ML20069C466
| ML20069C466 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/1994 |
| From: | Salas P, Tanya Smith TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9406010286 | |
| Download: ML20069C466 (13) | |
Text
.
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A Annessee Valley Authority. Post Ofnce Box 2000. Decatur. Alabama 35609 MEN 131994 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 APRIL 1994 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 April 1994 in the enclosure.
If you have any questions, please telephone me at (205) 729-2636.
Sincerely,
.V Pedro Salas Manager of Site Licensing Enclosure cc:
See page 2 i
9406010286 940430 qt PDR ADOCK 05000259
/-
PDR R
~ UGVUUJ_
~
e l
U.S.' Nuclear Regulatory Commission-Page 2-MAY-131994 i
Enclosure cc. '(Enclosure) :
Mr. Mark'S. Lesser, Section Chief-
'U.S.
Nuclear Regulatory Commission r
(
-Region II-l
_101 Marietta' Street, NW, Suite 2900 l
Atlanta, Georgia 30323 i
Hebdon,5 Director l
Mr.. Frederick'J.
[
Project Directorate II-4 l
Division of-Reactor Projects I-II Office of Nuclear Reactor i
Regulation, Mail 13 H3 Washington, D.C.
20555.
-1 INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GeorgiaL 30389 Mr. Ted'Martson, Director Electric Power Research Institute P.
O.
Box 10412
{
Palo. Alto,' California' 94304 NRC Resident Inspector-Browns Ferry Nuclear Plant Route 12, Box 637 Athens,' Alabama 35611
.l l
Regional Administrator L
U.S.-Nuclear Regulatory Commission j
Region II' l
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia' 30323 Mr. Fred Yost, Director of Research l
Utility Data Institute l
1200 G Street, NW Washington, D.C.
20005-3802 i
[,
ENCLOSURE l
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2,'AND 3 MONTHLY OPERATING REPORT l
APRIL 1994 L
I 1
1 I
l
l l'
OPERATIONAL
SUMMARY
APRIL 1994 l
t HEOWNS 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 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 j
During the month of April, Unit 2 operated at a capacity factor of 77.9 percent and generated 612,580 megawatt hours gross electrical power.
Unit 2 operated continuously from April 1 to April 15, when Unit 2 automatically scrammed from approximately l
100 percent power on low scram air header pressure.
The l
automatic scram ended Unit 2's record continuous run'at 315 days.
During return to service following-the scram,. Unit 2 automatically scrammed a second time on April 18 when the main steam isolation valves closed due to low reactor pressure following the spurious opening of the turbine bypass valves.
l Unit 2 returned to service on April 20 and reached 100 percent power on April 22.
Unit 2 operated continuously the remainder of the month.
F BROWNS FERRY 3 l
l
(
Unit 3 remains shutdown on administrative hold to resolve various TVA and NRC concerns.
Unit 3 has been on administrative hold since June 1, 1985.
As a result, TVA considers that accrual of I
reporting hours is suspended since the unit has a maximum L
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.
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N-e-ai-
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-259 UNIT BROWNS FERRY 1'
)
PREPARED BY:
T.
R.
Smith l
TELEPHONE:
(205) 729-2951 MONTH April 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
16 0
l 2
0 17 0
I 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
l
\\
l 4
l l
\\
1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-260 UNIT:
BROWNS FERRY 2 PREPARED BY:
T. R.
Smith TELEPHONE:
(205) 729-2955 MONTH Aoril 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1085 16 0
2 1093 17 0
3 1045 18 0
l 4
1092 19 0
5 1083 20 0
l l
6 1074 21 250 7
1091 22 832 8
1089 23 1001 9
1983 24 1083 10 1089 25 1085 l
l' 1088 26 1084 12 1085 27 1084 13 1086 28 1084 14 1081 29 1081 15 98 30 1073
]
l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-296 UNIT: BROWNS FERRY 3 PREPARED BY:
T.
R.
Smith TELEPHONE:
(205) 729-2955 MONTH April 1994 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
I l
1 l
l
I UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-259 REPORT MONTH:
April 1994 UNIT: BROWNS FERRY l PREPARED BY:
T.
R.
Smith TELEPHONE:
i2051 729-2955 Method of License Duration Shutting Event System Component Cause and Corrective Action to Prevent Wo.
Date Type' (Hours)
Reason:
Down Reactor' Report No.
Code' Code' Recurrence 1
06/01/85 S
719 F
4 Adninistrative held to resolve various TVA and NRC concerns.
'F-Forced
'A-Equipment Failure (Explain)
' Method:
' Instructions for Preparation of Licensee 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 ard License Examination 4-Continuation of Existing Outage F-Adninistrative 5-Reduction G-Operational Error (Explain) 9-Other H-Other (Explain)
1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-260 REPORT MONTH:
April 1994 UNIT:
BROWNS FERRY 2 PREPARED BY:
T.
R.
Smith TELEPHONE:
1205) 729-2955 Method of License Duration Shutting Event System Corrponent Cause and Corrective Action to Prevent No.
Date Type' (Hours)
Reason #
Down Reactor' Report No.
Code
- Code
- Recurrence 1
4/15/94 F
146 B
3 260/94004, During planned maintenance activities on the and scram pilot air header, Unit 2 automatically 260/94005 scrammed on low scram air header pressure following isolation of both primary and secondary scram pilot air header pressure regulators. Corrective actions include personnel corrective actions and additional controls for certain maintenance activities.
During return to service, Unit 2 automatically scrammed a second time on 4/18/94 when the main steam isolation valves closed following spurious opening of the turbine bypass valves due to trinown cause.
Corrective actions being developed for this latter event.
'F-Forced
'A-Equipment Failure (Explain)
' Method:
- Instructions for Preparation of Licensee 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-Adninistrative
'5-Reduction G-Operational Error (Explain) 9-Other H-Other (Explain) l l
i
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-296
~
REPORT MONTH:
April 1994 UNIT: BROWNS FERRY 3 PREPARED BY:
T.
R.
Smith TELEPHONE:
(205) 729-2955 Method of License Duration Shutting Event System Conponent Cause and Corrective Action to Prevent No.
Date Type' (Hours)
Reason' Down Reactor Report No.
Code' Code
- Recurrence 3
1 06/01/85 S
719 F
4 A&inistrative hold to resolve various TVA and NRC concerns.
'F-Forced A-Equipment Failure (Explain)
- Method:
" Instructions for Preparation of Licensee S-Scheduled B-Maintenance or Test 1-Manual Event Reports (NUREG-1022)
C-Refueling 2-Manual Scram D-Regulatory Restriction 3-Automatic Svam '
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)
D
OPERATING DATA REPORT DOCKET:
50-259 UNIT:
BROWNS FERRY 1 PREPARED BY:
T.
R.
SMITH TELEPHONE:
(205) 729-2955 l
OPERATING STATUS
- 1. Unit Names BROWNS FERRY UNIT 1
- 2. Reporting Period: APRIL 1994 1
- 3. Licensed Thermal Power (MWt):
3293 j
- 4. Nameplate Rating (Gross MWe):
1152
- 5. Design Electrical Rating (Net MWo):
10G5
- 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 Hold THIS MONTH YEAR TO DATE CUMULATIVE *
- 11. Hours in Reporting Period 0
0 95743
- 12. Hours Reactor Was Critical 0
0 59521
- 13. Reactor Reserve Shutdown Houre 0
0 6997
- 14. Hours Generator On Line 0
0 58267
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Generation (HWh) 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 j
- 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 i
l l
l Excludes hours under administrative hold l
(June 1, 1985 to present) l
i 4
OPERATING DATA REPORT DOCKET:
50-260 UNIT:
BPOWNS FERRY 2 j
PREPARED BY:
T.
R.
SMITH TELEPHONE:
(205) 729-2955 OPERATING STATUS
- 1. Unit Names BROWNS FERRY UNIT 2
- 2. Reporting Period: APRIL 1994
- 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 l
- 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 719 2879 116190
- 12. Hours Reactor Was critical 584 2744 77561
- 13. Reactor Reserve Shutdown Hours 0
0 14200
- 14. Hours Generator On Line 573 2733 75358
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Generation (MWh) 1820291 8818575 217366175
- 17. Gross Electrical Generation (MWh) 612580 2983360 72191278
- 18. Net Electrical Generation (MWh) 596521 2913079 70157741
- 19. Unit Service Factor 79.7 94.9 64.9
- 20. Unit Availability Factor 79.7 94.9 64.9
- 21. Unit Capacity Factor (MDC Net) 77.9 95.0 56.7
- 22. Unit Capacity Factor (DER net) 77.9 95.0 56.7
- 23. Unit Forced Outage Rate 20.3 5.1 18.1
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Cycle 7 refueling outage schede'ed to begin October 1, 1994, and currently scheduled for a 37 to 44-day duration.
- 25. If Shut Down At End Of Reporting Period, Estimated Date of Startup N/A l
- Excludes hours under administrative hold (June 1, 1985 to May 24, 1991)
4 i
l 1
j OPERATING DATA REPORT l
DOCKET:
50-296 l
UNIT:
BROWNS FERRY 3 l
PRE?ARED BY:
T.
R.
SMITH TELEPHONE:
(205) 729-2955
?
k*'
OPERATING STATUS i
- 1. Unit Names BROWNS FERRY' UNIT 3 i
d l
- 2. Reporting Period: APRIL 1994
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe):
1152 1
I 5.
Design Electrical Rating (Net MWe):
1065 I
}
- 6. Maximum Dependable Capacity (Gross MWe):
0 j
- 7. Maximum Dependable Capacity (Net MWe):
O
]
- 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 1
3 i
2 THIS MONTH YEAR TO DATE ' CUMULATIVE *
- 11. Hours in Reporting Period 0
0 73055 1
- 12. Hours Reactor Was Critical 0
0' 45306
- 13. Reactor Reserve Shutdown Hours 0
0 5150
- 14. Hours Generator On-Line 0
0 44195 1
5'
- 15. Unit Reserve Shutdown Hours 0
0-0 k
- 16. Gross Thermal Generation-(MWh)
O
_0 131868267 f
1
- 17. Gross' Electrical Ger. ration (MWh) 0 0
43473760 i
- 18. Het Electrical Generation (MWh) 0 0
42114009
?
- 19. Unit Service Factor
.0 0
60.5
- 20. Unit Availability Factor O.
0 60.5 j
3 i
- 21. Unit Capacity Factor (MDC Net) 0 0
54.2 j
- 22. Unit Capacity Factor (DER net) 0 0
54.2 j
- 23. Unit Forced Outage Rate 0
0 21.6 1
4
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):' N/A
- 25. If Shut Down At End Of Reporting Period,
)
s Estimated Date of Startup: To be determined 1
f
- Excludes hours under administrative hold (June 1, 1985 to present) i l
-