ML20236S165
| ML20236S165 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/31/1987 |
| From: | Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8711240262 | |
| Download: ML20236S165 (14) | |
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TENNESSEEVALLEhAUTHORITY OFFICE OF. NUCLEAR POWER
' BROWNS FERRY NUCLEAR PLANT:
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MONTHLY OPERATING REPORT TO NRC-I October 1, 1987:- October'31,' 1987' 1
r DOCKET NUMBERS 50-259. 50-260,'AND 50-296:
LICENSE NUMBERS DPR-33 DPR-52, AND DPR-68 l
l
- 1 Submitted by:
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- Plant' Manager 1d l
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PDR ADOCK 05000259 "
h' 8711240262 871031 PDR R
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-1 CONTENTS operations summary......
,............ :...............-..~1~
Refueling Information.
.....,..:... '...:..... 3
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l Significant operational' Events.......
'S V-Operating Data Report.,.. '.........
-..........:.......-6 Average Daily Unit Power Level. -. '.......'...:...'..
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9'
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Unit Shutdowns and Power Reductions.,.'.,.'.. '.......
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Operations Summary October 1987 The following summary describes the significant operation activities during the reporting period.
In support of this summary, a chronological log of i
significant events is included in this report.
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l There were nine reportable occurrences and two revisions to previous
)
occurrences reported to NRC during the month.
Unit 1 The unit remained on administrative hold the entire month. The unit is also 1
i undergoing its end-of-cycle 6 refueling.
l 1
Unit 2 The unit remained on administrative hold the entire month.
The unit is also l
undergoing its end-of-cycle 5 refueling.
Unit 3 i
i The unit remained on administrative hold the entire month. The unit is also l
undergoing environmental qualifications to comply with NRC requirements.
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8 1
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l Operations Summary (Continued)
October 1987 4
1 i
1 Fatigue Usage Evaluation The cumulative usage factors for the reactor vessel'are'as follows:
Location Usage Factor-Unit 1 Unit 2 Unit 3-1 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle-0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629-0.14360 l
I NOTE: This accumulated monthly information satisfies Technical I
Specification Section 6.6.A.17.b(3) reporting requirements.
. I Common System Approximately 6.86E+05 gallons of waste liquids were discharged containing approximately 5.02E-02 curies of activity.
l 6
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I 2'
Refueling Information October 1987 Unit 1 Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns.
The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date to be determined. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 1 items are environmental qualification of electrical equipment (10CFR50.49), torus modification (NUREG 0661). containment modifications l
(NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifications, j
modification of masonry walls (IEB 80-11), evaluation of the vent drain and test
)
l connections, VDTC, (LER 82020), valve modification (Appendix J), HPCI concerns,
)
modification of PCIS logic (LER 259/85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident i
evaluation (NUREG 0737), RPS modifications (IE Notice 78-45), H0 sample 1
22 l
line modification (LER 81050), radiation monitors modification (LER 80033), EECW carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which are scheduled for next outage.
There are 0 assemblies in the reactor vessel.
The spent fuel storage pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, l
232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present evallable capacity of the fuel pool is 1355 locations.
Unit 2 Unit 2 was shut down on September 15. 1984, for its fifth refueling outage with a scheduled restart date to be determined.
On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns.
The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.
l The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB 80-17),
environmental qualification of electrical equipment'(10CFR50.49), torus modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial), MSIV modifications, modification of I
masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J) (partial), D/G speed sensor l
l k
l 3
I 1
Refueling. Information October 1987 Unit 2 (Continued) installation (LER 81004), HPCI and RCIC testable check valve change out, modification of PCIS logic (LER 259/85009), HPCI concerns, seismic program review, and EECW carbon to stainless pipe change out.
There are 0 assemblies in the reactor vessel. At month end there were 304 l
new assemblies, 764 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 1481 locations. All HDRs have been installed in the pool l
with the exception of two.
Unit 3 I
Unit 3 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be i
i 1
determined.
The sixth refueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modification. The prior-to-startup unit 3 items are environmental qualifica-tion of electrical equipment (10CFR50.49), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-j tions, modification of masonry walls (IEB 80-11), evaluation of the vent drain l
and test connections, VDTC, (LER 82020), valve modifications (Appendix J), HPCI 1
concerns, replacement of plant process computer, seismic qualifications of l
piping (IEB 79-02/14), poetaccident evaluation (NUREG 0737), addition of redundant drywell control air supply, RPS modification (IE Notice 78-45),
H0 sample line modification (LER 81050), radiation monitor modification (LER.80033), replacement of jet p:.mtp holddown beam assemblies (IEB 80-07),
change out of switches in SBGT (LER 83018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.
There are 0 assemblies in the reactor vessel.
There are 764 assemblies to finish cycle 6, 248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent fuel storage pool.
The present available capacity of the fuel pool is 585 locations. All high density racks (HDR) have been installed in the pool with the exception of six.
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Significant Operational Events October 1987
-i Unit 1 0
10/01/87 0001 Unit remains on administrative hold to resolve various
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TVA and NRC concerns, and end of cycle 6 refueling andi modifications continues.
10/31/87
'2400 Unit remains on administrative hold.to resolve various j
TVA and NRC concerns,-and end of cycle 6 refueling and modifications continues.
Unit 2 10/01/87 0001 Unit remains on administrative hold to resolve various TVA'and NF3 concerns, and end of cycle 5 refueling and.
- 1 modifications continues.
10/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling'and modifications continues.
Unit 3 l
10/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
10/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental. qualifications and modifications continues.
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1
e OPERATING DATA REPORT DOCKET NO. 50-259 DATEJ 11-01-87 COMPLETED BY J. D. Crawford TELEPHONE.(205) 729-2507 OPERATING STATUS l Notes l.
l.
Unit Nano:
Browns Ferry Unit One l
l.
2.
Reporting Period: October 1987 l-l-
3.
Licensed Thermal Power (MWt): _3293 -
l l
4.
Nameplate Rating (Gross MWe): 1852 l
l 5.
Design Electrical Rating (Not MWe) 1065 l
l 6.
Maxinun Dependable Capacity (Gross MWe) 1098.4 l
.l l
7.
Maximum Dependable Capacity (Not MWe) 1065 l-l 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
NlA l
l 9.
Power Level To Which Restricted, if Any (Not MWe):'
NlA
- 10. Reasons For Restrictions, if Any:
NlA This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 745 7296 116.216
- 12. Number of Hours Reactor Was Critical 0
0 59 521.38 3
- 13. Reactor Reserve Shutdown Hours 0
0 6.997.44'
- 14. Hours Generator On-Line 0
0 58.267.26
~~
- 15. Unit Reserve Shutdo.an Hours 0
0 0
- 16. Cross Thermal Energy Generated (MWH) 0 0
168.066.797
- 17. Gross Electrical Enorgy Gonorated (MWH) 0 0
'55.398.830 j
- 18. Net Electrical Energy Generated (MWH)
-719
-12.787 53.707.848
{
- 19. Unit Service Factor 0
0 50.14
]
- 20. Unit Availability Factor 0
0 50.14
- 21. Unit Capacity Factor (Using MOC Net) 0 0
43.39
- 22. Unit Capacity Factor (Using DER Net) 0 0
43.39
- 23. Unit Forced Outage Rate 100 100 40.24-
- 24. Shutdowns Scheduled Ovsr Next 6 Months (Type, Date, and Duration of Each).
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup' To be determined
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY INITIAL ELECTRICITY
.j COMMERCIAL OPERAT10N (9l77) i 6
I 1
OPERATING DATA REPORT DOCKET NO.
50 260 DATE l l 87 COMPLETED BY J. D. Crawford TELEPHOWE T205) 729-2507
,0PERATING STATUS l Notes l
1.
Unit bme:
Browns Ferry Unit Two l
l 2.
Reporting Period:_ October 1987 l
l 3.
Licensed Thermal Power (MWt): 3293 l
l 4.
Nameplate Rating (Gross We): 1852 l
l 5.
Design Electrical Rating (Net We) 1065 l
l 6.
Maximum Dopendable Capacity (Gross MWe) 1098.4 l
l 7.
Maximum Dependable Capacity (Net MWe) 1065 l
l 8.
If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since Last Report, Give Reasons:
NlA j
i 9.
Power Level To Which Restricted, if Any (Net HWe):
NlA j
- 10. Reasons for Restrictions, if Any:
NlA
/
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 745 72 %
111.103
- 12. Number of Hours Reactor Was Critical 0
0 55.860.03
- 13. Reactor Reserve Shutdown Hours 0
0 14.200.44
- 14. Hours Generator On-Lins
_ 0 0
54.338.36
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWI) 0 0
153,245.167
- 17. Gross Electrical Energy Generated (MWH) 0 0
50.771.798
- 18. Not Electrical Energy Gonorated (MWH)
-5,017
-29.307 49.188.996 i
- 19. Unit Service Factor 0
0 48.91
- 20. Unit Availability Factor 0
0 48.91
- 21. Unit Capacity Factor (Using MDC Net) 0 0
41.57
- 22. Unit Capacity Factor (Using DER Net) 0 0
41.57
- 23. Unit Forced Outage Rate 100 100 39.28
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
1
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Comercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY ComERCIAL OPERATION (9]77) 7
I OPERATING DATA REPORT i
i DOCKET NO.
50-2 %
DATE 11-08-87 C0ffLETED BY J. D. Crawford TELEPHONE (205) 7z9-7507
.]
OPERATING STATUS l Notes l
1.
Unit Names Browns Ferry Unit Three l
l
- 2.. Reporting Period:_ october 1987 l-l 3.
Licensed Thennal Power (MWt): 3293 l'
l.
4.
Nameplate Rating (Gross MWe):' 1152 l
l
.)
5.
Design Electrical Rating (Not MWe) 1065 l
l 6.
Maximum Dependable capacity (Gross MWe) 1098.4
'l l
7.
Maximum Dependable Capacity (Not MWe)-
1065 l
l 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
i NlA'
~
)
\\
9.
Power Level To Which Restricted, if Any (Net MWe):
NIA j
- 10. Reasons For Restrictions, if Any:
NlA j
i
'I i
This Month Yr-to-Date Cumulative ll. Hours In Reporting Period 745 72 %
93.528
- 12. Number of Hours Reactor Was Critical 0
0 45.306.08
- 13. Reactor P,oserve Shutdown Hours 0
0 5.139.55
]
- 14. Hours Generator On-line 0
0
_ 44.194.76 j
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thennal Energy Generated (MWH) 0 0
_131.868.267
- 17. Gross Electrical Energy Generated (MWH) 0 0
43.473.760
- 18. Net Electrical Energy Generated (MM1)
-4,217
-42.569 47.049.559
- 19. Unit Service Factor 0
0
.47.25
- 20. Unit Availability Factor 0
0 47.25
- 21. Unit Capacity Factor (Using MDC Net) 0
'O 42.22
- 22. Unit Capacity Factor (Using DER Net) 0 0
42.22 J
- 23. Unit forced Outage Rate 100 100 42.47
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast-Achieved INITIAL CRITICALITY INITIAL ELECTRICITY l
COP 9fERCIAL OPERATION (9l77) l 1
8
1 l
'l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 Unit one DATE
__11-01-87 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH OCTOBER 1987 DAY AVERAGE DATLY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1
-1 17
-1 2
-1 18
-I 3
-1 19
-1 4
-1 20
-1 5
-1 21
-1 l
6
-1 22
-1 1
7
-1 23
-1 8
-1 24
-1 9
-1 25
-1 1
10
-1 26
-1 i
i 11
-1 27
-1
]
12
-1 28
-1 13
-1 29
-1 14
-1 30
-1 15
-1 31
-1 16
-1 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) 9
___ _ _ a
' AVERAGE DAILY UNIT POWER LEVEL DOCKET-NO.
50-260
Unit-
'Two-DATE'-
11-01-87 COMPLETED BY.
J.D. Crawford
' TELEPHONE (205)729-2507 MONTH.
OCTOBER 1987 DAY AVERAGE DAILY' POWER LEVEL DAY
- AVERAGE DAILY, POWER LEVEL-(MWe-Net)
(MWe-Net)-
1
-7 17
-6 2
-7
'18
-6 3 19
-7' 4
-7 20- 5
-6 21.
16 6
-7 22
-7 7
-7 23
-7 8
-7 24
-7 9
-7 25 10
-7 26
-7 11
-6 27-
-7 12
-6 28
-6 13
-7 29
-7 14
-7 30
-7 15
-7 31
-8 16
-7 INSTRUCTIONS on this format, list the average daily unit power level in MWe-Net'for each day'in the reporting month. Compute to the nearest whole megawatt.'
_9/77)
(
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i
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AVERAGE DAILY UNIT POWER LEVEL'
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DOCKET'NO.
50-296 Unit Three
.I I
DATE-11-01-87 COMPLETED BY J.D. Crawford
.j (205'729-2507
}
TELEPHONE
)
MONTH OCTOBER 1987 DAY AVERI(3 DAILY POWER LEVEL DAY-AVERACE DAILY POWER LEVEL (MWe-Net)
(MWe-Net)l
- j 1
-6 17
-5 2
-6 18
-5 3
-6 19'
-5 l
l 4
-6 20
-6 1
1 5
-5 21
-6
)
6
-6 22
-5 l
7
-6 23
-5 8
-6 24
-5 1
9
-6 25-
-6 10
-6 26
-6 11
-6 27
'5 12
-6 28
-5 1
13
-6 29
-6 il 14
-5 30
-6 l
1 15
-5 31 ;
16
-5
'l INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
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(9//7) 1 11 i.
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TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER
.1 1
l BROWNS FERRY NUCLEAR PLANT l
i MONTHLY OPERATING REPORT TO NRC
]
October 1, 1987.- October 31, 1987 q
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l l-DOCKET NUMBERS 50-259, 50-260, AND 50-296
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LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l
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l Submitted by:
Plant Manager i
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CONTENTS i
Operations' Summary.
7......' 1 '
1 Refueling Information.
.:.....'3 Significant Operational Events..
.....5 Operating Data Report.
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l Average Daily Unit Power Level.......
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Unit Shutdowns and Power Reductions.
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j Operations Summary October 1987 The following summary describes the significant operation. activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
l There were nine reportable occurrences and two revisions to previous i
occurrences reported to NRC during the month.
l Unit 1 1
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The unit remained on administrative hold the entire month. The unit is also
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undergoing its end-of-cycle 6 refueling.
Unit 2 The unit remained on administrative hold the entire month. The unit is also undergoing its end-of-cycle 5 refueling.
l Unit 3 The unit remained on administrative hold the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.
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Operations Summary (Continued)
October 1987 Fatigue Usage Evaluation The cumulative usage factors for'the reactor vessel are as follows:-
Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431' Feedwater nozzle 0.29782 0.21319-0.161'39 Closure studs 0.24204.
0.37629 0.14360 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.b(3) reporting requirements.
Common System Approximately 6 86E+05 gallons of waste 11gulds were discharged containing 3
i approximately 5.02E-02 curies of activity.
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Refueling Information October 1987 Unit 1 I
Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with a i
scheduled restart date to be determined. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup l
unit 1 items are environmental qualification of electrical equipment (10CFR50.49), torus modification (NUREG 0661), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifications, modification of masonry wallo (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J), HPCI concerns, modification of PCIS logic (LER 259/85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), RPS modifications (IE Notice 78-45), H 0 sample line modification (LER 81050), radiation monitors modification (LER 80033), EECW I
carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which are scheduled f
for next outage.
There are 0 assemblies in the reactor vessel. The spent fuel storage pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available capacity of the fuel pool is 1355 locations.
Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined. On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns.
The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core.
The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB 80-17),
environmental qualification of electrical equipment (10CFR50.49), torus modifications (NUREG 0661), containment modification (NUREG 0737), electrical l
changes (Appendix R 10CFR50) (partial), MSIV modifications, modification of masonry walls (IEB 80-11), addition'of feedwater nozzlo temperature monitoring
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(NUREG 0619), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J) (partial), D/G speed sensor
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Refueling Information October 1987 Unit 2 (Continued) installation (LER 81004), HPCI and RCIC testable check valve change out, modification of PCIS logic (LER 259/85009). HPCI concerns, seismic program review, and EECW carbon to stainless pipe change out.
There are 0 assemblies in the reactor vessel.
At month end there were 304 new assemblies, 764 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool.
The present available capacity of the spent fuel pool is 1481 locations. All HDRs have been installed in the pool with the exception of two.
Unit 3 Unit 3 was shut down on March 9, 1985, and placed on administrative hold to i
resolve various TVA and NRC concerns with a scheduled restart date to be determined. The sixth refueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-startup unit 3 items are environmental qualifica-tion of niectrical equipment (10CFR50.49), containment modifications (NUREC 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-tions, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), addition of redundant drywell control air supply, RPS modification (IE Notice 78-45),
l HO sample line modification (LER 81050), radiation monitor modification 2
(LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07),
change out of switches in SBGT (LER 83018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification, l
There are 0 assemblies in the reactor vessel. There are 764 assemblies to finish cycle 6, 248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent fuel storage pool.
The precent available capacity of the fuel pool is 585 locations.
All high density racks (HDR) have been installed in the pool with the exception of six.
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Significant Operational' Events
.l October 19871 Unit 1 10/01/87 0001 Unit remains on administrative hold to resolve various
'.14 TVA and NRC concerns, and. end of cycle 6 refueling and modifications continues.
10/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6' refueling and modifications continues.
Unit 2 10/01/87 0001 Unit remains on' administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and.
modifications continues.
i 10/31/87 2400 Unit remains on administrative hold to resolve varicusL i
TVA and NRC concerns, and end of cycle 5 refueling and modifications continues Unit 3 10/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
10/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and' environmental qualifications and modifications continues, i
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OPERATING DATA REPORT 00CKET NO. 50-259 DATE 11-01-87 COMPLETED BY J. D. Crawford?
' TELEPHONE (205) 729-7507 OPERATING STATUS l Notes l
1.
Unit Name:
Browns Ferry Unit One l
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2.
Reporting Period: October 1987 l.
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3.
Licensed Thennel Power (MWt): _3293 l
l' 4.
Namoplate Rating (Gross MWe): 1852 l
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5.
Design Electrical Rating (Not MWe) 1065 l-l l
6.
Maximum Dependable Capacity (Gross MWe) 1098.4 l
l 7.
Maximum Dependable Capacity (Not MWe) 1065 l
'l-l 8.
If Changes Occur in Capacity Ratings. (Items Number 3 Through 7) Since Last Report, Give Reasons:-
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NlA 1
9.
Power Level To Which Restricted, if Any (Net MWe):
NlA
- 10. Reasons for Restrictions, if Any:
NlA This Month Yr-to-Date Cumulative ll. Hours in Reporting Period 745 72 %
116.216
- 12. Numbor of !!ours Reactor Was Critical 0
0 59.521.38
- 13. Reactor Reserve Shutdown Hours O
0 6.997.44
- 14. Ilours Generator On-Line 0
0 58.267.26
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
168.066.787
- 17. Gross Electrical Enorgy Gonorated (MWH) 0 0
55.398.130
- 18. Net Electrical Energy. Generated (MWH)
-719
-12.787 53,707.848 l
- 19. Unit Service Factor 0
0 50.14 j
- 20. Unit Availability Factor 0
0 50.14
- 21. Unit Capacity Factor (Using MDC Net) 0 0
43.39
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- 22. Unit Capacity Factor (Using DER Net) 0 0
43.39
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- 23. Unit Forced Outage Rate 100 100 40.24
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Commercial Operation).
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9l 77) i 6
l OPERATING DATA REPORT DOCKET NO.
50-260 DATE 11-08-87 COMPLETED BY J. D. Crawford l
TELEPHONE (205) 729-2557 l
OPERATING STATUS l Notes l.
1.
Unit Name:
Browns Ferry Unit Two l
-l 2.
Reporting Period: cetober 1987 l
l 3.
Licensed Thermal Power (MWt): 3293 l
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4.
Nameplate Rating (Gross MWe): 1152 l
l 5.
Design Electrical Rating (Net MWe) 1065 l
l 6.
Maximum Dopendable Capacity (Gross MWe) 1098.4 l
l 7.
Maximum Dependable Capacity (Not MWe) 1065 l
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8.
If Changes Occur in Capacity Ratings (ltems Number 3 Through 7) Since Last Report,' Give Reasons: -
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9.
Power Level To Which Restricted, if Any (Not MWe):
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- 10. Reasons For Restrictions, If Any:
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This Month Yr-to-Date Cumulative I
t
- 11. Hours in Reporting Period 745 72 %
_Ill.103
- 12. Number of Hours Reactor Was Critical 0
0 55,860.03 i
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- 13. Reactor Reserve Shutdown Hours 0
0 14.200.44
- 14. Hours Generator On-l.ine O
0 54.338.36 _ _ _
- 15. Unit Reserve Shutdowr. Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
153.245.167
- 17. Gross Electrical Energy Generated (MWH)'
O-0 50.771.798 1
- 18. Net Electrical Energy Gonorated (MWH)
-5.017
-29.307 49.l88.996
- 19. Unit Service Factor 0
0 48.91
- 20. Unit AvalIabiIity Factor 0
0 48.9i
- 21. Unit Capacity Factor (Using MDC Net) 0 0
41.57 _
- 22. Unit Capacity Factor (Using DER Net) 0 0
41.57 i
- 23. Unit Forced Outage Rate 100 100 39.28
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
- 26. Units in Test Status (Prior to Connercial Operation):
Forecast Achloved INITIAL CRITICALITY INITIAL ELECTRICITY COPHERCIAL OPERATION (9l77) 7
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l OPERATING DATA REPORT 00CKET NO.4 50-2% -
DATE 11-01-87 i
COMPLETED BY J. D. Crawford
. TELEPHONE. (205) 729-2507.
OPERATING STATUS
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l Notes l.
i 1.
Unit Names Browns Ferry Unit Three l-l j
2.
Reporting Period: October 1987 l
l 3.
Licensed Thermal Power (MWt):- 3293 l
l.
4.
Nameplate Rating (Gross MWe):. Il52 l
l 5.
Design Electrical Rating (Not MWe) 1065 l
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6.
Maxinun Dependable Capacity (Gross MWe) 1098.4 l
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7.
Maximum Dependable Capacity (Net MWe) 1065 l
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-1 8.
If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Give Reasons:
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9.
Power Level To Which Restricted, if Any (Net MWe):
NlA
- 10. Reasons for Restr(ctions, if Any:
NlA This' Month Yr -to-Da te Cumulative
- 11. Hours in Reporting Period 745 72 %
93,528
- 12. Number of Hours Reactor Was Critical 0
0 45,506.09
- 13. Reactor Roserve Shutdown Hours 0
0 5,149.55
- 14. Hours Generator On-Line 0
0 44.194.76
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
131',R68,267_
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- 17. Gross Electrical Energy Generated (MWH) 0 0-43.473.760
- 18. Net Electrical Energy Generated (MWH)
-4,217
-42,569
_ 42,049,559
- 19. Unit Service Factor 0
0 47.25
- 20. Unit Availability Factor 0
0 47.25-
- 21. Unit Capacity Factor (Using MDC Net) 0 0
42.22 j
- 22. Unit Capacity Factor (Using DER Net) 0 0
42.22'
- 23. Unit Forced Outage Rate 100 100 42.47
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)::
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined-
- 26. Units In Test Status (Prior to Conimercial Operation):
Forecast Achloved INITIAL CRITICALITY INITIAL ELECTRICITY C069fERCIAL OPERATION (9l 77) '
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AVERAGE DAILY UNIT' POWER LEVEL DOCKET NO.
50-259 Unit.
One DATE 11-01-87 COMPLETED.BY-J.D. Crawford TELEPHONE-(205)729-2507-
.3 MONTH OCTOBER 1987
' DAY AVERACE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL.
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(MWe-Net)
-(MWe-Net) i 1
-1 17
-1 i
' l 2
-1 18
-1 3
-1 19
-1 4
-1 20
-1 3
-1 21-
-1 6
-1 22
-1 7
-1 23
-1 i
8
-1 24
-1 j
{
9
-1 25-
-1 30
-1 26
-1 11
-1 27
-1 12
-1 28
-1 13
-1 29
-1 14
-1 30
-1 15
-1 31
-1 16
-1 1
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Not for each day -in the reporting month. Compute to the nearest whole megawatt.
(9/77) 9
(.
i AVERACE DAILY UNIT POWER' LEVEL'.
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DOCKET NO.
'50-2601 Unit-Two' DATE' 11-01-87 a
'bOMPLETEDBY J.D.~Crawford 1
' TELEPHONE ~ -(205)729-2507' '-
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MONTH
' OCTOBER 1987
. DAY AVERAGE DAILY POWER LEVEL' DAY AVERACE' DAILY POWER! LEVEL
'l (MWe-Net)
(MWe-Net) 4
'1
-7 17
-6 2
-7 18,
il 3
-7 19
-7 4
-7' 20'
-7 '
.,.j 5
-6 21
-6 ~
6
-7
.22
-7 7
-7 23
-7 8
-7 24 9
-7 25
' -7 10
-7
'26
-7 11
-6 27
-7 12
-6 28-
-6 5
13
-7 29-
-7 l
14
-7 30
-7 i
15
-7 31
-8 16
-7 INSTRUCTIONS On this format, list the average daily. unit power level:in MWe-Net for each' day in-the reporting month.
Compute to the nearent whole megawatt.
(9/77)
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AVERAGE DAILY UNIT POWER LEVEL
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DOCKET NO.
50-296 Unit' Three-
- DATE, 11-01-87 COMPLETED BY J.D. Crawford TELEPHONE. '(205)729-2507-H MONTH-OCTOBER 1987 j
j DAY.
AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL'-
(MWe-Net).
'(MWe-Net) d 1
-6 17
-5' 2
-6 18'
- 3
-6 19
-5 4
-6 20
-6' 1
i!
5
-5 21
-6 6
-6 22
,-5
{
7
-6 23
-5 1
8
-6 24
-5
.j 9
-6 25
' -6
'h 10
-6 26
-6 11
-6 27
-5 0;
12
-6 28
-S I
13
-6 29
-6 i
i 14
-5 30
-6 f
15
-5 31
-6 5
l 16
-5
.j
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INSTRUCTIONS on this format, list the average daily unit power level in MWe-Nec for each day in the reporting month. Compute to the nearest whole' megawatt.
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L TENNESSEE VALLEYEAUTHORITY.,
j7/Mf Browns' Ferry Nuclear. Plant-
--Post Office Box 2000"
.Decatur, Alabama::35602
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U.S. Nuclear Regulatory Commissions ATTN: Document Control Desk
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1 Office of Nuclear Reactor. Regulation
~
Washington,.D.C. 20555' Attention: Office of' Management.Information.and Program' Control.
In the Matter of.the
)
Docket Nos.'50-259
- )
1 Tennessee Valley Authority
.)
50-260:
i ll g
50-296 BROWNS FERRY NUCLEAR PLANT-(BFN) - MONTHLY OPERATING REPORT.- OCTOBER 1987I L
i Enclosed is the October 1, 1987 Monthly Operating Report to NRC for' Browns Ferry Nuclear Plant units 1, 2, and-3.
L l
Very truly yours, TENNES E VAL EY THORITY 1
J G. Walker
]
ant Manager Enclosure I
cc: Mr. G. E. Gears Mr.
G.' G.:Zech,' Director l
Browns Ferry Project Manager TVA Projects j
U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue 101 Marietta St.,-NW, suite 2900' l
Bethesda, Maryland 20814 Atlanta,. Georgia 30323 j
1 U.S. Nuclear Regulatory Commission Browns Ferry Resident Inspector;
'j Region II Browns Ferry Nuclear Plant 1
Attn:
Dr. J. Nelson.Crace, P.O. Box 311
-Regional Administrator'
' Athens,' Alabama 35611.
101.Marietta Street, NW, Suite 2900 Atlanta, Georgia '30323, INPO. Records ~ Center l
j Institute of. Nuclear Power-l I
Mr. Ted Marston, Director Operations
~
Electric Power Research Institute Suite,1500; i
l P.:O. Box 10412.
1100 circle.75 Parkway.
j Palo Alto,. California' 94304 Atlanta,' Georgia 30389' L
\\
An Equal Opportunity Employer
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