ML20045H391
| ML20045H391 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1993 |
| From: | Ratliff S, Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9307200161 | |
| Download: ML20045H391 (13) | |
Text
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4 A
knrent;e Valley Astrori y. Post Offico Box 2000. Decatar. A:abama 35609 f
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'i JUL 151993 l
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 JUNE 1993 In accordance with the requirements of the BFN Technical <
i Specifications section 6.9.1.3, the Monthly operating Report.
i for the month of June 1993 is provided in the enclosure.
If you have any questions, please telephone me'at (205).729-7566.
Sincerely, r-a
/
edro S s
i Manager of Site Licensing Enclosure cc:
See page 2
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9307200161 930630 ADOCK_05000259 j
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2 U.S.
Nuclear Regulatory Commission JUL 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 Route 12, Box 637
}
Athens, Alabama 35611
~
Regional Administrator j
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 h
MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY JUNE 1993 o
DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR j I
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OPERATIONAL
SUMMARY
JUNE 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 one effective June 1, 1985.
Administrative hold status is considered by TVA to suspend the accrual of reporting period hours, because this unit is l
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 variables accordingly.
UNIT 2 Unit 2 resumed power operations following completion of the Cycle 6 refueling outage.. The unit was manually scrammed on June 3, 1993, as part of the Power Ascension Test Program (PATP).
The PATP was completed and on June 19, 1993, the unit achieved 100 percent power.
UNIT 3 Unit 3 remains on administrative hold to resolve various TVA and-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, because 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 variables accordingly.
i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-260 UNIT:
TWO PREPARED BY S.
A. Ratliff TELEPHONE:
f205) 729-2927 MONTH JUNE 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net)
(Mwe-Net).
1 0
17 712 1
2 27 18 810 3
0 19 1031 4
266 20 1044 5
303 21 1057 6
357 22
'1053 7
468 23 1057 8
535 2'4 1053 P
9 841 25 1065 10 876 26 1040 11 977 27 1064 i
12 1045 28 1058
{
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13 1024 29 1060
+
14 1031 30 1056 l
15 1042 16 735 I
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l AVERAGE DAILY UNIT POWER LEVEL DOCKET NOz.
~50-259 f
UNIT:
ONE PREPARED BY:
S.
A.
Ratliff j
' TELEPHONES. (205) 729-2937 MONTH JUNE 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY.. POWER' LEVEL
[
(Mwe-Net)
(Mwe-Net).
j 1
0 17 0
2 0
18 O'
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
r 13 0
29 0
14 0
30 0
15 0
1 16 0
i
.sJ r >
e
1 4
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-296 UNIT:
Three PREPARED BY:
S.
A.
Ratliff TELEPHONE:
(205) 729-2937 t
MONTH JUNE 1993
.t 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
i 12 0
28 0
13 0
29 0
14 0
30 0
[
15 0
16 0
i 8
i j
D DOCKET NO:
50-259 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
One REPORT MONTH:
JUNE 1993 P
( b5 Method of License Cause ard Corrective Duration Shutting Event System Component Action to Prevent No.
Date Type' (Hours)
Reason' Down Reactor
- Report No.
Code' Code' Recurrr.ce 315 06/01/85 N/A 720 F
4 Adninistrative hoto to resolve various TVA and NRC concerns.
l l
'F:
Forced
' Reason:
' Method:
' Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction Continuation of Existing Outage (NUREG-061)
E-Operator Training and License Examination 5-Redixtion F-Achinistrative '
9-Other G-Operational Error (Explain)
' Exhibit I-Same Source H-Other (Explain) m,. ~
. _. ~ -.. ~.,.
. J
DOCKET Noi 50-260 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT hAME:
two PREPARED BY:
S. A. Ratliff REPORT MONTH:
JUNE 1993 TELEPHONE: (205) 739-2937 Method of License cause and Corrective Duration Shutting Event System Component Action to Prevent No.
Date Type' (Hours)
Reason' Down Reactor' Report No.
Code' Code' Rect arrence 1
01/29/93 5
39.4 C
4 REFUELING OUTAGE 2
06/02/93 S
23.7 B
1 POWER ASCENSION TESTING PROGRAM
'F:
Forced Reason:
Method:
" Exhibit G-Instructions S:. Scheduled
'A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-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 5-Reduction F-Administrative 9-Other G-Operational Error (Explain)
' Exhibit 1-Same Source H-Other (Explain) a
DOCKET NO:
50-296 UNIT SHUTDOWNS AMD POWER REDUCTIONS UNIT NAME:
79tece PREPARED BY:
S. A. Rattiff REPORT MONTH:
JUNE 1993 TELEPHONE: (205) 739-2937 Method of License Cause aruf Corrective Duration Shutting Event.
System Conponent Action to Prevent No.
Date Type' (Hours)
Reason
- Down Reactor
- Report No.
Code' Code' Recurrence 315 06/01/85 N/A 7Z0 F
4 Adninistrative hold to resolve various TVA and hRC concerns.
i l
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' F: Forced
- Reason:
' Method:
'* Exhibit'G-Instructions I
S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data j
B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee
(
C-Refueling 3-Automatic Scram Event Report (LER) File i
D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-061)
E-Operator. Training and License Examination 5-Reduction F-Administrative 9-Other G-Operational Error (Explain).
- Exhibit I-Same Source H-Other (Explain) i l-y a
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i OPERATING DATA REPORT DOCKET NO.
50-259 PREPARED BY' S.A.RATLIFF TELEPHONE 205-729-2937 OPERATING STATUS
- 1. Unit Names BROWNS FERRY UNIT ONE
- 2. Reporting period: JUNE 1993
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electric 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 hold THIS YEAR-TO HONTH DATE CUMULATIVE *
- 11. Hours In Reporting Period-0.0 0
95743
- 12. Hours Reactor Was critical 0.0 0
59521
- 13. Reactor Reserve Shutdown Hours 0.0 0
6997
- 14. Hours Generator On Line 0.0 0
58267
- 15. Unit Reserve Shutdown Hours 0.0 0
0 1
- 16. Gross Thermal Generation (MWh) 0.0 0
168066787
.]
- 17. Gross Electric Generation (MWh) 0.0 0
55398130
- 18. Net Electric Generation (MWh) 0.0 0
53796427
- 19. Unit Service Factor 0.0 0.0 60.9
- 20. Unit Availability Factor 0.0 0.0 60.9
,]
- 21. Unit Capacity Factor (MDC Net) 0.0 0.0 52.8
- 22. Unit capacity-Factor'(DER. Net) 0.0 0.0 52.8
- 23. Unit Forced Outage Rate-0.0 0.0 25.6
.i
- 24. Shutdowns Scheduled Cver Next 6 Months (Type, Date, and Duration of Each):
]
- 25. If Shut Down At End Of Reporting Period, Estimated Date Of Startup: To be determined
- Excludes hours under administrative hold m
m
-u
OPERATING DATA REPORT' DOCKET NO.
50-260 PREPARED BY S.A.RATLIFF TELEPHONE 205-729-2937 OPERATING STATUS
- 1. Unit Name: BROWNS FERRY UNIT TWO
- 2. Reporting period: JUNE 1993
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electric 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:
"/A THIS YEAR-TO MONTH DATE CUMULATIVE *
- 11. Hours In Reporting Period 720.0 4343 108894
- 12. Hours Reactor Was Critical 712.9 1437 70400 s
- 13. Reactor Reserve Shutdown Hours 0.0 0
14200
- 14. Hours Generator On Line 656.9 1337 68208
- 15. Unit Reserve Shutdown Hours 0.0 0
0
- 16. Gross. Thermal Generation (MWh) 1830679.8 3363341 194091993
- 17. Gross Electric Generation (MWh) 584210.0 1085940 64363588
- 18. Net Electric Generation (MWh) 567975.0 1s51526 62519346
- 19. Unit Service Factor 91.2 30.8 62.6
- 20. Unit Availability Factor 91.2 30.8 62.6
- 21. Unit capacity Factor (MDC Net) 74.1 22.7 53.9
- 22. Unit capacity Factor (DER Net) 74.1 22.7 53.9
- 23. Unit Forced Outage Rate 0.0 0.0 19.5
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None
- 25. If 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)
a OPERATING DATA REPORT DOCKET NO.
50-296-PREPARED BY S.A.RATLIFF TELEPHONE 205-729-2937 s
OPERATIhG STATUS
- 1. Unit Names BROWNS FERRY UNIT THREE
- 2. Reporting period: JUNE 1993
- 3. Licensed Thermal Power (MWt): 3293
- 4. Nameplate Rating (Gross MWe): 1152
- 5. Design Electric Rating (Net MWe): 1065
- 6. Maximum Dependable Capacity (Gross MWe): 0
- 7. Maximum Dependable Capacit, (Net MWe): 0 8.
If Changes occur in capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason: N/A
- 9. Powiar Level To which Restricted, If Any (Net MWe): 0
- 10. Reason For Restrictions, If Any: Administrative hold THIS YEAR-TO MONTH DATE CUMULATIVE *
- 11. Hours In Reporting Period 0.0 0
73055
- 12. Hours Reactor Was Critical 0.0 0
45306
- 13. Reactor Reserve Shutdown Hours 0.0 0
5150
- 14. Hours Generator On Line 0.0 0
44195
- 15. Unit Reserve Shutdowa Hours 0.0 0
0
- 16. Gross Thermal Generation'(MWh) 0.0 0
131868267
- 17. Gross Electric Generation (MWh) 0.0 0
43473760
- 18. Net Electric Generation (MWh) 0.0 0
42114009
- 19. Unit Service Factor 0.0 0.0 60.5
- 20. Unit Availability Factor 0.0 0.0 60.5
- 21. Unit Capacity Factor (MDC Net) 0.0 0.0 54.2
- 22. Unit Capacity Factor (DER Net) 0.0 0.0 54.2
- 23. Unit Forced Outage Rate-0.0 0.0 21.6
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25.'If Shut Down At End Of Reporting Period, Estimated Date Of Startup To be determined
- Excludes hours under administrative hold 1
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