ML20207F713
| ML20207F713 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/30/1986 |
| From: | Creamer K, Robert Lewis, Ratliff S TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8701060202 | |
| Download: ML20207F713 (18) | |
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TENNESSEE VALLEY AUTHORIT(
s OFFICE OF NUCLEAR PCWER ^
BROWNS FERRY NUCLEAR PLANT
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.e MONTHLY OPERATING REPORT TO NRC i
SEPTEMBER 1, 1986 - SEPTEMBER 30,$1986 t i g;s
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DOCKET NUMBERS 50-259, 50-260, AND 50-296 i
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CONTENTS' Operations Summary.
1 Refueling Information...
3 Significant Operational Events.
5 Average Daily Unit Power Level.
6 Operating Data Reports..
9~
Unit Shutdowns and Power Reductions........
. 12
- Addenda - Revision to May, June, July and August-report.
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00278
1 Operations Summary-SEPTEMBER 1986 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.
There was one reportable occurrence and no revisions to previous occurrences reported to NRC during the month.
Unit'l The unit remained on administrative hold the entire month. The unit is also 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.
Unit 3 The unit remained on administrative hold the entire month. The unit is also undergoing environmental qualifications to comply with NRC requirements.
This was prepared principally by T. R. Smith.
0027B
2 Operations Summary (Continued)
SEPTEMBER 1986 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 0.00430 Feedwater nozzle 0.29782 0.21319 0.16133 Closure studs 0.24204 0.17629 0.14326 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.b(3) reporting requirements.
Common System Approximately 9.32E+05 gallons of waste liquids were discharged containing approximately 3.94E-02 curies of activity.
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l 00278
o 3
Refueling Information SEPTEMBER 1986 Unit 1 Unit I was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. Tne 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 (10 CFR 50.49), torus modification (NUREG-0661), containment modifications-(NUREG-0737),
electrical changes (Appendix R 10 CFR 50) (all) MSIV modifications, modifica-tion of masonry walls (IEB-80-ll), 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). H0 s amp.le 22 line modification (LER 81-050), 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 is 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, 232 EOC-3, 156 EOC-2, and 160 E0C-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 (retrofic) 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 (10 CFR 50.49), torus modifications (NUREG-0661), containment modification (NUREG-0737), electrical changes (Appendix R 10 CFR 50) (partial), MSIV modifications, modification of masonry walls (IES-80-ll), addition of foedwater nozzle temperature monit:rina (NUREG-0619), evaluation of the vent drain and test connections, VDTC, (LER-82020), valve modification (Appendix J) (partial), D/G speed sensor l
0027B i
4 Refueling Information SEPTEMBER 1986 Unit 2 (Contiuued)
! installation (LER-81-004),: HPCI and RCIC. testable check valve. change out, modification of PCIS.logicL(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'303 new assemblies, 764'EOC-5, 248'E0C-4, 352 EOC-3, 156 EOC-2, an'd 132'EOC-1 assemblies in the spent fuel storage pool. The present available capacity of
- the spent fuel pool-is 1164 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 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 electrical equipment (10 CFR 50.49), containment. modifications (NUREG-0737), electrical changes (Appendix R 10 CFR 50).(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 (NUREGJ0737),' addition of redundant drywell control air supply, RPS modification (IE Notice 78-45),
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H0 sample line modification (LER 81-050). radiation monitor' modification 22
[
(LER 80033),. replacement of jet pump holddown beam assemblies (IEB-80-07),
change out of switches in SBGT (LER-83-018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.
i There are 764 assemblies presently in the reactor vessel. There are
'248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-2, and 208 EOC-1 assemblies in the i'
' spent fuel storage pool. The present available capacity of the fuel pool is 914 locations.
!~
a 0027B l
3 Significant Goerstional Events SEPTEMBER 1986 Unit 1 09/01/86 0001 Unit remains on administrative hold to resolve various IVA and NRC concerns and end of cycle 6 refueling and modifications continues.
09/30/86 2400 Unit remains on administrative hold to resolve various T7A and NRC concerns and end of cycle 6 refueling and modifications continues.
Unit 2 09/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
09/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns and end of cycle 5 refueling and modifications continues.
Unit 3 09/01/86 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications. continues.
09/30/86 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.
0027B
6 AVER AGE DAILY UNIT 70 PEER LEVE!.
DCCKET NO.
~0-I5 UNIT one
-10 1-46 DATE COMPLETED 3Y K. L.
Creamer TELEPHONE 205/729-2955
'V'" **
MONTri
..VERAGE D AILY PowEP. LEVLL DAY AVEtt ACE DAILY POWER LEVEL DAY t\\lhea:t1 O!We Net)
-6
-7
' 6 __
t3-
-6 2
3-
-7
-5 tg
-6 4
20
~
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-6 21
-2 6
= - -
-6 22.
-3
-6
-3
.3
-6
,4
-4 3
-6 9
33
_4
-7 10 26
-4 II
-6 27
-3 12 23
~
13
-6 2'>
~3 is
-6 30
-3
-6 15
-6 it t
INE TRtX P.ONS On thoJorn:st, hst ite ater;.r: daih u..t p.mtr 1.:sel :a ?1We%t for cath day la the ryorting rnonth. Co npute to
!! e r.earnt whee!e niegawaii.
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01/77)
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c-AVERAGE D ALLY UNIT POWER LEVEL 50-260 DOCKET NO.
UNIT Two 10-1-86 DATE COMPLETED BY K. L. Creamer TELEPHONE. 205/729-2955 september MONTil DAY TVERAGE D41LY POWER LEVEL 04Y AVElt ACE D AILY POWER LEVEL i \\lhc.N rt!
IMwe Net)
-5
-5
_i7
-5 4
2
,3 3
-5 to
-5
-5 4 20 5
-5 21
-6
-5 6
22
-4
-5
-5
,.e
~
1 21
-5 9
-5 25
-6
-5 10 ll
-5 37
-5 23
-5
^r
~5 33 29
-5 l-
-5 30
-5 45
-4 3,
l e.
-6.
IN51Rt:CTIONS On (f..<).>ttnat, hst the verap dails us.: pour tegel ia siwe.ge fgI 3 3a c.i the tqunmg rnunth. Cinnpute.: 3 the r.estest whole niegaw,,it, (4/77i
3 AVER ACE D AILY UNIT P0wER LEVEL DOCKET NO.30-20A UNIT -T'hree DATE 10-1-86 COMPLETED 8Y K. L. Creamer TELEPHONE 205/729-2955 MONTil Sectember
..VERAGE D AILY POWER LEVEL DAY AVER ACE D AILY POWER LEVEL DAY Olhe NetI (MWe Net)
-3
-5
,7
-3
-5 i3
-5
-5 3
gg 4
-5 20
-5 s
-3 2:
-5 3
-5' 32
-4
-5'
_4 1
-4 23
-4
-5 9
25
-4
-5 10 26
-4 11
-5 27
-4
-5
_4 3
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-4 29
-5
-4 14 15
=
-5 3
16
- 3._.
INE IRt;CT!ONS On th.iJor'nst. Inst the ver p dals uti.: p, wur lesd in MW,:.' Jct for c;ch dav m the ts:portir.g mor'.(!.. C...
pu:: m the r.esrnt whole n egswan.
(4/77n
OPERATING DATA REPORT DOCKET NO.30-239 DATE
'O96 COMPLETED 3Y
~ ~
N acer TEL2P!!ONE N m o-1935 OPERA TING ST A TUS i
- 1. Umt Name:
3ro m Fe mt Cne
'w o <'s
- 2. Reporting Period:
Sectember 1986 j
l
- 3. Licensed Thermai Power pibti:
3293 l
l
- 4. Nameplate Rating (Gross Mbe).
1152 f
- 5. Design Electrical Rating ! Net 31 wet:
1065
$ Maximu:n Dependacie C.macity iGrow '.lhe r 1098 4 M.:ximum Depennanie Ca;:acity tNet.',the :
'065
- 3. If Changes theur :n Capacity Ratings a ttems Numcer 3 Througn h since L.:ss Report, Gi t Rea,,..m; N/A
- 9. Power Level To wheen Restricted. if Anv. vt '.lbe 3/A
'g j^
' +
to. Rea3on> For Restne: ion 3. If.\\ny:
This Month Yr. to.0 ate Cumu!.a ris e 720 6,551 106,711
- 11. liners ?n Reportin:t Period 0
0 59,521.36
- 12. Number Of flours Reactor has Critica!
- 13. Reactor Re erve Shutdown flours 0
0 6,997.44
- 14. Hours Generator 0n-Line 0
0 58,267.26
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Grow Then ni Energy Generated tMw11, 0
0 168.066,787 17 Grow Electrical Ener;y Generated (Mwil) 0 0
55,398,130 lb. Net Electrical Energy Generated IMhil)
-3,538 29,910 53,727,099
- 19. Unit Senice Factor 0
0
~54.6
- 20. Unit Aseitability Factor 0
0 54.6
- 21. Umt Capacity Factor t Lsm; MDC Net, 0
0 47.3 0
0 47.3
- 22. Unit Capacity Factor t L mq DER Net) 23 Unit Forced Outage Rai<.
100 100 33.8
- 24. Shutdowns Scheduled Oser Nest 6 Months iType. Date,and Duration of Each):
- 25. If Shut Down \\t End Of Report Period. Estimated Date of Startup.
To be determined.
- 26. Units in Test Status t Prior to Commercial Oneration):
Forecast
\\chiesed INITIA L CRITICA LITY INITI AL ELECTRICITY COMM ERCI A L Ol'ER ATION (9/77 )
10 OPERAILNG D A r.k REPORT DCCXETNO. 50-260 DATE.l.2/C / 86 C0atPLETED BY ?
Freamer
.'EL2 PHON E
'05/79-1955 OPERA TING STATUS i
- 1. Unit Name:
3 ro" Fer'~' TW l
- 2. Re::ortmg Period: Seotember 1986 3293 f
- 3. Licensed Thermal Power 45tht1:
1152
- 4. Nameplate Rating (Grow 3thes:
j 1065 I
- 5. Design Electrical RatingiNet Nthet:
- o. Stasimum Dependable Ocaeuy (G.ow alwe.
'098.4 U 6 3' i
7 31.nimum Depenuabie tap:.eav i. Net *>th.
i If Changes Occur :n Caoacity Ratings iit
.n.Nu:neer 3 Throu.n 7i Since Last Ret.on. Gis.- Reasonc N/A t Power Leset To which Retnered. If Anvi% Me.
N/A N/A
- 10. Reasons For Restrictium If Any:
Th'i! 31onth Yr. to-Date Cumuiata c 720 6.551 101.598
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor has Critical 0
0 55,860.03 0
0 14,200.44 13 Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line 0
0 54,338.36
- 15. Unit Rewrve Shutdown Hours 0
0 0
0 0
153.245.167
- 16. Grow Thermal L ergy Generated 13thH:
0 0
50,711,798 17 Grow Electncal Energy Generated i AlwH)
- 13. Net Electrical Energy Generated tilwil)
-3,501
-39,696 49,225,668 0
0 53.5
- 19. Unit Senice Factor 0
0 53.5 20 Unit Availability Factor 2!. Unit Capacity Factor iUsing 51DC Net, 0
0 45.5 0
0 45.5
- 22. Unit Capacity Fletor (Using DER Net)
- 23. Unit Forced Outage Rate 100 100 32.0
- 24. Shutdowns Scheduled Oser Nest 6 31onths 1 Type. Date,and Duration of Eachi:
- 25. If Shut Down A End Of Report Period. Estimated Date of Startup:
To be determined.
Ih Unit 3 in Test Status tPrior to Commercial 0peration):
orecast s.ehined c
INI TIA L CRI TICALITY INITlAL ELECTRICITY CO\\t31ERCI A L OPER A TION (9/77) i
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i OPERATING DATA REPORT I
DOCKET NO. 50-296 DATE 10/1/86 C031PLETED BY K.
L.
Creamer TELEPflONE 205/729-2955 OPERATING STATUS
- 1. Unit Name:
Browns Ferry Three N0'5
- 2. Reporting Period:
September 1986
- 3. Licensed Thermal Power 131Wil:
3293 1152
- 4. Nameplate Rating (Gross N!We):
1065
- 5. Design Electrical Rating (Net 31We):
1098.4
- e. 31asimum Dependable Capacit) eGross SIWE):
7 31aumum Dependable Capacity tNet $1We):
- s. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report. Gise Reasons:
N/A
- 9. Pawer Lesel To hhich Restrieted. If Anv (Net SIWel:
N/A
- 10. Reasons For Restnerions. If Any:
This 31onth Yr.-to Date Cumularive 720 6,551 84,023
!l. Hours la Reporting Period
- 12. Number Of Hours Reactor Was Critical 0
0 45,306.08
- 13. Reactor Resene Shutdown Hours 0
0 5,149.55
- 14. Hm n Generator On Line.
0 0
44,194.76
- 15. Unit Resene Shutdown flours 0
0 0
!6. Gross Thermal Energy Gerverated (31WH) 0 0
131,868,267
!? Gro,s Electrical Energy Generated (SIWH) 0 0
43,473,760
- 15. Net Electrical Encryy Generated 131WH)
-3,206
-29,790 42,103,983
- 19. Unit Senice factor 0
0 52.6 0
0 T2.6
- 20. Unit Availability Factor
- 21. Unit Capac:ty Factor (Using SIDC Net) 0 0
47.1
- 22. Unit Capacity Factor (Using DER Net) 0 0
47.1
- 23. Unit Forced Out. ige Rate 100 100 34.3
- 24. Shutdowns Scheduled Over Next 6 Stonths tType. Date,and Duration of Eachi:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: To be determined.
- 26. Units in Test Statm IPrior to Commercial Operation s:
Forecast Achieved INIIIA L CRITICA LITY lNITIAL ELECTRICITY l
CO\\l\\lERCIAL OPER ATION I-(4/77)
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e CPERATING DATA REFORT
~
DOCKET NO.
u-4 DATE '!Mo COSIPLETED SY R-T C r e a:".er TELEPHONE " ' " M 9 3.3 OPERA TING STATUS i
f N#8' E f 5#U S ~*f!" Yhr**
U.us Nune-i 2.: Reportmg Period:
' 3. Licenwd Ther=si Power t.\\1Wtt:
3""
3 e"-
- 4. Nunepkte :t ting (Grun SIWeI:
1065
- 5. Desisn Electrical Ratin4 iNet StWe):
1098.a
- c..\\laymum. Dependable Capacity (Gron 31We):
'taymum Jgendaone Cacae:ty tNet S!Wei:
it Chaap Ocear :n Casacity R tings itre:ns Numi:er 3 Througn ?) 5 inca Last Report. Give Reasons:
t
'U A 5 #A 4 Pewer Level To which Re>tricted. li Any (Net.41Weg
- 0.' 3easons Fer Restric
- iuns. ll Any:
This Stonth Yr..to.Date
. Cumularise 744 5,831
,8,3_,303
!I. Ilours in Report;ng Period 0
0
- 45,306.08
- 12. Number Of iJnurs Resetor Was Critical 0
0 5,149.35
- 13. Reactur Resene Shutdown flour, 14 Hours Generator On.Line 0
0 44.194.76
- 15. Unic Re,ene Shutdown flours 0
0 0
0 0
131,868,267
- 16. Grn>s Thermal Ener y Generated 131WH) 0 0
43,473,760 I~
Gem, E'eerical Ener4;y Generated 01WH)
- 15. Net E!cetrieal Energy Generated (31WH)
-2,974
-26,584 42,107.189 0
0 53.1
- 19. Unit Senice Factor 20 Unit Aunlability Factor 0
0 53.1 0
0 47.5 21.. Umt Capacitv Factur iUsing SIDC N:t) 0 0
47.5
? Unit Capacity Factor IUdng DER Net) 100 100 33.6
- 23. Unit Forced Outage Rate
- 24. Shutduwns Scheduled Oser Nest 6,\\lonths IT.ype. Date.and Duration of Eacht:
t
- 25. If Shut linwu \\t End Of Report Period. Estunated Date of Startup: To be determined.
2ti. Units in Test Status iPrior to Comrnercial OperationP Forecast Achiesed INITI \\ L Citt l~lCALITY INITIAL ELECTRICITY COi141ERCIAL OPI:R ATiON mj" }
i
$~~.
.c-,
e n-,
~to
,2 CPERATING DATA 2EPORT -
COC:GT NO. M
?' 6 0 ATE 9 " '04 COMPLETED BY E.
- 7.. Crec er TELEPl!ONE ?o"/
-2960' OPERATING STA TUS i
t 3r CWIIS Ferr*/ Three Notes
}
L.,;.. h.ame:
mt Ju l'r "2"4
. 2. Reportmg Penoo:
?283
- 3. t.ieensed Thermal Pow-r (SIWts:
1152
- 4. Nameplate Ratmg (Gross Sibe):
1065
- 5. Design Electrical Rating (Net SIWE):
1008 4
- o. Slasimum Dependable Capacitv (Gross atWe):
?043
' ~ 31axi. :um Decenuacie Capac:ty tNet.*.tWet:
it Chan;n 0cear :n Capaetty Ratiap (trems Number 3 Through 7) Since ! :st Report.Give Re suns:
3
'1 ! A V/A 9 Pov.er I.esel To Which Restri::ed. If Any (Net StWe):
WA (O. 'le.:mm For Restnctions. t any:
i I
t This *.1onth Yr.-to.Date Cumulative.
744 3,087 82,559 I
- 11. Hours la Reporting Period 0
0
.*45.306.08
- 12. Nomoer Of Houn Reactor ha Critic:1 0
0 5e149.55
- 13. Reactor Resene Shutdown Hours 0
0 44.194.76
- 14. ' Hours Generator On.Line 0
0 0
- 15. Unit Resene Shutdown Hours 0
0 131,868,267
- 16. Crow Thermal Energy Generated ($1WH) 0 0
43,473,760 Grow Electrical Energy Generated (Sth H)
-3, d '+o
-23,olo 42,110,163-l
- 13. Net Electrical Energy Generated (SIWH) 0 0
53.5
- 19. Unit Senice Factor l
0 0
53.5 i,,
20, Unit A$ailability Factor 0
0 47.9
- 21. Unit Capacity Factor (Using SIDC Net) 0 0
47.9
- 22. Unit Cap; city Factar (Using DER Net) 10 0 100 32.9
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Ne.st 6 Stonths (Type. Dale, and Dur: tion of Each):
March 1987-F
' 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA L CRITICALITY INITI AL ELECTRICITY CO\\l\\lERCI AL OPER ATION N/77)
- Revision i
l m--*
~.'
11 OPERATING D$TA REPORT DOCKET NO.
50-296 DATE-7-1 CA COMPLETED BY e n,o 4 cs TEl.EP110NE '
- m o-?955 OPERATING STATUS Notes 3rewns terry Three 1, Umt Name:
Juw 19R6
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (MWt):
1152
- 4. Nameplate Rating (Gross MWe):
1062
-5. Doign Electrical Rating (Net MWe):
1098.4
. o. Stasimum Dependable Capacity (Gross MWe):
1065 7 Masimum Dependable Capacity (Net MWe,
5, if Changes Occur in Capacity Ratings t ten Number 3 Through 7)Since Last Report, Gi e Res>ons:
i N/A N/A
- 9. Power Level To Which Restricted,If Any(Net MWe):
N/A 10, Re.nons For Restrictions,If Any:
This Month Yr..to.Date Cumulative.
720 4,343 81.815
!!. Hours in Reporting Period 0
0
- as 106.n9
- 12. Number Of Hours ReJetur Was Critical 0
0 5,149.55
- 13. Resetor Reserve Shutdown llours 0
0 44,194.76
- 14. Hours Generator On.Line 0
0 0
15 Unit Resene Shutdown llours
- 16. Gross Thermal Energy Generated (MWH) 0 0
131,868,267 0
0 43,473,760 I7 Gro>> Electrical Energy Generated (Mh H)
- h. Net Electrical Energy Generated (MWH) 3,452
-19,764 42,114,009 0
0 54.0
- 19. Unit Senice Fa, tor 0
0 54.0
- 20. Unit Asailability Factor 0
0 48.3 21 Unit Capacity Factor IU>ing MDC Neti 0
O.
48.3 22 Unit Capacity Factor (Using DER Net) f.
100 100 32.1
- 23. Unit Forced Outage Rate
- 24. Shutdumns Scheduled Over Next 6 Months (Type. Date[and Duration of Each):
March 1987
- 25. If Shut Dawn At End Of Report Period. Estimated Date of Startup:
2ti. Units in Test Status iPrior to Commercial Operation):
Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY COMM ERCIA L OPER ATION I
)
~
- Revision
e1
=
13 OPERATING DATA REPORT
^
DOCKET NO. 50-296 DATE 6-1-86 COMPLETED BY T. Smith TELEPHONE ?nc m o 99'55 OPERATING STATUS
'Brcwns Ferry Three Notes -
. g, g,, 3,y
- 2. Reporting Penod:
May 1986
- 3. Licensed Thermal Power (MWt):
3293 1152
- 4. Nameplate Rating (Giuss MWe):
- 5. Design Electrical Rating (Net MWe):
'1065
- 6. Sfaximum Dependable Capacity (Gross MWe):
1098.4-7 Masimum Dependable Capacity (Net MWe):
1065
- 3. If Changes Occur in Capacity Ra' tings (items Number 3 Through 7)Since Last Report. Give Reasons:
N/A
- 9. Power Level To WNeh Restricted,if An Net MWe):
N/A
...L.-
- 10. Reasons For Restrictions.If Any:
This Month Yr..to Date Cumulative.
I1. Hours la Reporting Period 744 3.623 81,095
- 12. Number Of Hours Reactor Was Critical 0
0
- 45.306.08 13.' Reactor Reserve Shutdown Hours 0
0 5,149.55
- 14. Hours Generator On.Line 0
0 44,194.76
- 15. Unit Reserve Shutdown flours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 0 0
111.868.267
'17 Gross Electrical Energy Generated (MhH) 0 0
43.473.760
- 18. Net E!cettical Energy Gen'erated (MwH)
-3.514
-16.312
- 19. Unit Service Factor 0
0
-- 42.117.461 54.5
- 20. Unit Asailability Factor 0
0 54.5
- 21. Unit Capacity Factor (Using MDC Net) 0 0
48.8
- 22. Unit Cipacity Factor (Using DER Net) 0 0
48.8
~
- 23. Unit Forced Outage Rate-100 100 31.4
- 24. ShutJowns Scheduled Over Nest 6 Months (Type. Date.and Duration of Eacht:
- 5. If Shur Down At End Of Report Period.E>timated Date of Startup: h@ 10S7
- 26. Um s in Test Status tPrior to Commercial Operation):
Forecast Achieved INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCIA L OPER ATION
- Revision (9/77)
'I i
1:
TENNESSEE VALLEY AUTHORITY '
s Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 b %YbR Nuclear Regulatory Commission-Office of Nanagement Information and Program Control Washington, D.C.
20555 Gentlemen:
Enclosed is the September 1986 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
Very truly yours, TENNESSEE VALLEY AUTHORITY Robert L. Lewis Plant Manager Enclosure ec: Director, Region II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, Georgia 30303 (1 copy)
Atlanta, Georgia 30389 Director Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D.C.
20555 (10 copies)
Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304 i
l 9
r6-3 An Equal Opportunity Employer j
-