ML20058N046

Monthly Operating Repts for Nov 1993 for Browns Ferry Nuclear Plant Units 1,2 & 3

ML20058N046
Person / Time
Site:	Browns Ferry
Issue date:	11/30/1993
From:	Salas P, Tanya Smith TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9312210210
Download: ML20058N046 (13)

Text

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Tennessee Valley Authority Post Office Box 2000. Decatur. Alabama 35609 DEC 151993 U.S.

Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter Of

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN)

'#9NTHLY OPERATING REPORT FOR THE MONTH OF NOVEMBER 1993 In accordance with the requirements of BFN Technical Specifications Section 6.9.1.3, TVA is submitting the Monthly Operating Report for the month of November'1993 in the enclosure.

If you have any questions, please telephone me at (205) 729-2636.

Sincerely,

{z o

' bN'

&las Manager of Site Licensing l

Enclosure cc:

See page 2 l

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- 9312210210 931130 f -.

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PDR :ADOCK 05000259 PDR Ib

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i U.S. Nuclear Regulatory Commission Page 2 DEC 151993 Enclosure cc (Enclosure):

Mr. R. V.

Crlenjak, Project Chief U.S.

Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects I-II office of Nuclear Reactor Regulation, Mail 13 H3 Washington, D.C.

20555 INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Mr. Ted Martson, Director Electric Power Research Institute P.

O.

Box 10412 Palo Alto, California 94304 NRC Resident Inspector Browns Ferry Nuclear Plant he s klbma 35611 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Fred Yost, Director of Research Services, Utility Data Institute, Inc.

1700 K Street, NW, Suite 400 Washington, D.C.

20006

ENCLOSURE MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY NOVEMBER 1993 i

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DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 i

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l OPERATIONAL

SUMMARY

NOVEMBER 1993 UNIT 1 Unit i remains on administrative hold to resolve various TVA and NRC concerns.

The operating data report reflects the assignment of administrative hold status to Unit 1 effective June 1, 1985.

Administrative hold status is considered by TVA to suspend the accrual of reporting period hours since this unit is considered to have a maximum dependable capacity of 0 MWe.

For this reason, cumulative reporting period hours for the period after June 1, 1985, to present are not considered when calculating operating status variables such as cumulative capacity factor rate.

These considerations will affect the other operating status reporting i

variables accordingly.

t UNIT 2 Unit 2 operated continuously during the month of November at a capacity factor of 101.5 percent and generated 797,290 megawatt hours gross electrical power.

Power was reduced to approximately 70 percent on November 19, 1993, to replace the 2C condensate pump oil cooler.

Unit 2 returned to 100% power on November 20, 1993.

Unit 2 was at reduced power for approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

As of November 30, 1993, Unit 2 has operated continuously for 181 i

days since returning to service following the refueling outage.

UNIT 3 i

Unit 3 remains on administrative hold to resolve various TVA and i

NRC concerns.

The operating data report reflects the assignment of administrative hold status to Unit 3 effective June 1, 1985.

Administrative hold status is considered by TVA to suspend the accrual of reporting period hours since this unit is considered i

to have a maximum dependable capacity of 0 MWe, For this reason, cumulative reporting period hours for the period after June 1, j

1985, to present are not considered when calculating operating status variables such as cumulative capacity factor rate.

These considerations will affect the other operating status reporting variables accordingly.

+

AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO:

50-259 UNIT:

One PREPARED BY:

T.

R. Smith f

TELEPHONE:

f205) 729-2955 MONTH November 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

I 2

0 18 0

3 0

19 0'

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

l I

14 0

30 0

I 15 0

16 0

I

4 h

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-260 UNIT:

Two PREPARED BY:

T.

R.

Smith TELEPHONE:

(205) 729-2955 5

MONTH November 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWs-Net) i f

1 1096 17 1087 2

1094 18 1092 i

3 1090 19 960 i

4 1091 20 987

?

5 1068 21 1085 6

1082 22 1093 7

1091 23 1094 8

1090 24 1089 l

9 1090 25 1090 10 1090 26 1090 11 1090 27 1087

)

12 1087 28 1089 13 1081 29 1093 14 1088 30 1093 15 1090 16 1089 l

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F AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO:

50-296 UNIT:

Three PREPARED BY:

T.

R.

Smith TELEPHONE:

(205) 729-2955 MONTH November 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

16 0

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)

DOCKET NO:

50-259 UNIT SHUTDOWNS AND POWER REDUCTICS LOIT NAME:

One PREPARED BY:

T. R. Smith REPORT MONTH:

Nove h r 1993 TELEPHONE: (205) 729-2955 Method of License Cause and Corrective Duration Shutting Event System Conponent Action to Prevent No.

Date Type' (Hours)

Reason' Down Reactor Report No.

Code

• Code' Recurrence 8

1 06/01/85 5

720 F

4 Adninistrative hold to resolve various TVA and NRC concerns.

'F: Forced Reason:

' Method:

• Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or fest 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-061)

E-operator Training and License Examhetion 5-Reduction F-Adninistrative 9-Other G-operational Error (Explain)

' Exhibit 1-Same Source H-Other (Explain)

I

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DOCKEi NO:

50-260 UNIV SHUTDOWNS AND POWEQ CEDUC710NS t*lf NAME:

Tuo PREPARED BY:

T. R. Smith REPORT MONTH:

Novenber 1993 TELEPHONE: (205) 729-2955 8

Method of License Cause ord Corrective Duration Shutting Event System Component Action to Prevent No.

Date Type' (Hours)

Reason' Down Reactor Report No.

Code

• Ccde' Recurrence s

3P 11/19/93 5

0 A

5 Power reduction to replace 2C condensate ptmp ott cooter 4

t

'F: Forced

_' Reason:

Method:

" Exhibit G-Instructions S: Scheduled A-Etpipment Failure (Explain)-

1-Manual for Preparatism of Data 8-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-061)

E-Operator Training and License Examination 3-Reduction

~ F-Administrative 9-Ottar~

G-Operational Error (Explain)

' Exhibit I-Same Source H-Other (Explain) 4 i

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_ -,. ~. -

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--.-m. -...

~, -. - - -.,.,..,...

......., -.. _ _ _... - ~,... - -. -

DOCKET NO:

50-296 10!? SHUTDOWNS AND POWER CEDUCTIONS UNIT CAME:

Three

^

PREPARED BY:

T. R. Smith REPORT MONTH:

Noveeber 1993 TELEPHONE: (205) 729-2955 Method of License Cause and Corrective Duration Shutting Event System Conponent Action to Prevent No.

Date Type' (Hours)

Reason' Down Reactor

• Report No.

Code

• Code' Recurrence 1

06/01/85 5

720 F

4 Adninistrative hold to resolve various TVA and NRC concerns.

'F:

Forced

' Reason:

Method:

' Exhibit G-Instructions S: Scheduled A-Equipnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Autmatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-061)

E-Operator Training and License Examination 5-Reduction F-Adninistrative 9-Other G-Operational Error (Explain)

' Exhibit I-Same Source H-Other (Explain)

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OPERATING DATA REPORT l

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DOCKET:

50-259 l

PREPARED BY

.T.

R. SMITH-l

{

TELEPHONES-(205) 729-2955 OPERATING STATUS

't

1. Unit Names BROWNS FERRY UNIT ONE l

2. Reporting Periods NOVEMBER 1993

3. Licensed Thermal Power (MWt):

3293 l

4. Nameplate Rating (Gross MWe):

1152 j

5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Gross MWe):

0

7. Maximum Dependable Capacity (Net MWe):

0 1l

8. If Changes occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason:.N/A

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

0

10. Reason'For Restrictions,.If Any: Administrative Hold t

i THIS MONTH YEAR TO DATE CUNULATIVE*

f

11. Hours in Reporting Period 0

0 95743

.l

12. Hours Reactor Was Critical 0

0 59521

13. Reactor Reserve Shutdown Hours 0

0

'6997

['

14. Hours Generator on Line

'O O

58267-

15. Unit Reserve Shutdown Hours 0-0 0

?

16. Gross Thermal Generation (MWh)

O.

0 168066787

17. Gross Electrical Generation (MWh) 0

.0-55398130

18. Net Electrical Generation (MWh) 0 0

53796427 l}

19. Unit Service Factor 0

0 60.9 i

20. Unit Availability Factor 0

0 60.9.

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21. Unit Capacity Factor (MDC Net) 0 0

52.8:

22. Unit Capacity Factor (DER net) 0 0

52.8 j

23. Unit Forced Outage Rate 0

0' 25.6 i

24. Shutdowns Scheduled Over Next 6 Months.

l (Type, Date, and Duration of-Each): N/A

25. If Shut Down At End Of Reporting Period, Estimated Date of Startup: To be determined i

• Excludes hours under administrative hold (June 1, 1985 to present) s.

I OPERATING DATA REPORT i

DOCKET 50-260 PREPARED BY T. R. SMITH

]

TELEPHONE:

(205) 729-2955

]

l OPERATING STATUS

1. Unit Name BROWNS FERRY UNIT TWO

2. Reporting Period NOVEMBER 1993

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net MWe):

1065

8. If Changes occur in capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason:

N/A

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

10. Reason For Restrictions, If Any:

N/A THIS MONTH YEAR TO DATE CUMULATIVE *

11. Hours in Reporting Period 720 8016 112567

12. Hours Reactor Was Critical 720 5110 74073

13. Reactor Reserve Shutdown Hours 0

0 14200

14. Hours Generator On Line 720 0010 71881

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Generation (MWh) 2349509 15373444 206102095

17. Gross Electrical Generation (MWh) 797290 5100030 68377678

18. Net Electrical Generation (MWh) 778483 4965575 66433395

19. Unit Service Factor 100.0 62.5 63.9

20. Unit Availability Factor 100.0 62.5 63.9

21. Unit capacity Factor (MDC Net) 101.5 58.2 55.4

22. Unit Capacity Factor (DER net) 101.5 58.2 55.4

23. Unit Forced Outage Rate 0

0 18.7

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

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

• Excludes hours under administrative hold 1

(June 1, 1985 to May 24, 1991)

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~

i OPERATING DATA REPORT

.'t i

DOCKET 50-296-PREPARED BY T. R.

SMITH

. TELEPHONE '

(205) 729-2955 1

i b

I OPERATING STATUS r

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1. Unit Names BROWNS FERRY UNIT THREE

2. Reporting Periods NOVEMBER 1993

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):.1152

-5 l

5. Design Electrical Rating (Net MWe):. 1065

6. Maximum Dependable capacity'(Gross MWe): 0 j

7. Maximum Dependable Capacity (Net.MWe):

0

[

8. If Changes occur in capacity Ratings (Items Number 3 Through 7)'Since Last Report, Give' Reason:

N/A

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

.0-

.l

10. Reason For Restrictions, If Any: Administrative Hold j

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i THIS MONTH 1 YEAR TO DATE CUMULATIVE

• 1

12. Hours Reactor Was Critical

._O O

73055'

11. Hours in Reporting Period 0

0 45306 l'

13. Reactor Reserve Shutdown Hours 0

0 5150

14. Hours Generator on Line 0

0 44195

15. Unit Reserve Shutdown Hours 0

0

'O i

16. Gross Thermal Generation (MWh) 0 0

131868267

l

17. Gross Electrical Generation (MWh) 0 0

43473760 i

18. Net Electrical Generation (MWh) 0 0

42114009

19. Unit Service Factor 0

0 60.5

20. Unit Availability. Factor 0

0 60.5

21. Unit Capacity Factor (MDC Net) 0 0

54.2

22. Unit Capacity Factor (DER net) 0 0

54.2-

23. Unit Forced Outage Rate 0

,0 21.6

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

' j

25. If Shut Down At End Of Reporting Period, Estimated Date of Startup: To be determined

• Excludes hours under administrutive hold (June 1, 1985 to present) i i