ML20107G025

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for March 1996 for Browns Ferry Nuclear Plant
ML20107G025
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 03/31/1996
From: Davenport J, Salas P
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9604230077
Download: ML20107G025 (14)
v • d • e


Text

Tennesseo Valley Authority. Post Ofhce Box 2000. Decatur, Alabama 35609 April 15, 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 I

)

BROWNS FERRY NUCLEAR PLANT (DFN) - MONTHLY OPERATING REPORT l FOR THE MONTH OF MARCH 1996 In accordance with the requirements of BFN Units 1, 2, and 3 Technical Specifications, Section 6.9.1.3, TVA is submitting l' the Monthly Operating Report for the month of March 1996 in the enclosure. Also included in the enclosure is a revised Unit 3 Shutdowns and Power Reductions page for the February i 1996 Monthly Operating Report.

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

Sin e ,

  1. W Pedro Salas Manager of Site Licensing l Enclosure cc: See page 2 9604230077 960331 PDR ADOCK 05000259 R PDR

$$Yb N

/[j u

4 i g

- U.S. Nuclear Regulatory Commission Page 2

-April 15,-1996

' Enclosure ]

cc (Enclosure): l 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 j Regulation, Mail 13 H3 ,

Washington, D.C. 20555 INPO Records Center 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 i 10833 Shaw Road

. Athens, Alabama 35611 Regional Administrator

U.S.' Nuclear Regulatory Commission Region II i l

101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l Ms. Elizabeth Hannon

-Utility Data Institute 1200 G Street, NW Washington, D.C. 20005-3802 1

. l

. 1 4

4 ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 I MONTHLY OPERATING REPORT j MARCH 1996 (SEE ATTACHED)

J.

k k

1 i

l 1

l l

.i i

.i i

i

- _ . . _ _ . _ _ _ . _ . ._ m __

e OPERATIONAL

SUMMARY

MARCH 1996 BROWNS FERRY 1 4

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 0 MWe. Accordingly, TVA does not consider cumulative reporting period hours for the period beginning June 1, 1985, when calculating the operating status variables.

BROWNS FERRY 2 During the month Unit 2 operated at a capacity factor of 58.5 percent and generated 478,480 megawatt hours gross electrical 4 power. Unit 2 shutdown at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on March 23, 1996 for the cycle 8 refueling outage. The unit had operated continuously for 214 days. Unit 2 is scheduled to begin cycle 9 operation on April 20, 1996.

BROWNS FERRY 3 During the month Unit 3 operated at a capacity factor of 90.4 percent and generated 734,140 megawatt hours gross electrical power. The unit restarted on March 2, 1996 following a February 29, 1996 reactor scram resulting from a failed turbine speed feedback card in the EHC control system. As of March 31, 1996, Unit 3 has operated continuously for 29 days.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-259 UNIT:

BROWNS FERRY 1 PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 MONTH MARCH 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 6 0 21 0 7 0 22 0 8 0 23 0 9 0 24 0 10 0 25 0 11 0 26 0 l

12 0 27 0 13 0 28 0 14 0 29 0 15 0 30 0 31 0 i

1 1

l 1

1 1

a a

  • AVERAGE DAILY UNIT POWER LEVEL DOCKET No: 50-260 UNIT: BROWNS FERRY 2 PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 MONTH MARCH 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1006 16 858 2 973 17 845 3 919 18 851 4 916 19 844 5 913 20 843 6 902 21 813 7 862 22 813 8 852 23 49 9 887 24 0 10 866 25 0 11 877 26 0 12 870 27 0 e

13 870 28 0 14 866 29 0 15 858 30 0 31 0 i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-296 UNIT: BROWNS FERRY 3

, PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 MONTH MARCH 1996 DAY AVEPAGE DAILY POWER LEVEL DAY AVEPAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 16 878 2 0 17 1072 3 582 18 1090 4 695 19 1088 5 957 20 1090 6 941 21 1092 7 888 22 1092 8 1083 23 1092 9 1082 24 1064 10 1038 25 1091 11 1090 26 1085 12 1091 27 1082 13 1089 28 1091 14 1087 29 1091 15 1066 30 1088 31 1094

4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-259 REPORT MONTH: MARCH 1996 UNIT: BROWNS FERRY l

  • l PREPARED BY: J. W. Davenport TELEPHONE: -(205) 729-2690 Method of License Duration Shutting Event Systep Cqt Cause and Corrective Action to Prevent No. Date Type 1 (Hours) Reason Down Reactor3 Report No. cede code Recurrence 1 06/01/85 'S 744 F 4 A &inistrative hold to resolve various TVA -

and NRC concerns.

i 1

1 2

I F-Forced A-Equipment Failure (Explain) hthod: knstructionsforPreparationofLicensee S-Scheduled B-Maintenance or Test 1-Manual Event Reports (MUREG-1022)

C-Refueling 2-Manual Scram D-Regulatory Restriction 3-Automatic Scram E-Operator Training and License Examination 4-Continuation of Existing Outage F-A&inistrative 5-Reduction G-Operational Error (Explain) 9-Other H-Other (Explain)

- _ _ - - - _ _ - _ - _ = . _ . _ - - _ _ _ . _

_ _ - _ _ - - - - , - - _ _ _ - _ - - -- ' _ mmL- ----u -- - - - ' ' ' " ' ' ' '

. .. __.m...... ... . .. .- _ _ . . _ . . _ . - _ . - - . - - . .-- .

a-

.l UNIT' SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO: 50-260  ;

REPORT MONTH: MARCH 1996 UNIT: BROWNS FERRY 2 -'

PREPARED BY: J. W. Davenport TELEPHCNE: (205) 729-2690 ,

i Method of License

' I Duration Shutting Event Systy C t Cause and Corrective Action to Prevent  !

No. Date Type (Hours) Reason Down Reactor Report No. Code Code Recurrence 1 3/23/96 s 214 C 1 N/A N/A N/A Unit 2 Reactor shutdown for Refueling at t

. 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on March 23, 1996. r

-i 1

I i

i

. t

=

l  !

e  !

i

, t l I F-Forced k-Equipment Failure (Explain) hethod: bnstructionsforPreparationofLicensee [

S-scheduled B-Maintenance or Test 1-Manual Event Reports (NUREG-1022).  !

. C-Refueling 2-Manual Scram D-Regulatory Restriction 3-Automatic Scram  !

E-Operator Training and License Examination 4-Continuation of Existing Outage

  • F-Administrative S-Reduction i G-Operational Error (Explain) 9-Other H-Other (Explain) l
  • I I

i f

l

. i i

I i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-296 REPORT MONTH: MARCH 1996 UNIT: BROWNS FERRY 3

  • PREPARED BY: J. W. Davenport TELEPHONE: (205) 729-2690 Methd of License Curation shutting Event Systep Cgt Cause and Corrective Action to Prevent No. Date Type 9 (Hours) Reason Down Reactor 3 Report No. Code Code Recurrence 1 02/29/96 F 43.7 A 3 296/96001 JJ CNV A failed turbine speed feed >ack card in the Electro-Hydraulic Control system caused fluctuations in the turbine control and bypass valves. This caused a reactor pressure spike, which in turn caused an Average Power Range Monitor high flux spike that scrammed the reactor.

Note: This shutdown is a continuation of the one identified in the February 1996 report.

2 03/16/96 S 26 B 5 N/A N/A N/A Reduced power to 80% for Control Rod Drive Testing I

F-Forced k-EquipmentFailure(Explain) hethod: knstructionsforPreparationofLicensee S-Scheduled B-Maintenance or Test 1-Manual Event Reports (NUREG-1022)

C-Refueling 2-Manual Scram D-Regulatory Restriction 3-Automatic Scram E-Operator Training and License Examination 4-Continuation of Existing Outage F- Achinist rat ive 5-Reduction G-Operational Error (Explain) 9-Other N-Other (Explain)

OPERATING DATA REPORT

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

. - - - ~ _. _- .-

. l DOCKET: 50-259 l

. UNIT: BROWNS FERRY 1 i PREPARED BY: J. W. Davenport r

TELEPHONE: (205) 729-2690 i

OPERATING STATUS i

l' '1. Unit Name! BROWNS FERRY UNIT 1

.2., Reporting Period: MARCH 1996

3. Licensed Thermal Power (MWt): 3293
4. Nameplate Rating (Gross MWe):

~

1152

5. Design Electrical Rating (Net MWe): 1065
6. Maximam 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 Hold a
THIS MONTH YEAR TO DATE CUMULATIVE *
11. Hours in Reporting Period 0 0 95743 l 12. Hours Reactor Was Critical 0 0 59521 1 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 l 20. Unit Availability Factor 0 0 60.9 j 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 I
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)

J-

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

4 OPERATING DATA REPORT DOCKET: 50-260 UNIT: BROWNS FERRY 2 PREPARED BY: J. W. Davenport )

TELEPHONE: (205) 729-2690 l l

OPERATING STATUS

1. Unit Name:- BROWNS FERRY UNIT 2 2._ Reporting Period: MARCH 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 MONTH YEAR TO DATE CUMULATIV**
11. Hours in Reporting Period 744.0 2184.0 133015
12. Hours Reactor Was critical 530.0 1970.0 92749
13. Reactor Reserve Shutdown Hours 0.0 0.0 14200
14. Hours Generator on Line 530.0 1970.0 90458 I
15. Unit Reserve Shutdown Hours 0.0 0.0 0 f
16. Gross Thermal Generation (MWh) 1462392.0 6028824 265369156 l
17. Gross Electrical Generation (MWh) 478480.0 1985080 88150398 1
18. Net Electrical Generation (MWh) 463626.0 1932741 85719612
19. Unit Service Factor 71.2 90.2 68.0 l
20. Unit Availability Factor 71.2 90.2 68.0
21. Unit. Capacity Factor (MDC Net) 58.5 83.1 60.5
22. Unit Capacity Factor (DER net) 58.5 83.1 60.5
23. Unit Forced Outage Rate 0.0 0.0 15.7
24. Shutdowns Scheduled over Next 6 Months (Type, Date,'and Duration of Each): U2 Cycle 8 Refueling Outage, In progress
2 5. If Shut Down At End of Reporting Period, Estimated Date of Startup
April 20, 1996 Excludes' hours under administrative hold (June 1,-1985 to May 24, 1991)

. ~ . _ . . _ . _ . _ ___

0-OPERATING DATA REPORT DOCKET: 50-296 UNIT: BROWNS FERRY 3 PREPARED BY: J. W. Davenport TELEPHONE: (206) 729-2690 1

OPERATING STATUS

1. Unit Name: BROWNS FERRY UNIT 3
2. Reporting Period: MARCH 1996
3. Licenaed 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 i
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 Aay: N/A I THIS MONTH YEAR TO DATE CUMULATIVE
  • i l
11. Hours in Reporting Period 744.0 2184.0 76237 l 12 Hours Reactor Was Critical 706 9 2124.9 48420 l 1
13. Reactor Reserve Shutdown Hours 0.0 0 5150
14. Hours Generator on Line 700.3 2118.3 47123

! 15. Unit Reserve Shutdown Hours 0.0 0 0

16. Gross Thermal Generation (MWh 2165688.0 6810552 141080833 L 17. Gross Electrical Generation (MWh) 734140.0 2305680 47304010 1 18. Net Electrical Generation (MWh) 716398.0 2250031 45128658 i 19. Unit Service Factor 94.1 97.0 61.8  ;
20. Unit Availability Factor 94.1 97.0 61.8 l 21. Unit Capacity Factor (MDC Nst) 90.4 96.7 55.6 4
22. Unit capacity Factor (DER net' , 90.4 96.7 55.6
j. 23. Unit Forced Outage Rate 5.9 3.0 20.6

. 24. Shutdowns. Scheduled Ovtr 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 4

. Excludes hours under administrative hold

.(June 1,-1985,to November 19, 1995)

. . - . - ,, c - , , . . ,.- -

. _. - . _ . . . - . . __. - ~ - _ - . - ~ _ . - _ _ - - - - - - . - - - - _ . - _ - > - - - . . - - ' - ~ ~ -- - - - -.

r 1 .

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-296 REPORT MONTH: FEBRUARY 1996

  • UNIT: BROWNS FERRY 3
  • i 4

PREPARED BY: J. W. Davenport j 4

TELEPHONE. (205) ~129-2690 I

i I

stethod of License  ;

i Duration Shuttine Event System Component Cause and Corrective Action to Prevent I too. Date Type' (elours) Reason

  • Doun Reactor
  • Report No. Code
  • Code' Recurrence
  • i 1 02/29/% F 22 A 3 296/96001 JJ CNV A failed turbine speed fee 6 ack card in the Electro-Nydrautic Control system caused  ;

fluctuations in the turbine control and >

bypass vatwes. This caused a reactor i pressure spike, d ich in turn caused an I Average Pouer Range Stonitor high flun spike ,

that screened the reactor. [

t t

t i

l t t

  • Revised to correct Report stanth from movember 1996 to February 1996 1 -

m i

! 'f-Forced .-E pipment Failure (Emptain) blethod: ' Instructions for Preparation of Licensee S-Scheduled g-plaintenance or Test 1-planual Event Reports (muREG-1022)

C-Refueting 2-stanuat Scram r D-Regutstory Restriction 3-Automatic Scram E-Operator Training and License Enemination 4-Continuation of Existing Outage i i F- Administrative 5-Reduction i G-Operational Error (Emplain) 9-Other M-Other (Emplain)

I I

t i  :

l

=_= _ _ _ _ _ - _ _ _ _ _ _ .. - . . - - . . - .

Retrieved from "https://kanterella.com/w/index.php?title=ML20107G025&oldid=2797108"