monthly operating repts for mar 1981. · refuelin information march 1981 unit 1 unit 1 is scheduled...
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TENNESSEE VALLEY AUTHORITY
DIVISION OF POWER PRODUCTION
BROWNS FERRY NUCLEAR PLANT
MONTHLY OPERATING REPORT
March 1, 1981 — March 31, 1981
DOCKET NUMBERS 50-259, 50-260, AND 50-296
LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
Submitted By:P nt Superin ndent
'It
*
TABLE OF CONTENTS
Operations Summary ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
Refueling Information
Significant Operational Events
~ ~ ~ ~
~ ~ ~ ~
~ ~ ~
~ ~ ~
Average Daily Unit Power Level ~ ~ ~ 15,
Operating Data Reports
Unit Shutdowns and Power
~ ~ ~ ~ ~ ~
Reductions. ~ ~ ~ ~ ~
~ ~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~ ~
18
21
Plant Maintenance ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ 25
Outage Summary ~ ~ ~ ~ 37
*4 4
0
0 erations Summar
March 1981
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.
There were sixteen reportable occurrences reported to the NRC during
the month of March.
Unit 1
There were no scrams on the unit during the month.
Unit 2
There were three scrams on the unit during the month. On March 7,
the reactor scrammed from a group 1 isolation due to 'high steam flow in
three steam lines caused when "B" inboard MSIV continued to close during
a MSIV 10% closure test. The reactor scrammed on March 13, when the main
urbfh'e==tripped,due'to=.~alse~high=water level-"on-.the, reactor caused-..by-
an open equalizer valve on a water level indicating switch. On March 28,
the reactor scrammed when the main turbine tripped due to a false signal
from thrust bearing wear detector caused when a wire was lifted from a re-
lay during electrical maintenance.
Unit 3
There was one scram on the unit during the month. On March 8, the
,reactor scrammed from an APRM "HI HI" flux caused by a pressure spike when
a broken weld on a samplinp line caused a loss of pressure to a main steam
line pressure regulator which resulted in a turbine trip.
2
~Oeraitfoue Su~mmer (Coutfaaued)
March 1981
Fati ue Usa e Evaluation
The cumulative usage factors for the reactor vessel, are as follows:
Location
Unit 1 Unit 2 Unit 3
Shell at water line
Feedwater nozzle
Closure studs
0.00501 0.00393 0.00331
0. 24257 ' '.'16960' 0. 12530
0. 19832 ' '. 13694' 0. 1011:7
Note: This accumulated monthly i6foRatiln 'sat!isfie's technical
specification section 6.6.A.lj7.8(3) r'epdrting requirements.
Common S stem
Approximately 3.35E+05 gallons of waste liquid were discharged containingapproximately 3e36E-01 curie. of activities.
Refuelin Information
March 1981
Unit 1
Unit 1 is scheduled for its fourth refueling beginning on or about
April 10, 1981, with a scheduled restart date of July 23, 1981. This re-
fueling will involve loaing additional 8 X 8 R (retrofit) fuel assemblies
into the core,. the final fix on the sparger modification, power supply on
LPCI modification, generator breaker and unit station transformer tie-in
(requires Unit 2 to be shutdown),, and torus modifications if all approvals
are received.
There are 764 fuel assemblies in .the reactor vessel. The spent fuel
storage pool presently contains 550 spent 7 X 7 fuel assemblies, five 8 X 8
spent fuel assemblies, 260 new 8 X 8 R fuel assemblies, and one spent 8 X 8
R fuel assembly. Because of modification work to increase spent fuel pool
capacity to 3471 assemblies; present available capacity is limited to 134
locations, Mew hdgh denslty~e~toragawachs have heen installed and
are in the process of being qualified for use in the upcoming fourth refuel-
ing out'age.
Unit 2
Unit 2 is scheduled'or its fourth refueling begi'nning on or about
March '26, 1982, with a scheduled restart date of August .13, 1982. This
refueling outage will involve completing reli'ef valve modifications, torus
modifications if all approvals are received, '"A" low pressure turbine in-
spection, MG set installation for. LPCI modification, and loading additional
8 X 8 R fuel assemblies into the core.
Refuel:L~n Information (Cont:Lnued)
March 1981
Unit 2 (Continued)
There are 764 fuel as. emblies in the reactor ~vessel. At the end of the
month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged
cycle 2 fuel assemblies, and 352 dischaxge'd cycle '3 fuel assemblies in 'the
spent fuel storage pool. The present avai'lable'apacity of the spent fuel
pool is 160 loca.tions. With present capacitp, the 1979 refueling was the
last refueling 'that could be discharged to'he @pent fuel poolwithout'xceeding
that capacity and maintaining fu'll'code discharge capability in
the pool. However., 949 new high density storage locations have been in-
stalled, but canno1 be used unt:Ll Special Test 161 is completed.
Unit 3
Unit 3 is scheduled for its fourth refuelihg 'beginning on or about
September 25, 1981,, with a scheduled restart'da'te 'of February 7, 1982. This
refuleing involues loading additional .8" X 8 R (retrofit) assemblies into the,
core, relief valve modification,, turbine inspection, generator breaker and
unit station transformer tie-in,, and torus'bdific'at:Lons if all approvals
are received.
There are 764 fuel assembl:Les presently in the x'eactor vessel. There
are 124 discharged cycle 3 fuel assemblies, 144 dischax'ged cycle 2 fue).
assemblies, and 208 discharged cycle 1 fuel assemblies in the spent fuel
storage pool. The present avai:Lable storage capacity of the spent fuel
pool is 1052 locat:Lons.
Date Time
Si nifi'cant 0 erational Events
Unit 1
Event
3/01/81 0001
1500
Reactor thermal power at 98%, maximum flow, rodlimited.Reactor thermal power at 99%, maximum flow, rodlimited.
3/04/81 1500 Reactor thermal power at 98%, maximum flow, rodlimited.
3/06/81 2300 Reactor thermal power at 97%, maximum flow, rodlimited.
3/08/81 0140
030003100400
0420
Commenced reducing thermal power for (MSIV closuretiming) SI 4.7.D.l.B-2 and SI 4.1.A-11.Reactor thermal power at 65%, holding for MSIV SI's.MSIV SI's complete, commenced power ascension.Reactor thermal power at 76%, holding for turbinecontrol valve tests.Control valve tests complete, commenced PCIOMR(sequence "B").
3/09/81 0335
2300
3/~13 81 2300
3/15/81 0025
0145
0202
Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 98%. EHC vibration limited.
Reactor thermal power, at 97%,,EHC,.vibration limited.
Reduced thermal power to 85% for turbine controlvalve tests and SI's.Turbine control valve tests and SI's complete,commenced power ascension.Reactor thermal power at 97%, EHC vibration limited.
3/17/81 0840
1000
10121030
Commenced reducing thermal power for a control rodpattern adjustment.Reactor thermal power at 64%, holding for controlrod pattern adjustment.All rods out.Control rod pattern adjustment complete, commencedPCIOMR.
3/18/81 2300 Reactor thermal power at,99%, maximum flow, EOC-4coastdown.
3/19/81 0700 Reactor thermal power at 98%, maximum flow, EOC-'4
coas tdown.
~si nifiennt Operationel Events
Unit 1
Date Time Event
3/20/81 0700
1924
1945
2300
Reactor thermal power at 99%, maximum flow, EOC-4
c'oastdown ~
Reduced reactor thermal power to 97% when the1001breaker tripped los:ing unit preferred power and i
locking out reactor feedwater pumps and. xecirculationMG controls due to loss of power to controller.,Reactor feedwater pumps and recixculation MG setsback to normal and unit prefez;red power placed on1002 breaker, conmlenced power ascension.Reactor thermal power at 98%, maximum flow, EOC-4coa.'tdown
e~
3/21/81 0115
0155
02300700
Reduced thermal power to 85% for turbine controlvalve tests and SI's.Turbine control valve te. ts and SI's completed,commenced power ascension.Commenced PCIOMR from 96% thermal power.Reactor thermal power at 98%, maximum flow~ ETC~4
coastdown.
3/23/81 0815
08250900
2300
Condensate demineralizer momentarily bypassed, re-ducied thermal power to 91%.Commenced power,ascen: ion from 91% thermal power.Reactor thermal power at 98%, maximum flow, EOC-'4
Reactor thermal power't 99%, maximum flow,. EOC-4'-
coastdown.
3/24/81 2300 Reactor thermal power at 98%, maximum flow, EOC-4coastdown.
3/25/81 2300 Reactor thermal'power at 99%, maximum flow, EOC"4coastdown ~
3/26/81 1500
2300
Reactor thermal power at, 98%, maximum flow, EOC 4coa s t(Iown ~
:Reactor thermal power at:.98%, EOC-4 coastdown.
3/28/81 0100
0121
0500
0700
Corrtmenced reducing thermal power fox turbine~control,valve tests and SI's.Reactor power at 82%, hplding for turbine controlvalve test.; and SI's.Turbine control valve tests and SI's completed,~commenced PCIOMR.Reactor thermal power at 98%, maximum, flow', EOC~4,coastdown.
Date Time
Si nificant 0 erational Events
Uni't 2
Event
3/18/81 2000 Reactor thermal power at 99%, maximum flow, rodlimited.
3/20/81 1225
12351240
3/21/81 0205
0336
0430
0600
Reduced thermal power to 97% for control rod ad-justments.Commenced power ascension.Reactor thermal power at 99%, maximum flow, rodlimited.
'
Reduced thermal power to 91% for turbine controlvalve tests and SI's.Turbine control valve tests and SI's complete,commenced power ascension.Commenced PCIOMR from 96% thermal power (sequenceIIEII )Reactor thermal power at 99%, maximum flow, rodlimited.
3/26/81 1555
1650
220.0.
Reduced thermal power to 82% for removal of Cland C2 high pressure heaters from service forrelief valve maintenance."C" string high pressure heater isolated, reactorthermal power at 82%, holding for relief valvemaintenance."C".. string high pressure&eaters, back in service.„commenced 'power ascension.
3/27/81 0300
0700
0820
2138
2325
Commenced PCIOiiK from 97% thermal power (sequence
Ilail
I)
Reactor thermal power at 99%, maximum flow, rodlimited.Reduced thermal power to 83% for removal of "C"string high pressure heaters from service formaintenance on heater drain line."C" string high pressure heaters back in service,commenced power ascension.Reduced thermal power from 96% to 82% for turbinecontrol valve tests and SI's.
3/28/81 0025
0900
1252
Turbine control valve tests and SI's complete,commenced power ascension.Reactor thermal power at 99%, maximum flow, rodlimited. (3)Reactor Scram No. 117 from 99% thermal power,turbine trip during work on thrust bearing weardetector.
~Si ~nific:ant Operational Events
Unit 1
Date Time Event
3/29/81 2300 Reactor thermal power at 97/, maximum flow, EOC-4coastdown.
3/31/81 2400 Reactor 'thermal power, at 97K, maximum flow, EOC-4coastdown.
Si nificant 0 erational Events
Unit 2
Date Time Event
3/01/81 0001
0910
Power ascension in progress from 0 power. (Startupfrom scram on February 28, 1981).Commenced PCIOMR from 64% thermal power (sequenceIIBII)
3/02/81 2010
2047
2225
Reactor thermal power at 99%, maximum flow, rodlimited.Both recirculation pumps tripped reducing reactorthermal power to 36%.SI 4.6.A.6 and 7 complete for "A" recirculationpump, "A" recirculation pump placed in service.Commenced power ascension.
3/03/81 0408
0700
1230
SI 4.6.A.6 and 7 complete for "B" recirculationpump, "B" recirculation pump placed in service.Commenced power ascension.Reactor thermal power at 87%, holding to maintaincore limits.Commenced PCIOMR from 87% thermal power (sequenceIIBII)
3/04/81 0700
1500
2300
Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 98%, maximum flow, rodlimit;ed-;. —-Reactor thermal power at 97%, maximum flow, rodlimited.
3/05/81 0700
1500
2300
3/07/81 0408
1430172021152142
Reactor thermal power at 98%, maximum flow, rodlimited.Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 98%, maximum flow, rodlimited.
Reactor Scram No. 115 from 98% thermal power(1)while performing SI 4.1.A-'l (MSIV closure), "B"inboard MSIV continued to go closed after the push-button was released, resulting in a full isolationand scram.Commenced rod withdrawal for startup.Reactor Critical No. 128.Rolled T/G.Synchronized generator, commenced power ascension.
3/08/81 2230 Commenced PCIOMR from 75% thermal power (sequenceI IBlI
)
3/09/81 2130 Reactor thermal power at 99%, maximum flow, rodlimited.
10
6~i„nilicant~Opatatinnal Evanta
Unit 2
Date Time Event
3/11/81 22042237
2243
Commenced reducing thermal power to test MSIV1-26.'eactorthermal power at 73X, holding to tekt P1SIV
1-26.MSIV 1-26 tested and. timed, commenced power ascen-sion.
3/12/81 0100 Reactor, thermal power at 99X, maximum f llaw, rdd1:imited.
3/13/81 2200
2259
Commene;ed reducing thermal power to remove bothrecirculation pumps from service fox bruah replaCe-ment oii recirculation 'Ig set.Reactor Scram No. 116 'rom 50% therma3. powerdue to high water level signal which caused'hemain turbine. and reactor feedwater pumps to tx'ip andreactor. scram on an indicated high water level.
3/14/81 131'6151518301915
Commenced rod withdrawal for startup.Reactor Critical Noa 129.Rolled T/G.Synchronized generator, commenced power ascension.
3/15/81 0330 Commenced PCIOMR from 67X thermal power,'(S'eqdence'I
pll )
3/16/81 0021
0026
01120200
0800
Commenced reducing thermal power from 87X p~ower" forcontro3. rod pattern adjustments.Reactor. thermal power at 78X for control rod adjust',—ments.Rod adjustments complete, commenced power a'scenieon.Commenced PCIOiK from 81% therma3. power '(se~quenc'eIIBII)Reactox thermal power at 99%,. maximum flow, rodlimited.
3/17/81 0600
1500
Reactor thermal power at 98%, maximum flow, rodlimited.Reactor thermal power at 97%, maximum flow, rodlimited.
3/18/81 1018
1045
1335
1355
Commenced reducing thermal power fox a contro3.rod pattern adjustment.Reactox'hermal power at 73%, holding for controlrod pattern adjustment.,Contro3. rod pattern adjuc>tment complete, commencedpower ascension.Commenced PCIOMR from 89% t'hex'mal powex'sequenceI
Idyll�
),
Si nificant 0 erational Events
Unit 2
Date Time
3/28/81 20352358
Event
Commenced rod withdrawal for startup.Reactor Critical No. 130.
3/29/81 045505171200
Rolled T/G.Synchronized generator, commenced power ascension.Commenced PClOMR from 67% thermal power (sequenceI IBlI )
3/30/81 2030 Reactor thermal power at 99%, maximum flow, rodlimited.
3/31/81 1245
1320
1930
2400
Reduced thermal power to 87% for control rodpattern adjustments.Control rod pattern adjustments completed, commencedPCIOHR (sequence "B").Reactor thermal power at 99%, maximum flow, rodlimited.Reactor thermal power at 99%, maximum flow, rodlimited.
~EI ~nifinant OEaratienal Evente
Unit 3
Date Time
3/01/81 0001
0100
0105
0230
Event:
Control rod pattern adjustment complete, in'cre'fasted'eactortherma.'L power to 70/, holdiiag fok t'urbine
control valve tests and SI"..Turbine control valve tests and SI's complete,',commenced PCI011R, (control cell core).Stopped PCI01IR at 71% thermal power, computer outof service.Computer back in servicel commenoed PCIONR frOm 71/.thermal po~er (control ce,ll core).
3/02/81 0801 Reactor thermal power at 99X, maximum flow, .rodlimited.
3/03/81 0419
0615
0705
1005
Reduced therma.'!. power to 86X, to remove "P." condensatedemineralizer vessel from s< rvice, to check'esselselements and resin t:rap for break through; ~also to
'ackwashand precoat: condensate demineraliz'er vesselsI l]l1II and IIJ I I
Condensrate demineralizer proble'm resolved, commencedpower ascen ion.Commenced PCIOlifR from 96X thermal power '(co'ntrol'ellcore) .Reac:tor thermal power at 99%, maximum flow, r<>dlimited.
3/07'/81 2340KH
Commenced reducihg;'thermal power for turbine- con'troI "
valve tests and SI's.
3/08/81 0035
0120
0430
0800
2011
Reac:tox thermal power at 64%, turbine control valvetests and SI's in progress.Turbine cont:rol valve tests and SI's complete,commenl.ed power ascension.Commenced PCIOllfR from 97%'lhermal power (cdnt&ol
chil'ore.)
.Reac,tor thermal power at 99%, maximum flow, rodlimited.Reactor Scram No. 94 from 99% thermal power d'ueto kll flux on "F'I and "C" APRN, caused b'y connectionfailure on the sens:Lng line of the turbine pressureregulator (equipment, malfunction) .
3/09/81 09352230
Commenced rod withdrawal for stax'tup.Reactox Critical No. 106«
3/10/81 024203102210
2300
Rolled T/G.Synchronized gene.rator, commenced power ascension.
'educedthermal power from 73% to 64% for controlrod adjustments.Rod adjustments completel commenced power ascension.
13
Date Time
Si nificant 0 erational Events
Unit 3
Event
3/11/81 0100
2300
Commenced PCIOi~K from 76% thermal power (control cellcore).Reactor thermal power at 99%, maximum flow, rodlimited.
3/12/81 1445
1520
21302300
Commenced reducing thermal power due to high river ~~
hT.Reactor thermal power at 73%, holding due to highriver hT.Commenced po~er ascension from 73% thermal power.Commenced PCIOi~K from 97% thermal power (cont'rol cellcore).
3/14/81 1150 Reactor thermal power at 99%, maximum flow, rodlimited.
3/15/81 0001
0036
0040
0135
--=,.- —..-0200- -- ~
Reduced thermal power to 82% for turbine controlvalve tests ans SI's.Turbine control valve tests and SI's completed,commenced power ascension.Reactor thermal power at 96%, holding for controlrod drive exercise.Control rod drive exercise complete, commenced powerascension.
.-.Reactor"'thermal= power-ae:'99%; Maximumflow,'od'imited.
3/20/81 2355 Commenced reducing thermal power for turbine controlvalve tests and SI's.
3/21/81 0015
0028
0035
0105
0115
0415
0740
0743
Reactor thermal power at 87%, turbine control valvetests and SI's in progress.Turbine control valve tests and SI's complete,commenced power ascension.Reactor thermal power at 91%, holding for control roddrive exercise.Control rod drive exercise complete, commenced powerascension.Commenced PCIOifR from 97% thermal power (control cellcore).Reactor thermal power at 99%, maximum flow, rodlimited.Commenced reducing thermal power for unit shutdowndue to high level alarm in east side scram dischargeheader (personnel error).Plant personnel were performing TI-58 on scram dis-charge header. Stopped reducing thermal power at 73%upon discovery of personnel error.
14
~Si ~~nificant O~erational Event:s
Unfi.t 3
Date Time Event:
3/21/81 07500835
Commenced power ascension from 73% therm@1 ipoker'.Reactor t'herma.'L power, at 99%, maximum flow, rodlimited.
3/25/81 1720
1755
Commenced reducing t:hermal power due to gen'erAtoLbus duct cooling fan siinoking.Reactor therma.'L power at 54X.
3/26/81 070015OO
1800
2200
Reactor therma.'L pbwerReactor thermal powering fan problems.Bus duct cooling fanspoweir ascension.Commenced PCIO],"R fromcell. core).
,at 55%.,at 58% due to bus duct cool-
back:in service,c*mmiended'5%
thermal power (co'ntrol
3/27/81 1306 Reactor thermal power at 99%, maximum flow, rodlimi.ted-
~
GAIA
3/28/81 0010
0020
0035
0700
Commenced reducing thermal power for turbin'e don<trol valve t:ests and SI's.Reactor thermal power at 82X, holding for. turbinecontrol valve tests and SI's.Turbine control y'alve tests and SI's complete„.commenced-power. —,ascensionReac:tor thermal power't'99X.; maximum flow, rodlimi.ted.
3/30/81 0357
0555
06250915
1130
1700
Reduced reactor thermal power to 71% when 3iAreactor. feedwater pump tripped '(hi vibrat;io'n).',Roll,ed 3A reactor feedwater pump for vibiat'iotIicihecks,,3A reactor feedwater pump tripped on high v'ibr'ation.Rolled 3A reactor feedwater pump, commended powerasceinsion.Commenced PCIOl!fR from 93% thermal power i|controlcell. core).Reactor thermal power at 99%, maximum flow, rodlimf.ted.
3/31/81 2400 Reactor thermal power, at 99%, maximum flow, rodlimited;
(1) Equipment malfunct:Lon(2) Unknown — suspected per onnel, error(3) Personnel er'ror
15
AVERAGE DAILYUNITPOWER L'EVEL
DOCKETNO.
Brotens Perry — 1
4-1-81
COMPLETED IIY Ted Thorn
TELEPHONE
IONTH March 1981
DAY AVERAGE DAILYPOWER LEVEL() IWe.)bet)
1045
DAY AVERAGE DAILYPOWER LEVEL(MWC-Net I
17 859
10
12
13
15
16
~ A
1061
1053
1048
1047
1042
1031
912
1057
"1057'041
1046
1044
1031
1032
1033
IS
19
20
21
23
'75
26
27
2S
')9
30
31
983
1042
1048
1038
1047
1038
1075
1045
10'40'*
1041
1023
1033
1027
1025
INSTR UCTIO)VS
On this I'or)nat,!ist thea))era c daily spit Poa').r le)el ii) ~Inc Nct I'))r each day ii) thc rcl)(»til) ~ lni)ilth. C)))ni)t)tc tt)lhc nc Jfcsl ivh))ic IncSa'6'at t.
li)/771
AVERAGE DAILYUNITPOWER LOVEL
DOCI'ET NO.
f rowns, y
DATE
CoiIPLETED BY Te.d Thorn
TELEPHONE
March 1981
DAY AVERAGE DAILYPOPOVER'EVEL(~IWe.Nct I
719
878
833
1056.
1062
1058
201
559
9.52
":10'69
'AY17
l9
OP,
21
23
24
)5
26
-AVERAGE DAILYPOWERLEVEL')))IWe*Net)
i 1048
9991066
~QZ)1056
1062
1064
106rI
1070
1007
ll 1055 27 958
I2
l3
l4
I5
IG
10i60
10,11
'93
8i66
1043
28
') 9,
552
,508
978
1~02
INSTRUCTIONS
Oi> this format.!ist the average daily j)'pit I)i))v'cr Ic)cl ii>!)Inc Nct for each day ir> tl>c icl)i)rtin nl))l>tl>~ Ci)n>pote tothc nearest whole n>c;a)vat t.
I'>/77>
17
AVERAGE DAILYUNITPOWER UsVEL
50-296DOCKET NO.
UNIT Browtls Ferry — 3
4-1-81
COMPLETED BY ~mt 'Ehom
TELEPHOiNE 205-729-6846
MONTH
DAY AVERAGE DAILYPOWER LEVEL(hlWC-Net) '
901
DAY -AVERAGE DAILYPOWER LEVEL(ill
We-Net�
)
107917
10
13
IS
1042
1031
1072
1080
1082
1077
864
-14===.487
959
978
1053
1068
1064
1071
18
19
ap
22
23
24
25
26
27
28
59
3P
31
1071
1074
1079
1053
1066
1068
1072
931
652=
1028
1056
1068
971
1067
INSTRUCTIONS
0» this for»tat.!ist thc ai'crape daily yI)it PI)Micr Icicl i»!II'tVC-Nct I'ol'ar!1 \lay I» thc fc})iiltl»I.»I i»th. Cii»IP»lc lolhc Ilcarcst Ivhiilc»lc~aN:Itt.
I'II77 )
18
OPERATING DATAREPORT
DOCKET NO.DATE 4-1-81
COMPLETED E>Y Ted ThornTELFPfIONE 205-729-6846
OPERATING STATUS
Notesl. Unit Name'
2. Reportine Period: March 1981
3. Licensed Thermal Power (!>IWt):
4. Na>neplate Rating (Gross i>ftVe):
5. Design Electrical Rating (Net MWe): 1065
6. !>Iaxin>um Dependable Capacity (Gross LIOVe):
7 ~fazin>um De endable Ca acitv Net i~Ice:
1098.41065
p p .( )8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
iIA
9. Power Level To.Which Restricted, IfAny (Net MWe):10. Reasons For Restrictions, IfAny:
This Month. Yr.-to.Date Cumuh tive
0
764,657
11. Hours ln Reporting Period 2,160
13. Reactor Reserve Shutdown Hours
14. Hours Generator On-Line 74415. Unit Reserve Shutdown ffours . 0
16. Gross Thermal Energy Gencratcd (MWH) 377- 054
17. Gross Electrical Energy Generated (l>IWII) 786,760 2,226,87018. Net Electrical Energy Generated (MIVH)19. Unit Service Factor20. Unit Availability Factor 100.0 99.121. Unit'Capacity Factor (Usi»g i>IDC Net) 96. 5 94.422. Unit Capacity Factor (Using DER Net) 96.5 94. 4
23. Unit Force<I Out:>gc Rate 0 0.924. Shutdo>vns Scheduled Over Next 6!>Ionth» (Type. Date. and Duration of Each):
Refue1in A >.il 1981
58,44256, 950,15 ———~5,115.29
99 972 69932,990 16032,035,01561.861.8.
51. 5
28.1
5. IfShut l)own At End'Of lfeport I'crif>):E»tin>atcd l)ate of Startup:6. Units I» Tc»t Status II'rior t» Con>n>ercial Operation): Fureca»t Ach>cved
IN ll'IAL ClfIT ICA LIT Y
INll'IAL ELECTRICITYCO.'VDIERCIAL OPI!RATION
(o/77)
'
OPERATI>NG DATAREPORT
OPERATING STATUS
DOCKET >NO. 50 260
CO.'>IPLETED BY ~~It'hornTELEPHONE M>~~29-6846
bootes1. U it N . Brogans Ferry — 2
Reportfnn Per>od; I'farch 19'81
3. Licensed Thermal Povver (!>I)Vt):
4. nameplate Rating (Gross -11)Ve'): 1152
5. Design Electrical Rating (iNet 5'IWe): 1065
6. Ifaximu>n Dependable Capacity (Gross IIIVfe): 1098.47 hfaximum De endable Ca acitv i%et slftVe: 1065
P P u( )8. IfChanges Occur, in Capacity Ratings (Items IIIumber 3 Through 7) Since Last Rel>ort. Give Reasons:
9. Po>ver Level To )Vhich Restricted, IfAny (Net MM(e):
10. Reasons For Restrictions. IfAny: NA.
This lpfonth Yr.~ to.Date Cun>uiative
744 2 1'60I i. Hours In Reporrie8 period
~ -1'.* 13. Reactor Reserve Shutdown Hours14. Hours Generator On-Liine 689.75 i i, 2040.99 .31 781.9515. Unit Reserve Shutdown Ilours 0 , 0
16. Gross Thermal Energy Gencratcd (ilfWH) :! 092 498 . 6 232 974, 99 803 61717. Gross Electrical Energy Generated (ilf)VH)18. Yet Electrical Energy Gencratcd (I>if)VII) 672,804
. . .2,031,060 29,981,367
19. Unit Scrvicc Factor 92.7 '4.5 59.620. l'nit Avaih>l>ilityFactor 92. 7 '94. 5 59. 6
l. Unit Capacity Factor (Use» l4IDC Nct) 84.9 l l l l 88 i3 51.02. Unit Capacity I'actor IU5i»g DER hct) 84.9 88.3 5r .0
23. Unit Forced Out:> c Rate . 7.3. '5.5 ~ . 31.524. Shutdo>vns Scheduled Over Nceet 6!>Idnths ITypce I);>te, and f)urati>»> ul';>ch):
4
Haintenance A.>ril 1981 (21 davs)
25. IfShut Du>vn At End IOf letup>irt I>crit>II:Esli>i>atcd I)r>tc ufStart»p.'6.
Units In Test Status I prior tu Cun»ncrcial Oper:>tiun)> r F>>recast A>.'h'>IeVCItf
IYITIAL Cft'.ITIiCALIT Y
IYll'IAL EL,EC'I'R ICITY, COiliIERCIAL Ol'FRATIO.4
(4)/77)
4
20
OPERATING DATAREPORT
OPERATING STATUS
DOCKET NO.DATE
COlifPLETED LtY Ted ThornTELEPHONE ~~o- 46
Notesl. Unit Name: Brows Ferr — 3
p od Harch 1 98 1
3. Licensed Thermal Poiver (!iIWt):4. Nameplate Rating (Gross IIWe): 1152
5. Dcsien Electrical Rating (Net MWe): 1065
6, alfaximum Dependable Capacity (Gross iiOVe):'i » e endable Ca acit Net iaaf lVe: 10657..fasnnn D p p y( )
8. IfClianges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
NA
~ ~
9. Povver Level To Which Restricted, IfAny (Net bfWe):10. Reasons For Restrictions, IfAny
NA
This ilfonth Yr.-to.Date Cumulative
11. Hoiirs In Reporting Period 744 2 160
13. Reactor Reserve Shutdown Hours
14. Hours Generator On. Linc 713.02 1 573.9915. Unit Rescrvc Shutdown floors 0
16. Gross Thermal Energy Gencratcd(MWH) 2 207 040 4 488 641
I i. Gross Electrical Energy Generated (iaaf WH) 744,730 1 511 950
18. Net Electrical Energy Gencratcd (illWkl) 722,574 1 465,667
!I 20. UllltAvailability Factor 95. 8
21. Unit Capacity Factor (Using i~IDC Net) 91. 2 63. 7
22. Unit Caixicity Factor (Using DER Nct) 91. 2
23. Unit Fr)reed Outage Rate 4.2 9.424. Shutdoivns Scheduled Over Next 6 iifonths (Type. 1)ate, and l)oration of Eaclt I:
58;442-.-2-7-- 605 88--1 966.46
~26 60788 626 050 98025,289,990
7
66.366 '9;"7
5. IfShut l)i)i'vllAt End Of ltcport Pcriy):Estin'iatcd l)atc of Startup:6. Units In Test Status (Prior to Coinmcrcial Operation): F >r ast Achieved
INITIAL CI<ll ICALITYINITIAL ELECTltlCITYCOilitii I(CIAL Ol'E RATION
(i)/77)
UNITSIIUTDOWNS AND POWER REDUCTIONS
lREPO T MON'fll
I
DOCKET NO..UNll NAME
DArECOhll'I.ETED IIY
TI!I.EI'IIONE
50-260
r- -81I e(I . I holll.
l)ale
fP
J
CfI
fLie
I:.
Rc
t
cnsccventort ~
ff CP
IJI'
c'
F IJO
Cause A CorrcclivcAction lo
Prevent Rccufrcncc
170 3-&81 B HSIV Closure Timing (SI 4;7.D.l.b.2and SI 4.1.A.-11)
171 3-17-81 Control rod pattern adjustment
F: I'orccdS: Schcdpled
()/77)
Reason:A.EIIuipmcnt Failure (Explain)B.Maintenance or TestC. Rc fuel inI;D.Rct,ulatory Restriction
I'i
Opcfalor Training h. Liccnsc Fxanthtatlon~F.Adtninistrativc f
G Operational Error (Explain)I I Other (Explain)
hlcthod:I hlanual2.hlanual Scram.3-Automalic Scram.4.Other (Explain)
4Exhibit G - Instructionsfor Preparation ol'DatalinlrySheets I'or Licenseefvcnt Rcport (I.l!R) File (NURI'.G.016 I )
Exhibit I ~ Sant' Iur '
VNITSIIUTDOWNS CND POWER REDVCTiONS
REP RThlON'fll
DOCKET NO 50"260
COh(PLETEI) N'ed Thorn
liate
'rr,
v1
LI
R
ccnsccvcnInnrl Ar—
r.0 ~C QG
Cause Lrr. CorrectiveActi(illIo
Prcvcnt Recurrence
179 3-2-81 Derated due to oA" and oBO recircula-.tion pumps tripping
180
181
3- I-81l
3-'11-81
1 I C 1Jl ~ Jl A n ral 4 1 n nnvI nv'Illa 11n CT ll 1 d 1 111 ~ ILLS Ir4LLvLllILll5vL ~ I ~ L ~
board MSIV continued to go closed aftetpushbutton was released, resulting ina full isolation and scram
Derated to test MSIV 1-26
182
183
3-13-81
3-18-81 S
19 ~ 2I
B
I
I
I
Cnvne lI~ In LO hallh llatnr 1 errel 'indi Ca
tion which caused the main turbineand reactor feedwater pumps to trip.Equalizing valve on level indicatorwas open ~
Control rod adjustment
I
F: ForcedS: Scheduleil
Reason:A Equipmcnt Failure (Explain)Bt.h(aintcnancc ol TestC Refuelingii.iRcgulatory RestrictionI!.Operator Training k Lii:ense FxaminationF.AdministrativeG upcrat(ona( Error (Expiain)I I Oilier (ExplJill)
3Method:i h(anual2.Manttal Scram.3.AUtolll'll!cScfJnl.4 OlhCf (I'xpiJIII)
Exhibit G Instrui.lionsfor PICp:IIJIniil ol Dal J
Entry Siiccts I'or LieciiseeEvent Report (Ll!R)File (NVREG-036rl-)
5— Exhi'Ml I - Sa;Ile Soliree
Olt'iVS AND POIVER REI)UCTIONSUNITSIIUTI)
RT hlON fll I larchREPO
l)OCKET NO. 50-260UNI'I' AhlE
I)ATF 4-2-81COhlPLETEI)!IY Ted Thorn
I)atc~A
I
CI
J
h
a
V Vi Re
cciisccvc iilpofl
Cause A ('orrcclivcAclioii lo
Prevent Rccurrcnce
184 3-28-"gl 16.42 Scram due to turbine trip whileworking on thrust bearing weardetector
I': FiircedS: Schedulcil
(9/77)
Reason:A.Equipmcnt Failure (Explain)I).hlaintenancc or TestC.RefuelingI).Regulatory Rcstri«lion, IL Opcral<ir Training 8; Liccnsc ExaniinationF-Administ rat ivcG Operational Error (Explain)I I Other (Explain)
hlcthod:I MJnual2 hlanual Scram.3 Auloinalic Scram.4 Otl)cf (ExplJiii)
Exhibit G - Instructionsfor Preparation of l)at JEntry Sliecls Ior LicciiseeEvent Report (I.I!R) Fil» (NLIREG.OI6I)
Exhibit I ~ Siuue Source
~~ ~ ~
o
I ~ ~ ~
I I ~
~ ~~ ~ I 'o
~ ~
~'
~ ~
0 ~
R~ ~ ~~ I ~
~ ~ ~ I
I
I
vJ
BRO'ZNS FERRY lUCLEA1'. PLANT UllITu
ELECTRICAL HAIHTENANCE SUMMARYl
For 'he ?lonth of Narch 19 81
D""e System Component Nature ofllaintenance
Operation ofThe I Reactor
Cause of."fal function
Results ofa~la 1 func t ion
Action '1'aken
To PrecludeR currence
3/6/81 EEC14 EEL Northheader lowflow alarmrelay (67AL1)
Received afalse low flowannunciationon panel 9-20for units'1 &~ 3
None Bad low flowalarm relaycoil.
Low flow alarminoperable.
Replaced relay, alarmsystem operated pro-perly. TRI't158585
3/8/81 Fire pro-tection
Smoke detector(XS-39-104AA)
Receivedflase alarmson panels25-325 and9-8.
!iNone! Increased sensi- Smoke detector actu-
tivity of smoke ated 3 false alarmsdetector. in a 6 hour period.
Replaced the smokedetector, performedSI4.11.C.1 & 5.TR8204709
~ ~
~ ~
~ ~ ~ I ~ ~ ~ I '~ ~ ~ ~
~ ~
I I ~ I I ~
~ I
~ ~
~ ~ ~ ~ ~ ~
~ I I ~ I ~ I I
~ ~ ~
~ ~ ~ ~
~ ~ ~
~ ~
~ ~
~ ~ '
~ ~ ~ ~ ~
~ ~ ~ ~ ~ ' ~ ~ I
I ~
~ ' I ~ tl ~
~ ~ ~ I
I ~ I
~ ~
~ I ~ ~
~ ~~ ~ ~ ~ ~ I
~ ~ ~ ~
CSSC EOUIPi'1ENT
BROMN
EKE
S FERRY NUCLEPJ; PL!>NT U?lXT
ECTRXCAL >lAXNTENr~CE SUlAlARY
For,'t he Honth,of Harch 19 81
System Component N,.ture ofllaintenance
EkredOpcl)
t on Sakeation of
ReactorCause of
HalfunctionResults of
Halfunction
chic t ion TakenTo Preclu"eR'currence
3/4/81 DieselGenerators
"HVST2 coil" EHX 3in D/G 3Bstart failurebackup circuit
None "llVST2 coil"found to be badduring redundantstart test.
This solenoid coilwas'ot deterioratedto the point of mak-ing the solenoidinoperable. The-coil did cause aspike on the oscillograph trace.
Replaced the bad coil,solenoid operatedproperly. TR//220503
3/8/81 . DieselGenerators
D/G 3A fueloil pressureannunciator
Received afalse fuel
oil'ressure
annunciation.
Nones Bad annunciatorcircuit card.
Received a falseannunciation.
Replaced the badcircuit card, annunci-ator operated properly.TRI'I204848 IV
3/10/81 Residualheat re-moval
FCV-3-74-74 FCV-74-74 feeder breakertripped aftervalve closedduring performance ofSX4.5.B.l.c
Unit in limitincondition foroperation(TS3.5.B.7)
Unknown RllR valve FCV74-74feeder breaker trip-ped after the valveclosed while per-forming SX4.5.B.1.C
The valve operatingcurrent was measuredand found to be accep-table. No loose con-nections were poundin the breaker'com-partment. The valvhas been cycled daily,through 3/18/81.
)
TR8204839LER8BFRO-50-296/8113
CSSC EOUIPINENT
rr
B 'Y tlJCLB/ P PLItt 0!rTT;30.:NS,,PER'Al - .
~ ELt:,CTRICAL tiAINTENANCE Sulau.RY
:il
I
3/13/83
System
Dieselgenerator
Component
3A D/Gannunciator
Nature of';taintenance
D/G alarmsinoperable
Etl Get, on SQreopera,'tion ofThe ,'coactor
None<
t3
Cause of>talfunction
Bad annunciatorcircuit card
Results ofNa 1 func tion
Annunciatorinoperable
Action TakenTo PrecludeR'currence
Replaced bad circuitcard, annunciator.operated properly.TRfI204821
3/13/8 Rad waste RHR pump room LA-77-25Cflood level would not
Mnnunciator testr t I n«nLA II IJL
None Loose connec-tion on annunciator cxrcuxL"Cnl
Annunciator inoper-able.
Corrected connection,annunciator operatedrorteiltr TR ($ 221 558
3/17/81 tlt Itltent Itt Vntl'3 71 /. /.«\rv& r& f'vnttrtA nnVt «r«ttt'Q vr ~
FCV-73-44"Inboarddischarge
IIval've
Valve motorlead "A2" wasgrounded attaped connectiorin limitorntteconnection com-partment.
Valve was placed inopen (operable) po-sition while theconlductor was r'G=
insulated.
Retaped the conductorperformed ENI 71, 18,and 18.1, valveOperated prOperly,TRf/2O5S09
>3/17/81
gener'atorsD/G 3C Received a
"control powerCC a nnJnVLL «I ~ I~ IU~ ~ t J.«t
tion
Nonet
Bad coil on NVR
relay and loose3558 annunciatocard.
Received a falsen ~ J A t j I«IIIIIUIIIJ«tl J.OII I ht«tt
the control powerwas off.
Replaced the baa.relay COil andt tight-ened the annunciatorcard, the annunciato
Ioperated properly.TR/~205434
'/17/81 480 Voltshutdownnnr,rer
Hotor genera-l.or t)a t 3DA
Received abeneLatoi ut ~
dervoltagealarm for noapparent rea-son.
None Bad annuncIatol.c«trd =
Received a falseundervoltage alarm.
Replaced the badannunciator card,
-annunciator checkedOK. TR//205410
CSSC EOIIIPHEHT
NNU!'NS'BNZaT NUCLNAZ PLANT UNIT
ELECTRICAL I~IAINTEN/ACE SmIIIARYII
JIL
II
DI
System Component Nature ofala'ntcnancc
IMtec!t on SateOpej'ation ofTh,i Iicactor
Cause of'.Inlfunc cion
Results ofNa 1 func t ion
Action TakenTo PrecludeR'currence
3/19/81 Diesel 38 D/GGenerators
Received aoverspeedannunciationon 38 D/G
None Bad annunciatorcard
Received a falseoverspeed annuncia-,tion.
Replaced bad annuncia-tor card, annunciatioitested and clearedproperly. TR8205511
I3/20/81I
I
Air-condi-tioning(I'oo1ing-heating)
38 control bay 38 control bayhiller chiller trippe
None.
K '
A
Oil bypass valveopen
Chiller tripped onlow oil pressure.
Closed oil bypassvalve and adjustedoil regulator valve,chiller operatedproperly. TR8220520
(I3/22/81 IIPCI Low level
switch ongland sealcondenser
Low levelswitch inoper-able.
None Level switch73-158 wassticking
Condensate pump con-trolled by LS73-158would not operateautomatically.
Freed the switch, thepump operated properl>TRPT205499
,,i..i II'. Ii i'ICAL Nu'<ItlTEYVICE SU<~i:IARY
;>«. >><<i~> r <
IKCllAi<
For tl>e .Hont.h of Narc'9 81
DATE SYS'1<;H COt IPO"<EHT ltATURE OF'lPAIttTEt<AIICE
EFFI:G'Ll Otl S>" rEOPERPjTIOiV OF
TiiE <REACTOR
C»USF O;t tALFNICTIOtI
RESUI.TS OF
>~«XLFUHCTIO<v<
ACTlOti T<".KE:I
TO Pi(ECI.UDEr<F CUIIREtICE
l! Fj»eiir<>toe t ioh
L
Iti V-26-95fi Broken Pin 1'fi Roll P|n Broken Frozen Valve Replaced )'insTP «KG<<512
5I((1s ~ ~ ),)/
I l.lie'iL siw:I.!..aci t s .>~a a use > A
CSSC ~l'.( UI.VII".NT >K(:IIAI'ICALIM.INTEV~QlCE SUI IlbhliY
For 'the Honth of .. Harch 19 81
D."i'l'. SYG TE! I
3-2-81 C RD
3-2-81 (:RI)
COHPO!KalT
H20 Header
H 0 Header2
NATURE OF
!-DXI!ITEIIAI!CE
Leakage
Leal:age
EFFI'.CT GN SP2'E
Opr.RATION01'II
E 'REAC1OR
'/A
N/A
CAUSE OF
IIALFUIICTION
Loose I'acking
I.oose Packing
RESUI;I'S OF
MAI,FU!!CTION
Leaking at StemPackin
leal:ing at StemPack:in~
~:C 110<1 IA.'r.hTO PRECI.UDE
RECI!RPJ HCE
Tighten PackinTR !220966
<Tighten PackingTI! ir'220967
2-.19-83 HI'CIRCIC
cCheck Valve „Check Va lveTest
N/A Unknown Unknown Perfor'med SI 3.2.7on Check
Valve'R
ff103787
3-4-81 RBCCM Surge Tank Float Hangs Unknown Bene Stem Mas Bindin Straighten StemTP ff220983
3-7-81
t
3-8-81
CRDr
CRD
SDV Drain 6Vent Valve
CRD 34-23
Frozen Valve
Morn Parts
N/A
N/A
Non-lubricatedValve Stem
Strainer Dirty
Non-lubricated Stem
Unknown
Lubricated ValveStemTR fi204516
Changed StrainerTR ~'220873
3-9-81 EF.CI" Fisher ControValve 50-51.-
Dirty Filter N/A Dirty Filter Unknown Replaced Filter ir6750-6751TR fi220845
3-14-8) EECM FCV 67-51 Change OutSt ainer
Filter StrainerDirt ~
Valve MillNot Close Installed New FilterTR Pc221554
3-13-8I Fut.l PoolCooling.'elium LeakDetectorValve 2BFPC Heat Exch.
Hook UpHeliumLeak
N/A Need to Hook UpI!elium Detectoi
Unknown Removed 1/2" Tubingand Hooked UpTesterTR 8216814
3-20-8. RBCCI I Surge Tank Level SwitchHeeds Adjust-ment
N/AH
Level Switch Outof Adjustment
Swatch Stic! s Adjusted Swit'chTR ff207824
CSSC I'.OUIPlI1'.NT
~'" ' " l ' ~
~ti? IEQUd; ICAL III'AI)ITEtI'AI11CE SUM'I'1RY
For 'the'onth of iIarch 19 81
DATIr'. S YS'1 A..t! CO'I"0" FNT IMMATURE OFI'~'A IllTE!tANCE
EFFECT ON SP "EOPERATIOl1 OF
TIIE",RFACTOR
CAUSF. OF
l I tlLFL"i)CTIOH
RESI)LTS OF
Nu<LFUNCTION
O'I Tl'~'.r".ltlic h
TO PRFCLUDEPZCURPZNCE
ttLI OJ
3-27-,81
I tt 1 01CI VJ
RBCCW
gECW
RBCCW
Dttrrt.tAU '4 \r ru
t A tn ttttttli I V CDSludge Tank
FCV-67-50
A D.W1 ~ AirCom ressor
I h-7A 7'Avh tv a u
'rt1 t ttt 4 t 4c JOdl D l Jctt Jllb
Valve Closed
Stopped UpLine
Wil 1 .Int ActIn On LowLevel
tl(A* ~
N)A
H')~ tg
ljl
1
1. 1 nn ~ C r I nl. w nnL JVQt V ~ k\ tlat ~ t)
Valve Was inClosed Pvs Jtlont
Blockage
BaII wires onLimit Switch
"Flo'at Not Sr ickinn
Stoppage
P lugged I.ine
Switch Will NotFunction
Backflushed FloatsTR:7187778
NoneTR Penn~ I t
BackflushedTR tll208404
Installed LimitSwitchTR !I208407
! 8( !:c'!'1p'.1 )KC)IJd 1.('AI )I.~T.'"P"JUDICE SU~ V~(Y
For thc Month of - )')arch 19 81
DATI'. 8'iS') r.) I CO"(PL~')~i')i011 Sr"'I
TION OFLACTO)t
ChliSE OF
) )ALEUII(.'TIONRHSUI:I'S OF
tP.I.FUNC')'ION
ACTIOII T:~HEI)
TO FRECLUDERECURRENCE
2-? 3-81
3-?-81
Fuel PoolCooling
I.PC IN(i Set
Pump 1)otor 3B
AX liG Set
Pump Out ofAlignment
Lubrication
N/A
H/A
Bent Shaf t &
Worn Par ts
Coupling NeededGreasin
Unkno~m
Unkn oem
Replaced Shaf t,Impel)or, Bearings,Sleeves, Wear Ringsand ItepackedTR 8136719
Greased CouplingTR I)182062
')-2-81 LPCIliG Set
3EA IIG Set Lubrication N/A Coupling NeededGreasin
Unknown Greased CouplingTR 8182082
3-3-81 D/C Air Coapressorl!l Leakage
~ ~ N/A Pilot UnloaderBad
Air Line Leak Repaired PilotValv'R
I/22 1503
3-11-81 CRD liodule 38-43 liechanicalProblem
, N/A Seal Problem Will Not Withdraw No Problem FoundWith Normal Pressure TR 8221559
3-11-81 RCIC 3-71-6A Stem Leak Loose PackingGland
Leakage Tighten PackingTR L!221526
3-11-81 CO> Storag& FireProtection
Cardox ValveA
Venting toAtmosphere
N/A Unknown Unknown NoneTR //220510
3-18-81. IIP CI 73-16 Leak„~
Loose Packing . Packing Leak Tigl>ten Packing.TR 8205407
3-17-81 )/PCI Turbine Exhaus Disc Blown N/A Ruptured Disk Blown Disc Replaced DiscTR 8205408
3-18-81 FireProtection
Valve3-26-1132
FlangeCracked
~ I N/A Unknown Unkno~m New FlangeTR 8199138
~ ~
~ ~
~ ~
~ ~ I
~ 4
~ ~
CSSC F UTPIF'IT
Bf(OIJNSi
5L<$
For tl
iiERRY: Ui;Li!AR Pl 'IIT Qil": )a.:
IANICAL IIAINTENANCE SUt'~fhRY
ie Honth of- ~ Harch 19 81
DATE SYS'ia.if COI IPO".1ENT llATURE OF
t IAIttTENANCE
EFFI'.CT GN SAFI?
OPE TION QF'l
'1"ifE: REACTOR
ChUSE OF
l IAI.FUIJCTION
RESVI.TS OF
IIALFUNCTION
AC'1'10:I TAKE:I
TO PIIECI.UDERECUIl"F"C".
2-28-8 EECIJ Strainer C3 Strainer Hal-Iunction
Gears Out ofAlignment
Gears Grinding l)isassembled and0
Turned Gear 180 .
TP, 1 204851
3-20-8'-14-8
FireProtection
RIIR
8" Strainer13asket
IUIRSIJ Pumps
DamagedStrainer
Unknown
"N/A ~
V/A
Unknown
Unl'nown
Strainer Damaged
Unknown
Complete perDCR P2473TRi'3182041
Performed !Cfl 29TR P 198828
3-14-8 EECIJ C3 EECIJ Pump Pump Not Mork-ing Up toRe uirements
1 J/A Coupling Out ofAdjustment
Pump Not HeetingSI Requirements
Adjusted Coupling toRead .048TR Prl99464
3-14-8 F.ECM D3 EECIJ Pump Pump Not IJork-ing Up toRe uirements
Unknown Not Pumping Itut4,000 gpm
Checked Coupling tOkay IIHI-29'fR 8199466
3-22-8 RIIR 3C RIIRSIJ Pump Low Flow /A Unknown Pump Not Pumping Iebuilt PumprR 8148095
3-16-8. I? ECIJ C Strainer lligh DP , '/A " 'nknown Unknown 'low Going Through; 6 D Strainer)ischargerR 8103793
CSSC E UIPffENT
SYSTEM
Unit ]
3-1O StandbyLiquidControl.
Standbv3-17I.iquidControl
n v « t««v' tI L LIIICILyLVContain-ment
Unit
3-3 RadiationHonitoring
StandbyLiquidrnnt rnlt
3-10 FeedwaterControl
3-16 Core Spray
3-12 emergencyf'qttinmentCoolingWater
3-1 7 Emornen('vEquipment(«e«t I « tt ~ ~
NATURE
OF
MAINTENANCECOMPONENT
TE-63-4 Replace
Ronl aceT.T-63-1 R
I'al ihrot oPT-f/. ( 1~ L Cl ~ Jk
Repair/Replace
CalibrateTS-63-4
FH-46-1A Replace
RepairFT-75-21
Dm ca 1DDCL Vl JCQPT-67-68
D 4 I/\ 1OC PClLL / IJCll. ~
P(f(I-67-R 11 onlnro c'tJi tr hoc
tt
BROWNS;
INSTRI
'ERRY NUCLEAR PLANT UNITf
fENT HAINTENANCE SAfffARY
HONTff OP Harch 19 81FOQ T1I
CAUSE
OF
1fALFUNCTION
N SAFE
ON OF
CTOR
EFFEC) 0RESULTS OF
HALPUNCTION
False IndicationShorted toGround
N ne
'I (
Non
t(
Nnn
Faulty Indicator Did Not Agree WithRedundant Indicator
Indicated False HighPressure
Tnst rttment Drift
I
N'aulty FlowControl Honitor
High'low Alarm
Palse Low AlarmSetpoint Driftne
Did Not Indicateteal - ow
Paulty CircuitCom(potient
ne
Faulty Amplifier False Indicationof Core Spray
ne
N
II
,
I
No
II
Tnrnrrert FlowIndication
6R 1fad RadAmplifier, 12BHad InstrumentDrift
~ AC
Paultv Switrhes Alarm 'ant(1�(f Nnt Cl onne
ACTION TAKENTO PRECLUDE
RECURRENCE
None
None
None
None
~ ~
None
None
None
None
Nnno
e as
37
OUTAGE SIR&QKY
MARCH 1981
Preparations continue for the upcoming unit 1 end-of-cycle 4 refueling/
torus modification outage presently scheduled to begin April 10, 1981 (duration
currently estimated't 104 days). Preparation work is also underway forthe'nit
2 outage required to accomplish ECN P0275 — unit station service transformer
modification. This unit 2 short outage is scheduled to begin. shortly after~
~
the start of the unit 1 cycle 4 outage and will .last approximately 23 days.
Significant work in progress at the end of the month includes:
1. ECN P0314 — This modification provides improved post accident
sampling facilities (PASF) for reactor liquid and atmospnere.
Preliminary work is in progress in preparation 'for this .modi-
fication to begin. The instrument mechanics shop in .the unit
3 turbine building has been relocated to allow access for the
PASF.
1C'd-P42'TB-=.Unit-station setnice-ttansdctaenatodidication*" r
Excavation work and installation of conduit and rebar's in
progress. Skid plate fabrication is complete for all 3 trans-
former pads.
3. ECN P0262 — Union Cordova 500kV line - This modification
installs new terminal facilities for a new 500kV transmission
line. Pork is complete on installation of the foundation for
the 500kV PCP and associated BUSS supports. Beginning ez-
cavation at switchyard. cable tunnels for conduit runs.
38
OUTAGE SlRMARY. (Continued)
Harch 1981
4.. ECN P0238 — Condensate Storage Tanks -~=Two additional 500,000
gallon storage tanks have been constructed as a result of thi4
modification. Conduit and cable runs 'fox,'alve and level controls
are approximately 80% complete. ~Inter~ior tank coatings have bee@
applied and .forced curie is in progress.
5. ECN P0027 - Unit 1 Spent Fuel Storage t'ool is 'under'going a setond
partial completion of the. high density fuel storage rackinstalla-'ions.
The original fuel storage racks have been removed and'ar'e
awaiting packaging for shipment as radwaste'. 'Six high density
fuel storage system modules (13 c 13 array each) have recently
been installed. These are in addition. to the '5 HDFSSmodules'nstalled
in August of 1979'ull core, unload capabilities. are'ow
available .for the outage.
&;—.SCN.=.F9078=.—..;Mechanid~a.-prefabr'xc:idion«worK''-is ini progress;.foi>t,e:
fire protection modification at thei pumpiintake structure.
7. ECN Ll!329/L1960 - Cooling tower modifications are in progress.
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