ML20112J208

Monthly Operating Repts for May 1996 for Browns Ferry Nuclear Plant Units 1,2 & 3

ML20112J208
Person / Time
Site:	Browns Ferry
Issue date:	05/31/1996
From:	Davenport J, Machon R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606200022
Download: ML20112J208 (13)

Text

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'L nn Twrmssw VJiey Auttienty. Post Offte Box 2000, Docatur, AiarArna 3'A09 2fX10 R. D. (Rick) Machon Vce Presdont, Browns Feny Nuclear Plant June 14, 1996 .

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) - MONTHLY OPERATING REPORT FOR THE MONTH OF MAY 1996 ,

i In accordance with the requirements of BFN Units 1, 2, and 3 Technical Specifications, Section 6.9.1.3, TVA is submitting the Monthly Operating Report for the month of May 1996 in the enclosure.

If you have any questions, please call me at (205) 729-2636. l Sincerely, R. D. on PAB 1E- FN Enclosure cc: See page 2 194 '

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9606200022 960531 PDR ADOCK 05000259 R PDR l

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U.S. Nuclear Regulatory Commission Page 2 l

June 14, 1996

- l Enclosure cc (Enclosure):

Mr. Mark S. Lesser, Branch 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 i Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. Jim Lang Director of Engineering and Operations Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 NRC Resident Inspector Browns Ferry Nuclear Plant  ;

10833 Shaw-Road Athens, Alabama 35611 3 Regional Administrator ,

U.S. Nuclear Regulatory Commission i Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

, Ms. Elizabeth Hannon Utility Data Institute ,

1200 G Street, NW l Washington, D.C. 20005-3802

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ENCLOSURE TENNESSEE VALLEY AUTHORIT" BROWNS FERRY NUCLEAR PLANT ( < Ai)

UNITS 1, 2, AND 3 MONTHLY OPERATING REPORT MAY 1996 (SEE ATTACHED) 4 I

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l OPERATIONAL

SUMMARY

MAY 1996 l BROWN 8 FERRY 1 Unit i remains shutdown on administrative hold to resolve various TVA and NRC concerns. Unit 1 has been on administrative hold since June 1, 1985. As a result, TVA considers that accrual of reporting hours is suspended since the unit has a maximum dependable capacity of zero MWe. Accordingly, TVA does not consider cumulative reporting period hours for the period beginning June 1, 1985, when calculating the operating status variables. I BROWN 8 FERRY 2 For the month of May, Unit 2 generated 699,980 megawatt hours l gross electrical power and operated at a capacity factor of 86 percent. The unit scrammed automatically on May 10, 1996, due to low reactor water level caused when the 2A and 2C feedwater pumps received a zero demand signal that resulted from reinitialization of the Reactor Feed Pump Feedwater Level Control System. The unit returned to service on May 14, 1996. As of May 31, 1996, Unit 2 has operated continuously for 18 days.

BROWNS FERRY 3 During the month, Unit 3 generated 699,980 megawatt hours gross electrical power and operated at a capacity factor of 86.1 percent. The unit scrammed automatically on May 1, 1996, due to low reactor water level following the failure of the Steam Packing Exhauster Condensate Bypass Valve. This action was followed by tripping of two of the condensate booster pumps and one feedwater pump thus causing a low reactor water level. The unit resumed operation on May 5, 1996. As of May 31, 1996, the unit has operated continuously for 27 days.

AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO: 50-259 l UNIT: BROWNS FERRY 1 i PREPARED BY: J. W. Davenport .

TELEPHONE: (205) 729-2690 l MONTH MAY 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 16 0 2 0 17 0 3 0 18 0 4 0 19 0 5 0 20 0 i 6 0 21 0 7 0 22 0 0 0 23 0 9 0 24 0 1

10 0 25 0 11 0 26 0 12 0 27 0 13 0 _

28 0 14 0 29 0 15 0 30 0 31 0 l

l

1 l

AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO: 50-260 '

UNIT: BROWNS FERRY 2 PREPARED BY: J. W. Davenport  !

TELEPHONE: (205) 729-2690

, MONTH. MAY 1996 i ' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net) 1 1085 16 1003  ;

i i 2 1092 17 1002 3 1085 18 1078 4 1083 19 1080

. J 5 1112 20 1074 l

-i

) 6 1086 21 1074 7 1083 22 1080 8 1087 23 1074

!~

9 1086 24 1075 10 445 25 1067 11 0 26 1071 12 0 27 1069 l 13 0 28 1073 14 167 29 1074 i

15 980 30 1077 i'

1 31 1078 i

1' 1

, l l

4 l M

, ,. ., 3 ,.m -

- m

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:- 50-296 UNIT:--BROWNS FERRY 3 PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 MONTH M.\Y 1996 DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 455 16. 1080 i

2 0 17 1079

-3 0 18 1076 4 0 19 1067 5 466 20 1072 6- 930 21 1072 7 875 22 1079 8 1093 23 1071 9 1092 24 1073 10 1022 25 1068 11 1077 26 1040 12 1062 27 1073 13 1079 28 1070 14 1080 29 1070 15 1081 30 1074 31 1079

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-259 REPORT MONTH: MAY 1996 UNIT: BROWNS FERRY 1 PREPARED BY: J. W. Davenport ,

TELEPHONE: T205) 729-2690 Method of License Duration shutting Event syst9 e t Cause and Corrective Action to Prevent No. Date Type 3 (Mours) Reesen2 Down Reactor3 Report No. Code Code Recurrence 1 06/01/85 5 744 F 4 Administrative hold to resolve verlous TVA and NRC concerns.

k-Forced k-EquionentFailure(Explain) hthod: ' Instructions for Preparation of Licensee S-Scheqlksted B-Maintenance or Test 1-Manuel Event Reports (NUREG-1022)

C-Refueling 2-Manuel Scram D-Regulatory Restriction 3-Automatic scram E-operator Training and License Examination 4-Continuation of Existing Outoge F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other M-Other (Emplain)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-260 REPORT MONTH: MAY 1996 UNIT: BROWNS FERRY 2 PREPARED BY: J. W. Davenport .

TELEPHONE: (205) 729-2690 Method of License Duration Shutting Event Systy Cgt cause and Corrective Action to Prevent No. Date Type 3 (Nours) Reason2 Doun Reacto.y Report No. Code Code Recurrence 2 05/10/% F 100 N 3 260/96005 Je sK The Unit 2 reactor scrassmed automaticatty on May 10, 1996, ekse to teu reactor water level caused when the 2A and 2C feedseter samps received a zero demand signet that resulted fross reinitialization of the Reactor Feed Puup Feedseter Level Control Systemi.

The root cause of the reactor scrant was inedep ote design of the digital feeduster control system softwere that caused five logic functions to automaticatly-reinitialize to zero output after software changes were made.

l i

l 2A-Equipment l

l F-Forced Failure (Explain) hthod: ' Instructions for Properation of Licensee S-Scheduled B-Meintenance or Test 1-Manuel Event Reports (NURE3-1022)

C-Refueling 2-Manuel scram D-Regulatory Restriction 3-Automatic scram E-Operator Training and License Examination 4-Continuation of Existing Outage F-Administrative S-Recisction G-Operational Error (Explain) 9-Other M-Other (Explain) l i

t

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

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-296 REPORT MONTH: MAY 1996 UNIT: BROWNS FERRY 3 PREPARED BY: J. W. Davenport .

TELEPHONE: (205) 729-2690 Method of License Duration shutting 3 Event Systage Qt Cause and Corrective Action to Prevent No. Date Type I (Nours) Reason2 Down Reactor Report No. Code Code Recurrence 4 05/01/96 F 74.9 A 3 296/96003 SJ FCV The Unit 3 reactor scransned due to low reactor water levet following the failure of the Steam Packing Exhauster condensate Bypass Va;ve.

The shaft connecting the valve disk to the operator fatted resulting in a sunnentary closure of the velve. This action was followed by tripping of two of the condensate booster pLaps and one feedwater ptsup thus causing a low reactor water levet.

h-Forced k-EquipmentFalture(Explain) hthod: ' Instructions for Preparation of Licensee S-Schedated B-Maintenance or Test 1-Manuel Event Reports (NUREG-1022)

C-Refueling 2-Manuel Scram D-Regulatory Restriction 3-Automatic Scram E-Operator Training and License Examination 4-Continuation of Existing Outage F-Administrative 5-Reduction G-operational Error (Explain) 9-Other M-Other (Explain)

OPERATING DATA REPORT DOCKET: 50-259 UNIT: BROWNS FERRY l i PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 l

l OPERATING STATUS

1. Unit Name: BROWNS PERRY UNIT 1

2. Reporting Period: NAY 1996

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): 0

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

10. Reason For Restrictions, If Any: Administrative Bold THIS M3NTE YEAR TO DATE CUNULATIVE*

11. Hours in Reporting Period 0 0 95743

12. Hours Reactor Was Critical 0 0 59521

13. Reactor Reserve Shutdown Hours 0 0 6997

14. Hours Generator On Line 0 0 58267

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Generation (MWh) 0 0 168066787

17. Gross Electrical Generation (MWh) 0 0 55398130

18. Net Electrical Generation (MWh) 0 0 53796427

19. Unit Service Factor 0 0 60.9

20. Unit Availability Factor 0 0 60.9

21. Unit Capacity Factor (MDC Net) 0 0 52.8

22. Unit Capacity Factor (DER net) 0 0 52.8

23. Unit Forced Outage Rate 0 0 25.6

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: To Be Determined

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

e OPERATING DATA REPORT DOCKET: 50-260 UNIT: BROWNS FERRY 2 PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 '

1 OPERATING STATUS

1. Unit Name: BROWNS FERRY UNIT 2

2. Reporting Period: MAY 1996

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 NoNTH YEAR TO DATE CUMULATIVE *

11. Hours in Reporting Period 744.0 3647.0 134478

12. Hours Reactor Was Critical 655.0 2843.0 93622

13. Reactor Reserve Shutdown Hours 0.0 0.0 14200

14. Hours Generator On Line 644.0 2779.0 91267

15. Unit Reserve Shutdown Hours 0.0 0.0 0

16. Gross Thermal Generation (MWh) 2085456.0 8508456 267848788

17. Gross Electrical Generation (MWh) 699420.0 2808510 88973828

18. Het Electrical Generation (MWh) 681561.0 2732294 86519165

19. Unit Service Factor 96.6 76.2 67.9

20. Unit Availability Factor 86.6 76.2 67.9

21. Unit Capacity Factor (MDC Net) 86.0 70.3 60.4

22. Unit Capacity Factor (b8R net) 86.0 70.3 60.4

23. Unit Forced Outage Rate 13.4 3.5 15.6

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

25. It Shut Down At End Of Reporting Period, Estimated Date of Startup: N/A Excludes hours under administrative hold (June 1, 1985 to May 24, 1991)

OPERATING DATA REPORT DOCKET: 50-296 UNIT: BROWNS FERRY 3 PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 4

e OPERATING STATUS

1. Unit Name: BROWNS FERRY UNIT 3

2. Reporting Period: MAY 1996

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 M3NTE YEAR To DATE CtBdULATIVE*

11. Hours in Reporting Period 744.0 3647.0 77700

12. Hours Reactor Was Critical 669.7 3488.0 49783

13. Reactor Reserve Shutdown Hours 0.0 0 5150

14. Hours Generator On Line 656.5 3460.7 48478

15. Unit Reserve Shutdown Hours 0.0 0 0

16. Gross Thermal Generation (MWh 2101128.0 11091408 145361689

17. Gross Electrical Generation (MWh) 699980.0 3739060 48737390

18. Net Electrical Generation (MWh) 681949.0 3647763 46526390

19. Unit Service Factor 88.2 94.9 62.4

20. Unit Availability Factor 88.2 94.9 62.4

21. Unit capacity Factor (MDC Net) 86.1 93.9 56.2

22. Unit capacity Factor (DER net) 86.1 93.9 56.2

23. Unit Forced Outage Rate 11.8 5.1 20.5

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 (June 1, 1985 to November 19, 1995)

.