ML18024A730
| ML18024A730 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/02/1979 |
| From: | Dewease J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A728 | List: |
| References | |
| NUDOCS 7903160117 | |
| Download: ML18024A730 (32) | |
Text
TENNESSEE VALLEY AUTEORXTY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT February 1, 1979 - February 28, 1979 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted By:
P ant Superintendent
TABLE OF CONTENTS Operations Summary
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1 Operational Data
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2 Maintenance
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~
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~
3'efueling Information
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~
3 Significant Operational Events Average Daily Unit Power Level Operating Data Reports Unit Shutdowns and Power Reductions.
5 13 l6
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~
~
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o l9 Plant Maintenance Summary.
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22
'i
0 erations Summar The following summary describes the significant operational activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report and begins on page 5-There were 3
Reportable Occurrences reported to the NRC during the month of February.
Two supplemental reports were also made.
Unit 2 Significant operational events for Unit 1 are tabulated by date and time beginning on page S.
The unit scrammed once during the month.
The unit was manually scrammed on February 27 to repair an EHC fluid leak.
A summary of maintenance work is shown on pages 22 through 29.
Unit 2 Significant operational events for Unit 2 are tabulated by date and time beginning on page 8.
The unit scrammed once during the month.
The unit was manually scrammed on February 21 to repair a Combined Intermediate Valve (CIV) on the "C" LP Turbine.
A summary of maintenance work is shown on pages 22 through 29.
Operations Summar (Continued)
Unit 3 Significant operational events for Unit 3 are tabulated by date and time beginning on page 10.
The unit did not scram during the month.
A summary of maintenance work is shown on pages 22 through 29
'atigue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Uni't 1 Unit 2 Unit 3 Shell at water line 0.00391 0.00262 0.00243 Feedwater nozzle 0.17730 0.11527
~
0.09511 Closure studs 0.17044 0.09873 0.07339 Note:
This accumulated monthly information satisfies technical
...,'....-. "i'~ -specification section 6.6.A.17.b(3) reporting requirements.
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- 0~%gcPBcP&'~3>vy~>>,~:(t j'v>> +Q Approximately 6.80E+5 gallons of waste liquid were discharged containing 8.84E-1 curies of activity.
Cooling Towers 3, 4, and 5 were operational this month for two lift'ump operations.
Pork on Towers 1,.2; and 6 was continued.
0 erational Data The average daily unit power level for Units 1, 2, and 3 is shown on pages 13 through 15.
The operating data reports for all three units are shown on pages 16 through 18.
Unit shutdowns and power reductions for all three units are shown on pages 19 through 21.
Maintenance, Ma]or electrical~ mechanical, and instrument maintenance activities during the month are described on pages 22 through 29.
Refuelin Information Unit 1 Unit 1 is scheduled for its third refueling beginning on or about-F December 15, 1979, with'a restart date of January 25, 1980.
This refueling;.
will load additional 8 X 8 R (retrofit) fuel assemblies into the core, re placing presently loaded 7 X 7 fuel.
There are 764 fuel-assemblies in the core.
The spent fuel storaga-;
pool presently contains 322 spent 7 X 7 fuel assemblies and two 8 X 8 R'uel.
1
~ '
'ssemblies.
The present storage capacity of the spent fuel pool is 1080.'ssemblies.
Present planning is to increase that capacity to 3471 assemblies..
'""'."~"rZ'.->>, ~'With present. capacity, Unit l does not have full core discharge capabilify<<
'+g~llllgg~y4~~~1~whywe<'~~
> ~'. +y g< ~ +p>, (i '
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Unit 2 is scheduled for its second refueling beginning on April 27, 1979, with a restart date of June 7, 1979.
Resumption of operation on that; date will require a change in technical spec'ifications pertaining to the core thermal limits.
Licensing information in support of these changes was sub-mitted to the NRC in February.
This refueling will involve replacing some.
more 7 X 7 fuel assemblies with.8 X 8 R (retrofit) assemblies;.
There are 764 fuel assemblies in the core.
At, the end of the month there were 132 discharged cycle 1(7 X 7)fuel assemblies in the spent fuel storage pool.
There are presently 59 new 8 X 8 fuel assemblies in the spent fuel storage pool, and 41 other new fuel assemblies on site.
The present storage capacity of the spent fuel pool is 1080 assemblies.
Present planning
Refuelin Information (Continued)
Unit 2 is to increase that capacity to 3471 assemblies.
With present capacity, the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
Unit 3 Unit 3 is scheduled for its next refuel outage beginning on August 30, 1979, with a scheduled restart date of December 8, 1979.
This refueling will involve loading additional 8 Z 8 R (retrofit) assemblies into the core, torus integrity modifications, core spray piping modifications,
.EECW piping
- changes, feedwater sparger modifications, and LPCX modifications.
Resumption of operation following refueling will require changes in technical specifica-tions pertaining to the core thermal limits.
Licensing information in support
"~~~of these changes will be submitted before the refueling.
~
There are 764 fuel assemblies presently in the core.
There are 208
,.."~.'.:~~fuel asse'mblies in'he spent fuel storage pool.
The present licensed storage capacity of the spent fuel pool is 1132 assemblies.
Significant Ooerational Events Unit 1 Date Ttme Event 2/1/79 0001 2000 2345 Reactor thermal power at 80%, with power ascension in progress in control zod sequence "B"
Reduced thermal power fxom 86% to 65X for reactor feed pump turbine xesponse checks All three reactor feed pumps oack in service, commenced power ascension 2/2 0700 0958 1515 2030 2120 Reactor thermal powex at 86%,
CPR limited.
Reduced thermal power fxom 86X to 72X for RTI-32A Reduced thermal powex fxom 72% to 64% fox RTI-23 RTI-23 completed commenced po~er ascension Commenced PCIOMR from 75X thermal power
.- 2/3 0315 0530 1240 2200 Reactor thermal powex at 86%,
CPR limited Reduced thermal power from 86X to 60X foz rod position indication {RPI) checks and RTI's RPI checks and RTI's completed, commenced power ascension Reactor thermal power at 80X,CPR limited I
2/4 0045 Reduced thermal power from 80X to 60X for zecirculation
- i!5 ~4.;..:'-'.t,"
'--;;-".~.,;>."'.
.-.:...., pumps trip tests
{RTI-27),
~~s.'200
~,
RTI-27 completed, both xecirculation pumps in service,
~,"-',.'~'!,,'>=",":.,'reduced thermal power from 60X to 40X for c ntrol r d
.. -~,~~~.
- ~~-~.
~;=, -0540.....,.Control,rod sequence exchange completed, commenced power
~@8.WWWA'@WPkAQascension
'"~t~-.>>- -".-
.~>~~~ ~i~P~+>-P~P'~,,0930 ':."-'.+<'Commenced PCIOMR from. 60X thermal power
~'-'-
1924 Reduced thermal power from 68X to 60X for control rod pattern adjustment 2330 Control rod pattern established, commenced PCIOMR 2/7 2115 Reduced thermal power from 91X to 50X for r'ecirculation pumps trip tests
{RTI-27) 2/8 0240 1255 1330 1650 RTI-27 completed, commenced power ascension Reduced thermal.power from 88% to 80X due to low pxessure heater level problems Heater problems resolved, commenced powex ascension Reduced thermal power from 88% to 65% for RTI-22 2/9 0010 0100 0130 0700 RTI-22 completed, commenced power ascension Reduced thermal power from 80X to. 58% for control rod pattern ad)ustment Reactor thermal power at 58X, holding for control zod pattern adjustment Control rod pattern established, commenced power ascension
f nlflfant Oaetatfnnal Events Unit 1 Date Event 2/9 1357 1445 1500 Commenced reducing thermal power from 75X for power shaping and control rod pattern adjustment Control rod pattern established, commenced power ascension from 65% thermal power Commenced PCIOMR from 75% thermal power 2/ll 0220 0540 0700 Reduced thermal power from 90X to 60% for control rod adjustment, turbine CV tests, and SI's Control rod adjustment, turbine CV tests, and SI's completed, commenced power ascension from 60% thermal power Commenced PCIOMR from 75X thermal power 2/13 0800 Reactor thermal power at 97%,
CPR limited 1955 1940 2/16 Reduced thermal power from 97X to 85% for condensate demineralizer backwash and precoat (spare vessel un-available) 2140
Condensate demineralizer backwash and precoat completed, commenced power ascension
~m~~~~~f,~2220
..--.;:,.Commenced PCIOMR from 95% thermal power
".;,I.'-,,'345 Reduced thermal power from 97X to 80X for turbine CV
,. tests and SI s
'>&f.M+2/17."~a~i~@0115-~~~"Turbine CV tests and SI s completed, commenced power
~~'>- --"'> ~" '~- ascension 0245 Commenced PCIOMR from 93% thermal power 0640 Reactor thermal power at 97X, core flow limited 1130 Reduced thermal power from 97X to 90X for pressure regulator test (RTI-22) 1830 RTI-22 completed, reduced thermal power from 90X to 60X for control rod pattern adjustment New control rod pattern established, commenced power ascension from 60% thermal power 2115 Commenced PCIOMR from 20% thermal power 2/19 2/23 0608 2108 2250 Reactor thermal power at 99X, steady state Reduced thermal power from 99% to 85X for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension
,Si nificant Ooerational Events Unit 1 Date Time Event 2/24 2/27 0100 0922 1020 1156 1419 1425 1519 1827 1855 Reactor thermal power at 99X, steady state Commenced reducing thermal power to shutdown to repair control valve no.
2 servo oil leakage Reactor scram no.
106 manual from 35X thermal power to accommodate maintenance Maintenance to no.
2 control valve servo completed, commenced mod withdrawal Reactor critical no. 121 Reactor made subcritical for further maintenance to no.
2 control valve Reactor made critical (no. 122) for startup Rolled T/G Synchronized generator, commenced power ascension in control rod sequence A
2/28 0731 2400 Commenced PCIOMR from 60X thermal power Reactor thermal power at 85X, PCIOMR in progress e
v ~APQ>LKi+(~-en%
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i nificant Ooerational Events Date Time Unit 2 Event 2/1/79 0001 Reactor thermal power at 95%, steady state, control rod sequence "A"
2/2 0700 Reactor thermal power at 94%, rods limited 2/3 0435 0527 0630 Reduced thermal power from 94% to 90X for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension Reactor thermal power at 94%, rods limited 2/6 0130 0308 0320 Reduced thermal power from 94% to 85% for condensate demineralizers backwash and precoat Condensate demineralizers backwash and precoat'ompleted, commenced power ascension Reactor thermal power at 94X, rods limited 1500 2/10 0306 Reduced thermal power from 94% to.'85% for condensate demineralizer backwash and precoat 0445 Condensate demineralizer backwash and precoat completed, commenced powex'scension
."0630
'- 'eactor thermal power at 94%, rods limited I e p e
2/11
.0037,
Reduced'hermal power from 94X to 85% for turbine CV
- .>~~q~~~j~fm"';.~~=4Ps.' tests and SI'.
.;l0148
"--"':-Tuxbine CV tests and SI's completed, commenced p
ascension 0310 Reactor thermal power at 94X, rods limited 1148 Reduced thermal power from 94X to 80X for control rod pattern adjustment and condensate demineralizer backwash and precoat 1345 New control rod pattern established and condensate demineralizer backwash and precoat completed, commenced power ascension Commenced PCIOMR from 85% thermal power 2/12 2300 Reactor thermal power at 98X, steady state 2/15 0020 0110=
0732 Reduced thermal power from 98X to 88% for condensate'emineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 99%, steady state
Si ni.ficant Operational Events Unit 2 Date Time Event 2/16 2200 2305 Reduced thermal power from 99X to 85X for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension 2/17 0001 Reactor thermal power at 97X, rods limited 2/19 2/21 1500 1245 2110 Reactor thermal power at 96X, rods limited Commenced reducing thermal power from 96X for shutdown to repair combined intermediate valve on "C" LP turbine Reactor scram no.
73 manual from 40X thermal power for maintenance to combined intermediate valve Commenced rod withdrawal 2/22 0104 0337 0400 1330 Reactor critical no.
86 (sequence "A")
Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOMR from 60X thermal power
";~~'~R-'."."~'-'/24
~ D.~A1330
-".->"~ Reactor thermal power at 97X, rods limited
~
t...-.',
~
>~m~q~"".2/25-;=-m0045 =-.w.'-Reduced thermal power from 97X to 75X, for turbine.CV
~~
f'i,
~ "!i'< afa-'a<)<<
"..~. ~ma
~ -'a
." ""-:a*a teStS and SI S
"'".'-".':"""'-""W."~0325;.",g,:.TurbineCV tests and SI's completed, commenced power 1500 Reactor thermal power at 97X,iods limited 2330 Reduced thermal power from 97X to 65X for removal of two condensate demineralizers for.backwash and precoat, and "B" condensate booster pump for seal water leakage 2/28 0210 0600 1500 2400 Completed condensate demineralizer backwash and precoat and maintenance to "B" condensate booster pump and placed in service, commenced power ascension..
Commenced PCIOMR from 80% thermal power Reactor thermal power at 97X, rods limited Reactor thermal power at 97X, rods limited
10
.--~initicant eratienal Events Unit 3 Date T1ae Event 2/1/79 0001 Reactor thermal power at 99%, sequence "B", steady state 2/2 1950 Reduced thermal power from 99X to 50X for both recirculation pumps M.G. set brush replacement and turbine CV tests and SI's 0002 0505 0620 0830 1255 1435 2/5 1405 2300 2/3
,Turbine CV tests and SI's completed, holding at 50X thermal power for completion of MG set brush replace-ment 0420 Both recirculation pumps MG set brush replacement completed, commenced power ascension Commenced PCIOMR from 65X thermal power Reactor thermal power at 71%, holding for removal of "C" reactor feed pump from service for maintenance (erratic flow controls) 1345 Commenced power ascension with two reactor feed pump operation 1500 Commenced PCIOMR fr'om 77X thermal. power
~>2/4-E ~.,0225,,...,3, Reduced thermal power from 82X to 72% for control rod
- - pattern adjustment
":;:;-P~ '.",-,"-,,';,.'.'0252 '.":
New control rod pattern established
....-, -att;,,0300
- t. Commenced PCIOMR from 72X thermal power
~WW~49~~% '0720~;~=.~.'educed thermal power from 80X to 62% due to loss of
'~~'~--.P~~~'-"8=";~~""';~~~"'";-..'".;",,"-"'A" reactor feed pump (erratic flow controls) 0725 "A" reactor feed pump back in service, commenced power ascension from 62X thermal power Commenced PCIOMR from 75% thermal. power "C" reactor feed pump back in service Reducing thermal power.Crom 77% to 62X due to feed pump control problems on all 3 feed pumps 1800" Reactor thermal power at 62X and "C" reactor feed pump out of service 2200 Commenced power ascension 2230 Commenced PCIOMR from '78% thermal power for two reactor feed pumps operation 0700 Reactor thermal power at 80%,
two reactor feed pumps operation limited "C" reactor feed pump maintenance.
completed and pump placed in service 1430 Commenced PCIOMR from 80% thermal power 2120 Reduced thermal power from 88% to 80% for control rod pattern ad)ustment New control rod pattern established, commenced PCIOMR from 80% thermal power
11
~ttnittcant Oaerattenal Erenta Date Ttaa Unit 3 Event 2/6 2/10 2330 1045 1105 1200 1500 2313 Reactor thermal power at 99% steady state Reduced thermal power from 99X to 70X due to steam E
jet air ejector isolation causing vacuum to drop Steam jet air ejector back in service, commenced power ascension Commenced PCIOMR from 96X thermal power Reactor thermal power at 99X, steady state Reduced thermal power'rom 99X to 85X for turbine CV tests and SI's 0045 0130 0530 1007 2/11 Turbine CV tests and SI's completed, commenced power ascension Commenced PCIOMR, from 96X thermal power
~a Reactor thermal power at 99%, steady state Reduced thermal. power from 99X to 90X for control rod pattern adjustment 1030 New control rod pattern established, commenced PCIOMR from 90X thermal power
=
2300
'.'=
Reactor thermal power at-99% steady state
'IIC meteaaeetet~ae iea aW~~.t
~
~-w;i~-;~.'- 2/14
..~.-'.;. 0945 -;. Reduced thermal power from 99X to 95% due to rods'imits 1840:
- Reduced thermal power from 95X to 75% for control rod
.---~~~~'~~',"~@~>-".~,", -',-'"~pattern adju tment
- ." '--'-". -~
!'~-".::~~ '2105..'.+;;New'ntrol rod pattern established, commenced power
"'~.~'" >"."-"t;- ~'3 ':"~-.' '=~-'-"-" "- '-
~ 'SCenSiOn 2230 Commenced PCIOMR from 90X thermal power 2/15 0700 2000 2056 2300 Reactor thermal power at 96%, rods limited Reduced thermal power from 96X to 75% for control rod pattern adjustment New control rod pattern established, commenced power ascension Commenced PCIOMR from 90% thermal power 2/16 2300 Reactor thermal power at 99%, steady state 2/17 1300 Reactor thermal power at 100%, steady state 2/18 0001 0130 0240 1100 Reduced thermal power from 100% to 85% for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension Commenced PCIOMR from 95X thermal power Reactor thermal power at 99%, steady state
12
-Ai nificant 0oerational Events Unit 3 Date Time Event 2/23 2217 2347 Reduced thermal power from 99% to 80% for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension 2/24 2/28 0030 2400 Reactor thermal power at 99%, steady state Reactor thermal power at 99%, steady state
13 AVERAGE DAILYU. iITPOWER LEVEL DOCKET NO.
UNIT Brosrrts Ferry T-DATE COMPLETED BY TELEPHONE 205/729-6846 MOi(TH Februar 1979 DAY AVERAGE DAILYPOWER LEVEL (iMIWe-Net)
I
. 839 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 940 791 729 598 713 18 19 20 21 902 1065 1072 1062 6
876 22 881 23
~~lje~~'9~py%o~Aac: 806
~I@i~ <<<i. Pj paVhYgg)Vv, i 0 6j ~Yg
.s fJ PfY
\\
~ ~44~.eY~W.
a: w
'4tcfItt. ~~
=--'
-. '.;..26 1089 1100 1045 1069 1090 488 12 l3 14 IS 16 879 1002 1046 1040
. 1037 28 29 30 31 827 INSTRUCTIONS On this format.!1st the average daily unit power level in!~ltVe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(')/77)
14 AVERAGE DAlLYUNITPOWER LEVEL DOCKET NO.
3/2/79 COMPLETED BY TELEPHONE 205/729-6846 hiOi(TH February 1979 DAY AVERAGE DAILYPOWER LEVEL (iWWe-iVet)
I 1041 DAY AVERAGE DAILYPOWER LEVEL (MWe-iVet) 1074 17
~-3 5
6 1037 1022 1025 1019 1030 18 19 20 21 22 1048 1036 1035 642 457
.-:='-:-'..'--.- 7.-
23 n+$&q~+i) Atty-~i.~~g~ ', 9'-=',"x%'+s~g'.] 043 9
~
25 s <aj+A)gp wM,.
'A ~'M5)c4.gi. y pcs, g Qgf 842 989 1028 1071 1061 12 13 14 15 16 1060 1074 1072 1059 1068 28 29 30 31 1019 IibSTRUCTIOiNS On this forntat,!ist the average daily unit power level in BIIVe.i(et for each day in-the reporting:nonth. Compute to the nearest whole megawar t.
(9i771
15 AVERAGE DAILYUNITPOWER LEVEL DOCKET i tO.
50-296.
Browns Ferry III DATE COMPLETED BY TFLEP HONE 205/729-6846 ilIONTH Feb rua 1979 DAY AVERAGE DAILYPOWER LEVEL (ilIWe-Net)
DAY AVERAGE DAILYPOWER LEVEL (M
We-Net
)
1063 2
"3 T
4 1000 745 799 IS 19 20 1034 1071 1072 1062 982
~v, 22 1059 23'4 v<wp~~~<4~~,p. <<4~W=i'",rstv:v:~--rnr v 1067 25
~fmP+4'srQ+k')4$ @i4<W 0+ ~~1053 i,'gip" Inc: i 1081 1098 1037 1061 1081 1073.
13 14 IS l6 1073 1069 1022 987 1022 2S 29 30 31 1069 lilSTR UCTIONS On this format.!1st the average daily unit pi>iver level in MlVe-Xi'et for each day irt the rcportina ntonth. Compute to the nearest whole megawat t.
(')(77 l
16 OPERATING DATAREPORT DOCKET i90.
D4TE 5
2 79 COBIPLETED BY Doo G'reels TELEPHONE
~205 729-6646 OPERATliVG STATUS Notes Unit Name:
Bro~s Kerr I
- 3. Licensed Thermal Power (MIVt):
- 4. Nameplate Rating (Gross hOVe):
1152
- 5. Design Electrical Rating (Net MWe):
10 5
- 6. hlaximum Dependable Capacity (Gross hl>Ve):
1098.4 i We 1065
- 7. hlaxin>um Dependable Capacity (Net i I
).
- 8. IfChanges Occur in Capacity Ratings (Items iVumber 3 Through 7) Since Last Report, Give Reasons:
... 9, Power Level To Iyhieh Restricted. IfAoy)Net hIWe):
~,10. Reasons For Restrictions. IfAny:
Cr.
e(p N/A "I6'."
~~
~c,of< r r'p
~ Q
~wee,hr'>>~, ' -".vrwr,,
='his hIOnth
."~.'""'ll. Hours In Reporting Period,.,"
~;,.'~.14 Hours Generator On Line ".~<-.,'"..:-D:..r <.;-."~","
' '"'.15. Unit Reserve Shutdown Hours ~~'-'"""7"."" '.
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (hDVH)
- 18. Net Electrical Energy Generated (MPH)
- 19. Unit Service Factor
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over iVext 6 hlonths (Type. Date. and Dura Yr.-to-Date 1416 966.80
.37 898.22 2,315,055 740,253 63.4 63.4 49.1 4.8 tion of Each):
Cumulative
'40 154 21198.39 4424.50
- 20589.56 53 087 727 17,580,130 17,046,473 51.3 51.3 39.9 39.9 39.2 e
ss
- 25. IfShut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COhlhlERCIAL OPERATION (o/77)
17 OPERATING DATAREPORT DOCKET NO.
D4TE C05IPLETED BY TELEPHONE
~205 729-6646 OPERATING STATUS.
Notes I
Unit Name.
Browns Fer TI
- 2. Reporting period:
Februa 1979
- 3. Licensed Thermal Power (ilIWt):
- 4. Namephte Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable'Capacity (Gross MWe):
1098.4 1065
- 7. Maximum Dependable Capacity (Net IIIWe):
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Net MWe):
""- 10. Reasons For Restrictions, IfAny'/A N/A This Month
@44~~,
flan p4ppr,. 9'~Eppc<<<<~9rp>>.. <<<<4pL<<2~@i 4>>74 ~ r>><<r p<<>>> -<<.:,>>. 4 H
~
~
~
- ,~~~II.Hours In Reporting Period..'- '
-'.". ~ ~ '12. Number Of Hours Reactor Was Critical
~
~<<. <<+>>54Y"-<<>>
I
~
m
'4~r<<B
.-" r~"~=~13;..Reactor Reserve Shutdown Hours
..~", '~'-..-<<.;,'
" 15: Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated.(MWH)
~ 19. Unit Service Factor
- 21. Unit Capacity Factor (Using 4~IDC Net) 93 ~ 7
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
-24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Refuelin April, 1979 Yr:to.Date 1416 1406.72 9.28 1
3.7 0
4,280,311 1 462 030 1 425 466 99.1 94.5
0.9 Each)
~
~r
'umulative 35065 18,125.01 11,485.99
,I' 47,732,099 15 775 818 15 315 630 49.8
~ L>>
41.0 43.8
~
I I
- 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units ln Test Status (Prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COIIIliIERCIALOPERATION (0177)
18 OPERATING DATAREPORT DOCKET BIO.
DATE COIIPLETED IIY Don Green TELEPHONE I
6 6
OPERATING STATUS Notes Browns Perry III I. Unit Name:
- 3. Licensed Thermal Power (bIWt):
- 4. Nameplate Rating (Gross iiIWe):
1152 S. Design Electrical Rating (Net 51)Ve):
- 6. Maximum Dependable Capacity (Gross M)Ve):
't et IIWe:
1098.4 1065
- 7. Maximum Dependable Capaci y (N i
)
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:.
, 9. Power LevelTo Which Restricted, IfAny(Net MWe):
- 10. Reasons For Restrictions. IfAny:
N/A W
1"
,~~+13~Reactor Reserve Shutdown Hours.:"ij~~-..'-iii;-;"
'+W~+:.~~14.'.Hours Generator On-Line v"-.,";.-'"w'""-'.l.'7.",.;
IS. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
I7. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH)
'9. Unit Service Factor
- 20. Unit Availability Factor
. 100
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 0
- 24. Shutdowns Scheduled Over Next 6 iiilonths (Type. Date, and Dura Yr:to-Date 1416 1 02.15
'1394.37 0
4,278 736 1 449 190 1 414 010 98.5 98.5 93.8 93.8 1.5 tion of Each):
Cumulative 17;520 14,493.35 T
40 430 118 13 216 690 12 819 198 80.6 80;6 68.7 68.7
~
8.7 C
. 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY IiNITIAL ELECTRI CITY COMAIERCIAL OPERATION (o/77)
1 I
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.tl'N!i'sllUTDOIVN
'"'4'i-f S AND POPOVER REDUCTIONS DOCKET NO.
UNI'I NAhfE Browns Ferr Utttt-COh(PLETED IIY MQlLZireett TI!LBI'IIONE, 2~OS 72~9-68I
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l 63 Date 790201 S
2tg B
g%
Tran
.Q yz tl m ~cc
~V) g A
":; 'Liceriscc"I I:. - Evcrit Rcporti'<
42 Cl'a 61> G 62~
OC u 2 ~
to Cause 6%. ( ofrcclivc Aclilu> lo Prevent Rcl.'o>real.'c Derated for Rx feed pump response checks 64 790203.
B Derated for rod position indication checks 65 790204 B
Derated for control rod sequence ex-chan e and recirc um tri test
'66 790207'erated for recirc um tri test 67.
790211 Derated for control rod ad)ustment and turbine C.V. test 68 790217 Derated for control rod ad ustment 69 790227 8.58 Maintenance to number 2 control valve (servo oil leak)
~ ~
t F: Forced S: Scheduled
('>/77)
Reason:
A.Equipment Failure (Explain)
~,
8 hlaintcnance or Test C.Rcfueliog O.Regulatory Restriction E Operator Training k. Liccosc,Exao>lnation F-Adn>ioislralivc C.OpcratIonal L'rr>>r (Explain)
I l.Other fExpl >io) h(ethod:
I hlaot>al 2-hlanual Sera>n.
3-Anion>atic Scram.
4-Other (Explain) 4 Exhibit G - instructions for Prcparatil>o of Data Entry Sheets tor I.icc>>scc Event Rcp >rI (I.I II) Fil (NUI(l!G.
OI6 I )
Exhibit I - Sa>nc Sour'cc
'l l
UNITS IUTDOWNS tttND POWER REDUCTIONS I! '.'j!'p'p'ORTl!ONp![~peblual DOCKET NO.
UNITNAh(E DATE COMPLETED BY TEI.LPIIONE 50-260 Browns Ferr II 3
2 79 Don Green Ho.
Date Ill I
pe I
C J J= -cc
- jII-'
- .
":sk'!
'r:- ':( '.
'; ivn,'(cen'scc"),
j$>,! Event
- ,','f, Report rr>> ',.
P)
Ctf 4l 4l'a
>>I w Cr Cause &Corrective Action lo Prevent Recurrence 77 790221 12.22 A
2 I(aintenance to combined intermediate valve on L.P. Turbine 78 790225 B
Derated for turbine 'control valve test and SI's 79 790227 Derated for condensate demin.
backwash and precoat and condensate booster um seal water leak II
, ~
I F: Forced S: Scheduled
('>/77)
Reason:
A-Equipment Failure (Explain)
B.Maintenance or Test C.Refueling D Regulatory Restriction E.Operator Training & Liccnsc Examination F.Administrative G Operational Error (Explain)
I I.Other (Explain) hlethod:
I -hlanual 2-hlanual Scram.
3-Automatic Scram.
4.0lllcf(Explaill) 4 Exl>ibit G - Instructions for Prcparathul of Data httry Sheets Ior I.iccr>scc Event Rcport (I.I'.R) I'ilc (NURI'.G.
Ol 6l )
5 Exhibit I - Same Source I
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UNITSHUTDOWNS AND POWER REDUCTIONS fi),'.;::,::::.j DOC YET NO.
50-296 COhfPLETED It@
Don Green No.
77 78 Date 790202 790210 fP~
0 gp~ V)
'gg'L(kcnscc;,
( "Rcpoft ¹-
-'.5f" "wgh-
'a C
C Cl a~0 f= 0 0
Cr Cause h Corrective Aelioll If>
P(event Rccuffcnec Derated to replace brushes in both recirc H.G. sets Deraded when steam )et air e)ector isolated 79 790214 H
Control rod ad ustment 80 790215 H
Control rod ad ustment F: Forced S: Schedule>sec L'vent Report (I.ER) File (N(IRI:.G.
016I )
Exhibit I
~ Salnc Source
CSSC E UIPMBNT BROWS PERRY NUCLEAR PLANT UNIT 1
,.p, il
~
!:.jMECHANICAL MAINTENANCE SUKQ.RY Pop> the-Month of February
] 9 79 2/8 2/11 SYSTEM Control Rod Drive Residual Heat Removal COMPONENT, CRD discharge filter 1B RHR heater service water drain NATURE OP MAINTENANCE Dirty filter Line plugged EFFECT ON SAFE
,-OPERATION OP
'THE REACTOR
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'.A: None
-i p.
CAUSE OP MALPUNCTION Operation Operation RESULTS OF MALFUNCTION None None ACTION TAKEN TO PRECLUDE RECURRENCE" Replaced with clean filters Backf3,ushed line and unplugged 2/17 I
CRD Valve 1-85-588 Leaking pack-ing gland
'>,. None Operation None Tightened packing gland 'and stopped leak 2/22 CRD 1B CRD pump suction filter Dirty filter
.'. None Operation None Installed clean filters
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BRQ5S PEI<RY NUCLEAR PLANT UNXT
- ,.gfNECNANXCAX >fAXNXENlXNCE ECELNY
""Poj, the'Honth of February X979 SYSTBI COIiPONEHT EPFECT ON.GAPE NATURE OF,:; OPERATION. OP
'AINTENANCE 4'HE REACTOR CAUSE OP IIALFUNCTXOH RESULTS OF
?lALFUNCTXOH ACTXOII TAKEN
'lQ PRI:CLUDE RECURRENCE NONE
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- f. i ig,f WCY<
>'
j!if',Hone f.
- jte"t 3/4" pipe plug missing and bad controller Chiller inoperable Replace 3/4" plug, Replaced proportion 1
controller and set to mfg.'pecs.
Checked o.k.
TR 1073 7
2/13 RHRSW 3C RIOR SUP motor vents Air suction vents partial-ly plugged
'!j.'one
-I; n>>>>
t>>n:
Dirty vent Vent screws plugged Cleaned vents Checked'.k.
TR 116900 2/17 Primary Contain-ment 16A-K39 Does not operate None Burned up coil in relay 16A-K39 Alarm does not clear Replaced coil in relay 16AK-39 pnl.
o' 9-42.
Tested ok TR 110156 2/22 Ventila-tion 250V shutdown board battery room - exhaust
'fan B
Motor very noisy None I
ad bearing Improper ventilation Replaced bearing.
Tested ok TR 34830
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BROYBlS PERRY NUCLEZZi PLP~%T UNIT 3
i'k (ELECXRYCAL NAXNTENANCE EIMIARY
~5'LA, gJ
'<w, t>>.'
Date System Component ect on a e Nature of
/Operation of Maintenance 5The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 2/ll CRD Hand switch 85-48 Contacts not working pro-perly Morn switch Not making up Installed new switch Tested ok TR ill)27 2/14 R11R Mechanical Interlock 74-12A Mechanical Interlock 11anging
N/A l A
f, Dirty contacts Contacts on '(pen contactor handing u
Cleaned and lubri-cated mechanical interlock contacts Tested ok TR 111681
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