ML20107G025
| ML20107G025 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| 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) | |
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
)
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 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 1996 Monthly Operating Report.
If you have any questions, please call me at (205) 729-2636.
Sin e
W Pedro Salas Manager of Site Licensing Enclosure cc:
See page 2 9604230077 960331 PDR ADOCK 05000259 R
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- U.S. Nuclear Regulatory Commission Page 2
-April 15,-1996
' 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 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
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Ms. Elizabeth Hannon
-Utility Data Institute 1200 G Street, NW Washington, D.C.
20005-3802 1
1 4
ENCLOSURE 4
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2,
AND 3 I
MONTHLY OPERATING REPORT MARCH 1996 j
(SEE ATTACHED)
J.
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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 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 4
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
12 0
27 0
13 0
28 0
14 0
29 0
15 0
30 0
31 0
i 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 1
3 Systep Cqt Cause and Corrective Action to Prevent No.
Date Type (Hours)
Reason Down Reactor 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 I
2 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)
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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
i.
i Method of License Duration Shutting Event Systy C
t Cause and Corrective Action to Prevent I
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.
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F-Forced k-Equipment Failure (Explain) hethod:
bnstructionsforPreparationofLicensee
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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
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H-Other (Explain) l I
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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 9
3 Systep Cgt Cause and Corrective Action to Prevent No.
Date Type (Hours)
Reason Down Reactor 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 k-EquipmentFailure(Explain) hethod:
knstructionsforPreparationofLicensee IF-Forced 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
.. -. _ ~
. - - - ~ _. _-.-
DOCKET:
50-259 l
. UNIT:
BROWNS FERRY 1 i
PREPARED BY:
J.
W.
Davenport TELEPHONE:
(205) 729-2690 r
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 f
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0
- 16. Gross Thermal Generation (MWh) 1462392.0 6028824 265369156
- 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
- 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 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
- 22. Unit capacity Factor (DER net' 90.4 96.7 55.6 4
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
.. -.. __. - ~ - _ -. - ~ _. - _ _ - - - - - -.
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1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-296 REPORT MONTH:
FEBRUARY 1996
- UNIT: BROWNS FERRY 3 i
PREPARED BY:
J.
W.
Davenport j
4 TELEPHONE.
(205) ~129-2690 4
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.
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F L
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- Revised to correct Report stanth from movember 1996 to February 1996 P
1 m
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'f-Forced
.-E pipment Failure (Emptain) blethod:
' Instructions for Preparation of Licensee i
S-Scheduled g-plaintenance or Test 1-planual Event Reports (muREG-1022)
[
C-Refueting 2-stanuat Scram r
D-Regutstory Restriction 3-Automatic Scram i
E-Operator Training and License Enemination 4-Continuation of Existing Outage i
i F-Administrative 5-Reduction l
i G-Operational Error (Emplain) 9-Other M-Other (Emplain)
I I
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i l
.