ML20082C306
| ML20082C306 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1991 |
| From: | Carier P, Ratliff S TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9107180304 | |
| Download: ML20082C306 (13) | |
Text
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'JUL i5 411 U.S. Nuclear Regulatory Commission ATTH: Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Hos. 50-259 Tennessee Valley Authority
)
50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFIO - MONTHLY OPERATING REPORT FOR THE MONTl!
0F JUNE 1991 In accordance with the requirements of the BFN Technical Specifications (TS) section 6.9.1.3, the Monthly Operating Report for the month of June 1991 is enclosed.
If you have any questione, please telephone me at (205) 729-3566.
Very truly yours, TENNESSEE VALLEY AUTHORITY l
,m. o ') t.
l P. Carier, Manager I
of Site Licensing Enclosures cc: See page 2 I
KhS71' del'$ !>bE$ff!j9 R
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.U.S. Nuc1 car Regulatory Commission Enclosures cc (Enclosures):
INPO Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30389 Regional Administration U.S. Nuclear Regulatory Commission Re2 ion 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 Mr. Ted Marston, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta Georgia 30323 NRC Resident Inspecter Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. ? red Yost, Director of Research Services, Utility Data Institute, Inc.,
1700 K Street N. W., Sui *e 400 Washington, D.C.
20000
5 a
4 e
MONTilLY OPERATING REPORT BROWNS PERKY NUCLEAR PLANT TENNESSEE VALLEY AUT!!ORITY JUNE 1991 l
i DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
_a_,_-.
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1 OPERATIONAL
SUMMARY
JUNE 1991 UBIT.1 i
Unit remains on administrative hold to resolve various TVA and NRC concerns.
UNIT 2 Unit initial criticality has been accomplished. Generator breaker closure was June 27, 1991. BFN is still in the power ascension testing program.
UNIT _3 Unit remains on administrative hold to resolve various TVA and NRC concerns.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 Unit One PREPARED BY S. A. Ratliff TELEPHONE
.(205) 729-2931 MONTH JUNE 19_91 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I
(MWe-Net)
(MWe-Net) 1 0
17 0
- 2 0
18 0
i 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 13 0
29 0
14 0
30 0
15 0
16 0
- 0449k/8 re-Y ya-vy-w%memW-T-u-wi'a---+=e-
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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 Unit Two PREPARED BY S. A. Ratliff TELEP110NE 12Q1) 729-2937 MONTil JUNE 1991 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
12 0
28 25 13 0
29 0
i 14 0
30 11 15 0
16 0
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t AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-296 UNIT Three l
PREPARED BY L_Ade1DJL.
TELEPIl0NE 1201L729-2937 MONTI! J1Jf(E 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net)
(MWe-Net) 1 0
17 0
j l
2-0 18 0
1 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 O
28 0
13 0
29 0
~14 0
30 0
15 0
16 0
0449k/10
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t OPERATING DATA REPORT DOCKET 90. _50-259 i
PREPARED bY $_._A3,Ratliff TELEPHONE (2051 729-2937 OPERATING STATUS
! Notes 1.
Unit Name:
Browns Ferry Unit One 2.
Reporting Period:
June 1991 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 #atings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level To Which Restricted. If Any (Net MWe):
N/A
- 10. Reasons For Restrictions, If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 4343 148327
- 12. Number of Hours Reactor Wss Critical 0
0 59521
- 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 Energy Generated (MWH) 0 0
168066787
- 17. Gross Electrical Energy Generated (MWH) 0 0
55398130 l
- 18. Net Electrical Energy Generated (MWH)
-1951
-11928 53549542
- 19. Unit Service Factor 0
0 39.3
- 20. Unit Availability Factor 0
0 39.3
- 21. Unit Capacity Factor (Using MDC Net) 0 0
33.9
- 22. Unit Capacity Factor (Using DER Net) 0 0
33.9
- 23. Unit Forced Outage Rate 100 100 55.0
- 24. Shutdowns Scheduled Dwer Next 6 Months (Type, Date, and Duration of Each):
N/A
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: To be determined 0449k/11 t
4 m
w OPERATING DATO REPORT BDCKET NO.
50-260 FREPARED BY $. A. Ratliff TELEPHONE 12_q5) 729-2937 OPERATING STATUS
! Notes 1.
Unit Name: _ Browns Ferry Unit Two 2.
Repcrting Period:
June 1991 1
3.
Licensed Thermal Power (MWt): 3293 1
1 4.
Nameplate Rating (Gross MWe): 1152 1
5.
Design Electrical Rating (Net MWe): 1065 6.
Maximum Dependable Capacity (Gross MWe): 1099.4 7.
Maximum Depindable Capacity (Net MWe): 1065 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A 9.
Power Level To Which Restricted, If Any (Net MWe):
25 percent
- 10. Reasons For Restrictions If Any: NRC hold point This Month Yr-to-Cate Cumulative
- 11. Hours in Reporting Period 720 4343 143214 l
- 12. Number of Hours Reactor Was Critical 416 455.6 56316 i
- 13. Reactor Reserve Shutdown Hou s 0
0 14200
- 14. Hours Generator On-Line 15.6 15.6 54354
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 48226.6 48926.6 153294094
- 17. Gross Electrical Energy Generated (MWH) 1650.0 1650 50773448
- 18. Net Electrical Energy Generated (MWH)
-6661.0
-34875 49016246
- 19. Unit Service Factor 2.2 0.4 38.ja_
- 20. Unit Availability Factor 2.2 0.4 322D_
- 21. Unit Capacity Factor (Using MDC Net) 0 0
32.1
- 22. Unit Capacity Factor (Using DER Net) 0 0
32.1
- 23. Unit Forced Outage Rate 97.8 99.6 55.3 J
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
N/A l
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
N/A 0449k/12 l
CPERATING DATA REPORT DOCKET NO.
50-296 PREPARED BY S. A. Patliff_
TELEPHONE (205) 729-22]I OPERATING STATy$
! Notes 1.
Unit Name:
Browns Ferry Unit Three 2.
Reporting Period:
June 1991 3.
Licensed Thermal Pcwer (MWt): _1293 4.
Nameplate Rating (Gross MWe): 1132 t
5.
Design Electrical Rating (Net MWe): 1065 6.
Maximum Dependable Capacity (Gross MWe): _J023 4 7.
Maximum Dependable Capacity (Net MWe): 1065 If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
8.
N/A 9.
Power Level To which Restricted, If Any (Net MWe):
N/A
- 10. Reasons For Restrictions If Any:
N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 720 4343 125639
- 12. Number of Hours Reactor Was Critical 0
0 45305 0
0 5150
- 13. Reactor Reserve Shutdown Hours 0
0 44195
- 14. Hours Generator On-Line 0
0 0
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 0 0
131258267
- 17. Gross Electrical Energy Generated (MWH) 0 0
43473760
- 18. Net Electrical Energy Generated " ")
-1610
-9554 41962982 0
0 35.2
- 19. Unit Service Factor 0
0 35.2
- 20. Unit Avai! ability Factor
- 21. Unit Capacity Factor (Using MDC Net) 0 0
31.4
- 22. Unit Capacity Factor (Using DER bit) 0 0
31.4 100 100 59.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
N/A To be determined
- 25. If Shut Down At Er d Of Report Period, Estimated Date of Startup:
0449k/13 D
4
EDCCIET NO:
50-259 UNIT SKUTDOWNS AND POWER REGUCTIONS UNIT NAME:
One PREPARED BY:5. A. Ratlif f REPORT PONTH:
June 1991 TELEPHORE:(205) 729 2937 t
! Hethod of
! Licensee Cause and Corrective !
1
! Duration !
! Shutting Down ! Event
!Systgm
!Compgnent!
Action to 1
4 l
! No.
Date 17ype
! (Hours) - ! Reason 2
! Reactor 3
! Report No.
! Code
! Code Prevent Recurrence j.
t'
~!
! 315
.! 06/01/85 !
F
! 720 F'
4
! Administrative hold to 1 i
'l
! resolve various TVA and 1
! NRC concerns.
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1 l
4 F: Forced 2 Reason:
3Hethed:
Enhibit G-Instructions I
4 S: Scheduled A-Equipment failure (Explain) 1-Manual for Preparation of Data E-Maintenance or fest 2-Manual Scram Entry sheets for Licensee i
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-Admini strative 9-Other 6
G-Operational Error (Emplain)
SExhibit I-Same Source H-Uther (Explain) i 0449k i
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I t
i i
g f
4 t
i
00CELET to:
50-250 l
UNIT SHUT!&NS AND POWER REBUCTIONS UNIT NAME:
Two COMPLETED Sv:5. A. Ratliff R90RT NONTH:_ Jure 1991 TELEPHONE:(205) 729-2937
! Method of
! Licensee Cause and Corrective !
! Duration !
! Shutting Down ! Event
!Systgm
,! Corpgnent !
Action to l
! No.
! Date
! Type
! (Hours) ! Reason 2
! Reactor 3
! Report No.
! Code
! Code Prevent Recurrence
! 1 106/28/91 ! F
! 6.8 i
B 1
! Tripped main trubine
! due to high vibration
! 2
!06/29/91 ! F
! 18.9.
D 1
2
! RHR pump "A" placed in !
I service per 2-SI 4.5.B. !
! 1.D(1) at this time j
! Torus Bulk temperature !
I was poted to increase
! rapidi due to mining 4
1
! of hotter water in
! Torus RCIC Quad.
l i
I i
i
?
I: Forced 2
F Reason:
3 Method:
Enhibit G-Instructions d
S: Scheduled A-Equipment Tallure (Emplain) 1-Manual for Precaration of Data B-MaintSnance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Evant Report (LER) File l
D-Regulatory Restriction 4-Enntinuation of Esisting Outage (NUREG-061)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Othe r G-Operational Error (Expla'n)
SEnhibit I-Same Source H-Other (Emplain) 0449k 4
1 a
9 4
i O o
<Q.
- - ~ ' '
e
DOCKET to:
50-296 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME:
Three CCitPLETED BY:5 A. Ratliff r
kEPORT I40 NTH:
June 1991 TELEFHONE:(205) 729-2937 l
1-
! Method of
! Licensee Cause and Corrective !
! Duration !
! Shutting Down ! Event
!Systp 1Comppent!
Action to l
! No.
l' Date
! Type
! (Hours). ! Reason 2
! Reactor 3
! Report No.
! Code
! Code Prevent Recurrence 1
1 1
'l -
! 157 L! 03/03/85 1 F
! 720-F 4
! Administrative hold to !
! resolve various TVA and !
! NRC conceens.
4
[
't 4
l L
l I
I: Forced 2 Reason:
3 Method:
- xhibit G-Instructions F
E
'S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B enintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling
~
3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation of Existieg Outage (NUREG-051)
E-Operator Training and License Examination 5-Reduction F-Administrative-9-Other G-Operational Error (Explain)
SEnhibit I-Same Source H-Other (Esplain) 1 0449k/33 i
i t-9 9
4 6'
s
.