) IIOURS REASON (2) DOWN REACTORM REPORT # CODE (4) CODEM PREVENT RECURRENCE j fihere were no Shutdowns or power reductions during the month. ,

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4 F: Forced Reason Method Exhibit G-Instructions for Exhibit I - Same Source j S: Scheduled A - Equipment Failure (Explain) 1 - Manual Preparations of Date Entry B - Maintenance or Test 2 - Manual Scram Sheets for Licensee Event i C - Refueling 3 - Automatic Scram Report (LER) File (NUREG-016I)

.j D - Regulatory Restriction 4 -Other (Explain)

E - Operator Training & License Examination F - Administrative G - Operational Ervar (Explain) j II - Other (Explain) i l

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Joseph M. Farley Nuclear Plant )

Unit 2

! Narrative Summary of Operations l December 1994 l I There were two unit shutdowns during the month.

l l At 0352 on 12/18/94, with the unit in mode 1 and operating at 100 percent reactor power, the l reactor tripped due to low-low water level in the 2C steam generator (SG). This was a result l of a transient initiated from the closing of all four governor valves due to an intermittent i failure of the turbine control system. A suspect pressure switch, which provides an l electrical input to the digital electro-hydraulic control (DEHC) auto stop latch circuitry was l replaced.

l The unit returned to 100 percent reactor power at 0542 on 12/21/94.

l At 1534 on 12/25/94, with the unit in mode I and operating at 100 percent reactor power, the reactor tripped due to a turbine trip caused by an intermittent DEHC system failure. When '

compared to the 12/18/94 reactor trip, both trips were most likely caused by an intermittent DEHC system processor failure. Subsequently, the suspect DEHC cards were replaced.

The unit retumed to 100 percent reactor power at 0743 on 12/28/94.

There was no major safety related maintenance performed during the month.

,- OPERATING DATA REPORT DOCKET NO. 50-364 DATE January 9,1995 COMPLETED BY R. D. Hill TELEPilONE (205) 899-5156 l

QPEIMTING STATUS

1. Unit Name: Joseph M. Farley - Unit 2 Notes

2. Reporting Period: December 1994 1) Cumulative data since 07-30-81,

3. Licensed Thermal Power (MWt): 2,652 date of commercial operation.

4. Nameplate Rating (Gross MWe): 860

! 5. Design Electrical Rating (Net MWe): 829 l 6. Maximum Dependable Capacity (Gross MWe): 863.6

7. Maximum Dependable Capacity (Net MWe): 822

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A l 9. Power Level To Which Restricted, If Any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A l

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This Month Yr.to Date Cumulative

11. Hours in Reporting Period 744.0 8,760.0 117,673.0

12. Number Of Hours Reactor Was Critical 702.0 8,704.0 101,657.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 138.0 l 14. Hours Generator On-line 676.0 8,660.8 100,222.6 l 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

! 16. Gross Thermal Energy Generated (MWH) 1,709,587.1 22,804,352.9 256,339,705.7 l 17. Gross Electrical Energy Generated (MWH) 562,813.0 7,505,081.0 84,054,542.0 l 18. Net Electrical Energy Generated (MWH) 532,685.0 7,147,209.0 79,722,298.0

19. Unit Service Factor 90.9 98.9 85.2

20. Unit Availabilty Factor 90.9 98.9 85.2 l 21. Unit Capacity Factor (Using MDC Net) 87.1 99.3 82.6_

l 22. Unit Capacity Factor (Using DER Net) 86.4 98.4_ 81 7 j 23. Unit Forced Outage Rate 9.1 1.1 4.0 l 24. Shutdowns Scheduled ' . <er Next 6 Months (Type, Date, and Duration of Each):

Refueling / Maintenance outage, March 10,1995. Approximately 39 days.

25. If Shut Down at End Of Report Period, Estimated Date of Startup: N/A

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved i Initial Criticality 05/06/81 05/08/81 Initial Electricity 05/24/81 05/25/81

- DOCKET NO. 50-364 UNIT 2 DATE January 9,1995 COMPLETED BY R. D. Ilill TELEPHONE (205) 899-5156 MONTH December DAY AVERAGE DAILY POWER LEVEi DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 846 17 840 l 2 843 18 107 l

3 836 19 8.2 i

4 831 20 331 I

5 838 21 820 i

6 838 22 839  !

7 838 23 839 I

8 837 24 842 9 845 25 535 10 845 26 0 l

l 11 845 27 334 l

12 843 28 777 13 843 29 837 14 843 30 836 15 843 31 839 16 841 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting period. Compute to the nearest whole megawatt.

UNIT SIIUTDOWNS AND POWER REDUCTIONS ,

DOCKET NO. 50-364

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UNIT NAME J. M. Farley - Unit 2 .

DATE January 9,1995 COMPLETED I?Y R. D. Ilill REPORT MONTil Decernher TELEPilONE (205) 899-5156 h1ETilOD OF 11 WSIE CAUSE ANDCORRECTIVE DURATION SilUTTING IVENT SYSTIhl COMPONENT ACilON TO

_ NO. DATE TYPli{l) IIOURS REASON (2) IXhVN REACIOR131. RFPORT # { CODE (4) CODE 151 PREVENT RECURRENCE

'004 12/i8/94 F 38.2 A -3 44-003-00i At 0352 on 12/18/94, with the unit in mode I and operating at 100 percent reactor power, the reactor tripped due to low-low water level in the 2C steam generator (SG). This was a result of a transient initiated from the closing of all four governor valves due to an intermittent failure of the turbine control system. A suspect pressure switch, which provides an electrical input to the digital electro-hydraulic control (DEIIC) auto stop latch circuitry was replaced.

The unit returned to 100 percent reactor power at 0542 on 12/21/94.

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I: 2: 3: 4: 5:

F: Forced Reason hiethat Exhibit G- Instructions for Exhibit I - Same Souru:

S: Scheduled A - Equipment Failure (Explain) 1 - N1anual Preparations of Dare Entry B - hiaintenance or Test 2 - h1anual Scram Sheets for Licensee Esent C - Refueling 3 - Automatic Scram Report (LER) File (NUREG-016I)

D - Regulatory Restriction 4 - Other (Explain)

E - Oxrator Training & License Examination F- Administrative G - Operational Error (Explain) 1I-Other (Explain) 7.-, . n_ : , ~g,~r -m, ,

2- . ) l k$ ~ s .u :s2 +rO ,+

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-364 ,

UNIT NAME J. M. Farley - Unit 2 DATE January 9,1995 COMPLETED BY R. D. Ilill .

REPORT MONTil December TELEPilONE (205) 899-5156 i

METilOD OF LICENSEE CAUSE AND CORRECTIVE DURATION SIIUTTING EVENT SYSTEM COMPONENT ACTION TO NO. DATE TYPE (1) IlOURS REASON p)tDOWN REAcrOR (3} REPORT # CODE (4) CODE (5} PREVENT RECURRENCE 005 12/25/94: F F 2Mil A 3 94-004-00' At 1534 on 12/25/94, with the unit in mode 1 and operating at 100 percent reactor power, the reactor tripped due to a ,

turbine trip caused by an intermittent DEllC system failure.

When compared to the 12/18/94 reactor trip, both trips were most likely caused by an intermittent DEllC s 7.m processor failure. Subsequently, the suspect m 'IC cards were replaced.

The unit returned to 100 percent reactor power at 0743 on 12/28/94.

1: 2: 3: 4: 5:

F: Forced Reason Method Exhibit G-Instructions for Exhibit 1 - Same Source S: Scheduled A - Equipment Failure (Explain) 1 - Manual Preparations of Date Entry B - Maintenance or Test 2 - Manual Scram Sheets for Licensee Event C - Refueling 3 - Automatic Scram Report (LER) File (NUREG-016I)

D - Regulatory Restriction 4 - Other (Explain)

E - Operator Training & License Examination F- Administrative G - Operational Error (Explain)

II- Other (Explain)

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