ML20101R711
| ML20101R711 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1992 |
| From: | Baron R, Ratliff S TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9207160157 | |
| Download: ML20101R711 (13) | |
Text
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. Terwnsee VMey Autrottf Pcst Othce Box ?000 Deca:ur. Alat ama 35609 JUL 131992 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 0F JUNE 1992 In accordance with'the requirements.of the BFN Technical Specifications section 6.9.1.3, the Monthly Operating Report for the month of June 1992.
is irovided 'n'the enclosure.
'If
.u have any questions, please ~ telephone me at (,':')S) 729-7566.-
Sincerely, f
jhk $b
.- p R. - R, - aron,. Manager
-' of Si e Licensing Enclosures cc:.'See'page 2 1
O 9
'lfj$k7I
2; fr
.U.S. Nuclear Regulatory Commission jul'131992-Enclosures cc (Enclosures):
INPO Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta,' Georgia 30389 Regional Administrator U.S. Nuclear Regulatory Commit aion Regicn 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 Martson, 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 Inspector-
~ Browns Ferry Nuclear Plant Route 12, Box 637--
Athens, Alabama 35611 Mr. Fred Yost,. Director of Reseatch Services, Utility Data Instituta, Inc.,
1700 K-Street, NW,; Suite-400
~ Washington, D.C.
20006-o b
I
1:
s MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUT110RITY JUNE 1992 DOCKET NUMBERS 50-259, 50-260, AND 50-296 j.
LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 l
I' d
L-S.
i.-
v.
OPERATIONAL
SUMMARY
JUNE 1992 UNIT 1 Unit remains on adminictrative hold to resolve various TVA and NRC concerns.
UNIT 2 Unit 2 generated 769,840 MWHs (gross) electrical power and was on line 100 percent of the reporting period.
UNIT 3 Unit-remains on administrative hold'to resolve various TVA and NRC concerns.
i 1
L-l.-
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, Srl-259 Unit (gi PREPARED BY S. A. Ratliff TELEPHONE (205) 729-2937 MONTH
' JUNE 1992 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
_., _ )
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=
D 12 0
28 0
13 0
29 0
14 0
30 0
15 0
16 0-PLLIC207/449/8 l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-260 Unit Two PREPARED BY
- 5. A. Ratti.f_f__
l TELEPHONE (205) 729-2937 MONTH JUNE 1992 DAY AVERAGE DA!LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1075 17 1074 2
1077 18 1068 3
1076 19 1067 4
1.7 20 1059 5
1086 21 1068 6
1"11 22 1070 7
1077 23 1069 8
106r 24 1066 9
1070 25 1066 10 1064 26 1046 11 1071 27 887 12 1056 28 1071 13 770 29 1070 14 875 30 1071 15 1058 16 ib70 generation values are based en manual readings from an NOTE: Net integrating watt hour meter. Smalt differences in the time of day of manual recording may cause the values to very slightly.
PLLIC207/449/9 f
l
4 c
- prs, AVERAGE DAILY UNIT POWER.tEVEL 4
DOCKET'NO.-
50-296 UNIT Three PREPARED BY.
S.'A.
Rattiff
' TELEPHONE (205) 729-2937-MONTH JUNE 1992 DAY AVERAGE DAILY POWER LEVEL-DAY
' AVERAGE' DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
'T 0
18 0
3
'O 19 0
4 --
0 20 0
5 0
21 0
6 0
22 0
'T 0
23 0
0 0
24 0
9 0
25 0
10 0
26 0
11
'O 27 0
12 0
28 0
13
'O 29 0
14 0
30 0
15 0
16 0
PLLIC207/449/10 1
b 1
OPEROTING DAVA REPOPT-DOCKET No.
50-259 PREPAR*O BY S. A.
Rattiff
'~ 1 TELErdONE.(205) 729-2937 OPERATINGSTATUk l Notes l
1.
Unit Name: -Browns Ferry Unit One
-l l
2.
Reporting Period:
June 1992
- ,__ ' l l
3.
Licensed Thermal Power (MWt): 3273 j'
I 4.
Nameplate Rating (E oss MWe): 1152 l
[
-5.
Design Electrical Rating (Net-MWe): 1065
-l l
6.
Maximum Dependable Capacity (Gross MWe): 1098.4 l
l 7.
Maximum Deper340!e Capacity (Net MWe): _1965 I
f G.
If Changes Cecac in capacity Ratings (ttems Number 3 Through 7) Since Last Report, Give Reasons:
N/A' 9.
Power Level To Which Restricted,. lf Any (Net MWe):
N/A
- 10. Reasons For Restrictions, if Any:
N/A i
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period.
720 4367 157111
- 92. Number of Hours Reactor Was Criticat 0
0 59521
- 13. Reactor Reserve thatdown Hours O ___
0 6997
- 14. Hours Generator On.:ine 0
0 58267
- 15. Unit Reserve Shutdown Hours' O
O O
- 16. Gross Thermal Energy Generated (MWH) 0 0
__,16*066787
- 17. Gross Electrical Energy Generated (MWH) 0 0
55}98530
- 18. Net Electrical Energy Generated (MWH)
-2267
-12679
__ 53522811
- 19. Unit Service Factor 0
0 37.1
- 20. Unit Avaltability Fector 0
0 37.1
- 21. Unit Capacity Factor (Using MDC Net) 0 0
32.0
- 22. Unit capacity Factor (Using DER Net) 0 0
32.0
- 23. Unit Forced Outage Rate 100 100 57.9
- 24. Shutdowns. Scheduled Over Next 6 Months (Type, Date,. and Duration of Each):
N/A
- 25. If Shut Down At End Of Rcport Period, Estimated Date of Startup: To be determined PLLIC20//449/11
(.
y OPERATING DATA REPORT DJCKET No.
50-?60' PREPA. RED SY' S. A. Ratliff_
TELEPHONE-f205) 729-2937 LO/ERATING STATUS, l Notes j
Browns Ferry Unit Two l
[
1.
Unit Name:
2.
Reporting Period:
June 1992
.l l
3.
Licensed Thermal Power (Mut): 3293 l
l 4.
Nameplate Rating (Gross MWe): 1102 l
l S.
Design. Electrical Rating (Net MWe): 1065 l
l G.
Maximum Otpendable Capacity (Gross MWe): 1098.4 j
l 9.
Maximoa rependable Capacity (Net MWe): *065 1.
__1
' 9.
If Changes Occur in Capacity Ratings (Items Stumber 3 Through 7) Since Last Report, Give Reassns:
N/A
/
9.
Power Levet. To Which Restricted, If Any (Wet '4W2):
N/A
- 10. Reasons For Restrictions, If Any:
N/A This Panth Yr-to-Date cumulative
- 11. Hours in Reporting Period 720.0 4367.0 151998
- 12. Number of Hours Reactor Was Critical 720.0 4178.9 64685
- 13. Reactor Reserve Shutdown Hours 0
0 14200
- 14. Hours Generator On-Line 720.0 4'22.9 62590
- 15. Unit Reserve Shutdown Hours
'O O
O
- 16. Gross Thermat Energy Generated (MWH) 2308531.2 13054615.3
__ 178130471
- 17. Gross Electrical Energy Generated (MWH) 769540.0 4413130.0 59082938
- 18. Net Electrical Energy Generated (MWH) 751784.0 4306910.0 57117169
- 19. Unit Service Factor 100,0 __
?4.4 41.2
- 20. Unit Availability Factor 100.0 94.4 41.2
- 21. Unit Capacity Factor (Using MDC Net) 98.0 92.6 35.3
- 22. Unit Capacity Factor (Using DER Net) 98.0 92.6 35.3
- 23. Unit Forced Outage Rate 0.0 1.0 51.8
- 24. Shutdawns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A
- 25. If Shut Down At End of Report Period. Estimated Date of Startup:
N/A PLLIC207/449/12
'OPERAT!#G DATA REPORT' DorKET NO.
50-294 PREPARED BY S. A. Rattiff TELEPHONE (205) 729-2937 OPERATIh6 STATUS
.l Notes-l 1.
Unit Name: __8rpwne ferry Unit Three-l l
2.
Reporting Period:
June 1992 l
l 3.
Licensed Thermal Power (MVt): 3293
]
l 4.
Nameptate Rating (Gross MWe): 1152 l
l S.
Design Electrical Rating -(Net Mbe): 1065 l
t 6.
Maximum Dependable Capacity. (Gross MWe): 1078.4 l
l 7.
Maximum Dependable Capacity (Net' MWe): 1065 I
__{
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):
N/A
- 10. Reasons For Restrictions, If Any:
h/A This Month Yr-to-Dete Cumulative
- 11. Hours in Reporting Period 720.0 4367.0
- 34425
- 12. Number of Hours Reactor Was Critical' 0
0 45306
- 13. Reactor Reserve Shutdown Hours 0
0 5150 14 Hours Generator On-Line 0
0 44195
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. r.ross Thermal Energy Generated (MWH) 0 0
131868267
- 17. Gross Electrical Energy Generated (MWH) 0 0
43473760
- 18. Net Electrical Energy Generated (MWM)
-1594.0
-993!.0 41942873
- 19. Unit Service Factor 0
0 32.9
- 20. Unit Availability Factor
.0 0,_
32.9
- 21. Unit Capacity Factor (Using MDC Net) 0
__ 0 29.3
- 22. Unit Cacacity Factor (Using DER Net) 0 0
29.3
- 23. Unit Forced Outige Rate 100.0 100.0 62.5
- 24. Shu* downs Scheduled Over Nett.6 Months (Type, Date, and Duration of Each):
N/A
- 25. If Shut Down At o.u Of Report Period, Estimated Date of Startup: To be determin?d PLLIC207/449/13 o
DOCKET to:
50-259 tEllT SPUTDOWNS KD POWER REDUCTIONS UNIT CAME:
One PREPARED BY:5. A.
Rattiff JEPORT MONTH:
June 1992 TELEPHONE:(205) 729 2937 9
l l
Method of Licensee-l Cause and Corrective l
'l Duration Shutting D w1 Event System' Component l action t):
2 No.
'Date.
.iType (Hours)'
Reason Reactor Report No.
Code' Code Prevent Recurrence 315 06/01/85 r
720 F.
4
.asinistrative hold to.
resolve various TVA and NRC concerns.
I 2
3 F: Forcert Reason:
Method:
L4hibit G-Instructions S: Scheduled A* Equipment Failure"(Exptu'n) 1 Manual for Preparation of Data B-Maintenance or Test 2-Manusi Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory kestriction 4-Continuation of Existing Outage (NUREG-061)
E-Operator T aining and License Examination 5-Reduction F-Administrative' 9-Other S
G-Operhtlonal Error (Exple'n)
Exhibit 1-Seme Source H-Other (Explair.)
PLLIC207/449/14 S
L
DOCKET NO:
50-260 UNIT EAXEr TAs Uh!T SHUTDOWNS ALD POVER REDUCTIOXS COMPLITED SY:?. A.
Rattiff.
REPORT MONTH:
June 1992
. TELEPHONE:(205) 729-2937
{
l l
l Method of Licensee j
Cause and Corrective l l
l Duration l Shutting Dwwn Event Sys.em l Component Action to l
I Code' Ccde Prevent Recuarence j
Nc.
Date
' Type (Hours)
Reason Reactor Report No.
Power Reduction to 70%
8 6/13,92 0
B 5
for condenser tub-e i
cleaning and inspection.
l 1
Power Reduction to 70%
9 6/26/92 0
8 5
for rod adjustment and water box fnspection.
i 1
Method:
Exhibit G-Instructions I: Forced Peason:
for Preparation of Data F
1-Manual S: Scheduled A-Equipment Failure (Explain)
Entry sheets for Licensee 2-M2nual Scram B-Maintenance or Test 3-Automatic Scram Event Report (LER) Fite C-Refueling 4-Continuation of Existing Outage (NUREC-061)
E-Regulatory Restriction E-Operator Training and License Examinatf or.
5-Reduction 9-Other F-Administrative
'Exh;*e!". ;15ame Source G-Operational Error (Explain)
H-Oth*r (Explain)
PLLIC207f449/15
' DOCKET.CO:
50-296'
~
UNIT SHUIDOWNS A!D POWER.REDUCTIOMS UNIT CAME:
Three
'+'
COM?LETLD 8Y:S.
A. Rattiff' MEPOWT MONTH:
June 1092
. TELEPHONE:(205) 729-2937' I
l
~lShu'tingDown Method of l Licensee l
l Cause and Corrective Duration
{ Event System j Component l Action to l
2 3
No.
,Date Type (Hours)
-Reason Reactor Report No.
Code' Code $
. Prevent Recurrence 157 03/03/85 F
720 F
4 Administrative nold to resolve variouc TVA and NRC concerns.
I 2
' Exhibit C-Instructions F: Forced Reason:
hethod:
S: Scheduled A-Equipment Falture (Explain) 1-Manual for Preparation of Data 8-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Repor* (LER) File D-Regulatory Restriction 4-Continuation of Existing Outage (NUREG-061)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other 5
G-Operational Error (Explain)
Exhibit 1-Same Source N-Other. (Explain)
PLLIC207/449/16 s
.