ML18025B442
| ML18025B442 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/01/1981 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B441 | List: |
| References | |
| NUDOCS 8104170530 | |
| Download: ML18025B442 (44) | |
Text
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
'I t
TABLE OF CONTENTS Operations Summary...
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Refueling Information Significant Operational Events
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Average Daily Unit Power Level
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15, Operating Data Reports Unit Shutdowns and Power
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Reductions.
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18 21 Plant Maintenance
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25 Outage Summary
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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 containing approximately 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 pool without'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, rod limited.
Reactor thermal power at 99%,
maximum flow, rod limited.
3/04/81 1500 Reactor thermal power at 98%,
maximum flow, rod limited.
3/06/81 2300 Reactor thermal power at 97%,
maximum flow, rod limited.
3/08/81 0140 0300 0310 0400 0420 Commenced reducing thermal power for (MSIV closure timing) 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 turbine control 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, rod limited.
Reactor thermal power at 98%.
EHC vibration limited.
Reactor thermal power, at 97%,,EHC,.vibration limited.
Reduced thermal power to 85% for turbine control valve 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 1012 1030 Commenced reducing thermal power for a control rod pattern adjustment.
Reactor thermal power at 64%, holding for control rod pattern adjustment.
All rods out.
Control rod pattern adjustment
- complete, commenced PCIOMR.
3/18/81 2300 Reactor thermal power at,99%,
maximum flow, EOC-4 coastdown.
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 the1001 breaker tripped los:ing unit preferred power and i
locking out reactor feedwater pumps and. xecirculation MG controls due to loss of power to controller.,
Reactor feedwater pumps and recixculation MG sets back to normal and unit prefez;red power placed on 1002 breaker, conmlenced power ascension.
Reactor thermal power at 98%,
maximum flow, EOC-4 coa.'tdown e
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3/21/81 0115 0155 0230 0700 Reduced thermal power to 85% for turbine control valve 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 0825 0900 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-4 coastdown.
3/25/81 2300 Reactor thermal'power at 99%,
maximum flow, EOC"4 coastdown
~
3/26/81 1500 2300 Reactor thermal power at, 98%,
maximum flow, EOC 4 coa 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 control valve 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, rod limited.
3/20/81 1225 1235 1240 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, rod limited.
Reduced thermal power to 91% for turbine control valve tests and SI's.
Turbine control valve tests and SI's complete, commenced power ascension.
Commenced PCIOMR from 96% thermal power (sequence IIEII )
Reactor thermal power at 99%,
maximum flow, rod limited.
3/26/81 1555 1650 220.0.
Reduced thermal power to 82% for removal of Cl and C2 high pressure heaters from service for relief valve maintenance.
"C" string high pressure heater isolated, reactor thermal power at 82%, holding for relief valve maintenance.
"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, rod limited.
Reduced thermal power to 83% for removal of "C" string high pressure heaters from service for maintenance on heater drain line.
"C" string high pressure heaters back in service, commenced power ascension.
Reduced thermal power from 96% to 82% for turbine control 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, rod limited.
(3)
Reactor Scram No.
117 from 99% thermal power, turbine trip during work on thrust bearing wear detector.
~Si ~nific:ant Operational Events Unit 1 Date Time Event 3/29/81 2300 Reactor thermal power at 97/,
maximum flow, EOC-4 coastdown.
3/31/81 2400 Reactor 'thermal power,at 97K, maximum flow, EOC-4 coastdown.
Si nificant 0 erational Events Unit 2 Date Time Event 3/01/81 0001 0910 Power ascension in progress from 0 power.
(Startup from scram on February 28, 1981).
Commenced PCIOMR from 64% thermal power (sequence IIBII) 3/02/81 2010 2047 2225 Reactor thermal power at 99%,
maximum flow, rod limited.
Both recirculation pumps tripped reducing reactor thermal power to 36%.
SI 4.6.A.6 and 7 complete for "A" recirculation
- pump, "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" recirculation
- pump, "B" recirculation pump placed in service.
Commenced power ascension.
Reactor thermal power at 87%, holding to maintain core limits.
Commenced PCIOMR from 87% thermal power (sequence IIBII) 3/04/81 0700 1500 2300 Reactor thermal power at 99%,
maximum flow, rod limited.
Reactor thermal power at 98%,
maximum flow, rod limit;ed-;. -
Reactor thermal power at 97%, maximum flow, rod limited.
3/05/81 0700 1500 2300 3/07/81 0408 1430 1720 2115 2142 Reactor thermal power at 98%,
maximum flow, rod limited.
Reactor thermal power at 99%,
maximum flow, rod limited.
Reactor thermal power at 98%,
maximum flow, rod limited.
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 isolation and 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 (sequence I IBlI) 3/09/81 2130 Reactor thermal power at 99%,
maximum flow, rod limited.
10 6~inilicant~Opatatinnal Evanta Unit 2 Date Time Event 3/11/81 2204 2237 2243 Commenced reducing thermal power to test MSIV 1-26.'eactor thermal 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, rdd 1:imited.
3/13/81 2200 2259 Commene;ed reducing thermal power to remove both recirculation pumps from service fox bruah replaCe-ment oii recirculation 'Ig set.
Reactor Scram No.
116 'rom 50% therma3.
power due to high water level signal which caused'he main turbine. and reactor feedwater pumps to tx'ip and reactor.
scram on an indicated high water level.
3/14/81 131'6 1515 1830 1915 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 0112 0200 0800 Commenced reducing thermal power from 87X p~ower" for contro3. 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'e IIBII)
Reactox thermal power at 99%,. maximum flow, rod limited.
3/17/81 0600 1500 Reactor thermal power at 98%,
maximum flow, rod limited.
Reactor thermal power at 97%,
maximum flow, rod limited.
3/18/81 1018 1045 1335 1355 Commenced reducing thermal power fox a contro3.
rod pattern adjustment.
Reactox'hermal power at 73%, holding for control rod pattern adjustment.
,Contro3. rod pattern adjuc>tment
- complete, commenced power ascension.
Commenced PCIOMR from 89% t'hex'mal powex'sequence I
Idyll
),
Si nificant 0 erational Events Unit 2 Date Time 3/28/81 2035 2358 Event Commenced rod withdrawal for startup.
Reactor Critical No. 130.
3/29/81 0455 0517 1200 Rolled T/G.
Synchronized generator, commenced power ascension.
Commenced PClOMR from 67% thermal power (sequence IIBlI) 3/30/81 2030 Reactor thermal power at 99%,
maximum flow, rod limited.
3/31/81 1245 1320 1930 2400 Reduced thermal power to 87% for control rod pattern adjustments.
Control rod pattern adjustments completed, commenced PCIOHR (sequence "B").
Reactor thermal power at 99%,
maximum flow, rod limited.
Reactor thermal power at 99%,
maximum flow, rod limited.
~EI ~nifinant OEaratienal Evente Unit 3 Date Time 3/01/81 0001 0100 0105 0230 Event:
Control rod pattern adjustment
- complete, in'cre'fasted
'eactor therma.'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 out of 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,.rod limited.
3/03/81 0419 0615 0705 1005 Reduced therma.'!. power to 86X, to remove "P." condensate demineralizer vessel from s< rvice, to check'essels elements and resin t:rap for break through;
~also to
'ackwash and precoat:
condensate demineraliz'er vessels Il]l1II and IIJ II Condensrate demineralizer proble'm
- resolved, commenced power ascen ion.
Commenced PCIOlifR from 96X thermal power '(co'ntrol'ell core).
Reac:tor thermal power at 99%,
maximum flow, r<>d limited.
3/07'/81 2340 KH 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 valve tests 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, rod limited.
Reactor Scram No.
94 from 99% thermal power d'ue to kll flux on "F'I and "C" APRN, caused b'y connection failure on the sens:Lng line of the turbine pressure regulator (equipment, malfunction).
3/09/81 0935 2230 Commenced rod withdrawal for stax'tup.
Reactox Critical No.
106<<
3/10/81 0242 0310 2210 2300 Rolled T/G.
Synchronized gene.rator, commenced power ascension.
'educed thermal power from 73% to 64% for control rod 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 cell core).
Reactor thermal power at 99%,
maximum flow, rod limited.
3/12/81 1445 1520 2130 2300 Commenced reducing thermal power due to high river
~
~
hT.
Reactor thermal power at 73%, holding due to high river hT.
Commenced po~er ascension from 73% thermal power.
Commenced PCIOi~K from 97% thermal power (cont'rol cell core).
3/14/81 1150 Reactor thermal power at 99%,
maximum flow, rod limited.
3/15/81 0001 0036 0040 0135
--=,.-..-0200- -- ~
Reduced thermal power to 82% for turbine control valve tests ans SI's.
Turbine control valve tests and SI's completed, commenced power ascension.
Reactor thermal power at 96%, holding for control rod drive exercise.
Control rod drive exercise
- complete, commenced power ascension.
.-.Reactor"'thermal= power-ae:'99%;
Maximum flow,'od'imited.
3/20/81 2355 Commenced reducing thermal power for turbine control valve tests and SI's.
3/21/81 0015 0028 0035 0105 0115 0415 0740 0743 Reactor thermal power at 87%, turbine control valve tests and SI's in progress.
Turbine control valve tests and SI's complete, commenced power ascension.
Reactor thermal power at 91%, holding for control rod drive exercise.
Control rod drive exercise
- complete, commenced power ascension.
Commenced PCIOifR from 97% thermal power (control cell core).
Reactor thermal power at 99%,
maximum flow, rod limited.
Commenced reducing thermal power for unit shutdown due to high level alarm in east side scram discharge header (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 0750 0835 Commenced power ascension from 73%
therm@1 ipoker'.
Reactor t'herma.'L power, at 99%,
maximum flow, rod limited.
3/25/81 1720 1755 Commenced reducing t:hermal power due to gen'erAtoL bus duct cooling fan siinoking.
Reactor therma.'L power at 54X.
3/26/81 0700 15OO 1800 2200 Reactor therma.'L pbwer Reactor thermal power ing fan problems.
Bus duct cooling fans poweir ascension.
Commenced PCIO],"R from cell. 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, rod limi.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. turbine control valve tests and SI's.
Turbine control y'alve tests and SI's complete
.commenced-power.,ascension Reac:tor thermal power't'99X.;
maximum flow, rod limi.ted.
3/30/81 0357 0555 0625 0915 1130 1700 Reduced reactor thermal power to 71% when 3iA reactor.
feedwater pump tripped '(hi vibrat;io'n).',
Roll,ed 3A reactor feedwater pump for vibiat'iotIi cihecks,,
3A reactor feedwater pump tripped on high v'ibr'ation.
Rolled 3A reactor feedwater
- pump, commended power asceinsion.
Commenced PCIOl!fR from 93% thermal power ilcontrol cell. core).
Reactor thermal power at 99%,
maximum flow, rod limf.ted.
3/31/81 2400 Reactor thermal power,at 99%,
maximum flow, rod limited; (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-NetI 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 ncJfcsl 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
'AY 17 l9 OP, 21 23 24
)5 26
-AVERAGE DAILYPOWER LEVEL')))IWe*Net) i 1048 999 1066
~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 to thc nearest whole n>c;a)vat t.
I'>/77>
17 AVERAGE DAILYUNITPOWER UsVEL 50-296 DOCKET 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
)
1079 17 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-NctI'ol'ar!1 \\lay I>> thc fc})iiltl>>I.>>I i>>th. Cii>>IP>>lc lo lhc Ilcarcst Ivhiilc>>lc~aN:Itt.
I'II77 )
18 OPERATING DATAREPORT DOCKET NO.
DATE 4-1-81 COMPLETED E>Y Ted Thorn TELFPfIONE 205-729-6846 OPERATING STATUS Notes
- l. 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:
1098.4 1065 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 744
- 15. Unit Reserve Shutdown ffours 0
- 16. Gross Thermal Energy Gencratcd (MWH) 377- 054
- 17. Gross Electrical Energy Generated (l>IWII) 786,760 2,226,870
- 18. Net Electrical Energy Generated (MIVH)
- 19. Unit Service Factor
- 20. Unit Availability Factor 100.0 99.1
- 21. Unit'Capacity Factor (Usi>>g i>IDC Net)
- 96. 5 94.4
- 22. Unit Capacity Factor (Using DER Net) 96.5
- 94. 4
- 23. Unit Forcegc Rate 0
0.9
- 24. Shutdo>vns Scheduled Over Next 6!>Ionth>> (Type. Date. and Duration of Each):
Refue1in A >.il 1981 58,442 56, 950,15~
5,115.29 99 972 699 32,990 160 32,035,015 61.8 61.8.
- 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'riort>> Con>n>ercial Operation):
Fureca>>t Ach>cved IN ll'IAL ClfIT ICA LIT Y INll'IAL ELECTRICITY CO.'VDIERCIAL OPI!RATION (o/77)
OPERATI>NG DATAREPORT OPERATING STATUS DOCKET >NO.
50 260 CO.'>IPLETED BY ~~It'horn TELEPHONE M>~~29-6846 bootes
- 1. 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):
1098.4 7
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 1'60 Ii. Hours In Reporrie8 period
~-1'.*
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Liine 689.75 i i, 2040.99
.31 781.95
- 15. Unit Reserve Shutdown Ilours 0
, 0
- 16. Gross Thermal Energy Gencratcd (ilfWH)
- ! 092 498 6 232 974, 99 803 617
- 17. 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 59.6
- 20. 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 51.0
- 2. Unit Capacity I'actor IU5i>>g DER hct) 84.9 88.3 5r.0
- 23. Unit Forced Out:> c Rate
. 7.3.
'5.5
~
31.5
- 24. 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 uf Start>>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 Thorn TELEPHONE ~~o-46 Notes
- l. 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:
1065 7..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 1 573.99
- 15. Unit Rescrvc Shutdown floors 0
- 16. Gross Thermal Energy Gencratcd(MWH) 2 207 040 4 488 641 Ii. 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 9.4
- 24. 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 6
0 788 6
26 050 980 25,289,990 7
66.3 66 '
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<llICALITY INITIAL ELECTltlCITY COilitii I(CIAL Ol'E RATION (i)/77)
UNITSIIUTDOWNS AND POWER REDUCTIONS l
REPO T MON'fll I
DOCKET NO..
UNll NAME DArE COhll'I.ETED IIY TI!I.EI'IIONE 50-260 r- -81 I e(I.
I holll.
l)ale fP J
CfI f
Lie I:.
Rc t
cnscc vent ort ~
ff CP IJI' c'
F IJ O
Cause A Corrcclivc Action lo Prevent Rccufrcncc 170 3-&81 B
HSIV Closure Timing (SI 4;7.D.l.b.2 and SI 4.1.A.-11) 171 3-17-81 Control rod pattern adjustment F: I'orccd S: Schcdpled
()/77)
Reason:
A.EIIuipmcnt Failure (Explain)
B.Maintenance or Test C. Rc fuelinI; D.Rct,ulatory Restriction I'i Opcfalor Training h. Liccnsc Fxanthtatlon~
F.Adtninistrativc f
G Operational Error (Explain)
I I Other (Explain) hlcthod:
I hlanual 2.hlanual Scram.
3-Automalic Scram.
4.Other (Explain) 4 Exhibit G - Instructions for Preparation ol'Data linlrySheets I'or Licensee fvcnt 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
ccnscc vcnI nnrl A r
r.0 ~
C Q G
Cause Lrr. Corrective Acti(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
1 Jl
~Jl A
n ral 4 1 n nnvI nv'Illa 11n CT ll 1
d 1 1 11 ~ILLS Ir4LLvLllILll5vL ~ I ~ L ~
board MSIV continued to go closed aftet pushbutton was released, resulting in a 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 turbine and reactor feedwater pumps to trip.
Equalizing valve on level indicator was open
~
Control rod adjustment I
F: Forced S: Scheduleil Reason:
A Equipmcnt Failure (Explain)
Bt.h(aintcnancc ol Test C Refueling ii.iRcgulatory Restriction I!.Operator Training k Lii:ense Fxamination F.Administrative G upcrat(ona( Error (Expiain)
I I Oilier (ExplJill) 3 Method:
i h(anual 2.Manttal Scram.
3.AUtolll'll!cScfJnl.
4 OlhCf (I'xpiJIII)
Exhibit G Instrui.lions for PICp:IIJIniil ol Dal J Entry Siiccts I'or Lieciisee Event Report (Ll!R)File (NVREG-036rl-)
5 Exhi'Ml I - Sa;Ile Soliree
Olt'iVS AND POIVER REI)UCTIONS UNITSIIUTI)
RT hlON fll Ilarch REPO l)OCKET NO.
50-260 UNI'I' AhlE I)ATF 4-2-81 COhlPLETEI)!IY Ted Thorn I)atc
~A I
CI J
h a
V Vi Re cciiscc vciil pofl Cause A ('orrcclivc Aclioiilo Prevent Rccurrcnce 184 3-28-"gl 16.42 Scram due to turbine trip while working on thrust bearing wear detector I': Fiirced S: Schedulcil (9/77)
Reason:
A.Equipmcnt Failure (Explain)
I).hlaintenancc or Test C.Refueling I).Regulatory Rcstri<<lion, I L Opcral<ir Training 8; Liccnsc Exaniination F-Administ rat ivc G Operational Error (Explain)
I I Other (Explain) hlcthod:
I MJnual 2 hlanual Scram.
3 Auloinalic Scram.
4 Otl)cf (ExplJiii)
Exhibit G - Instructions for Preparation of l)atJ Entry Sliecls Ior Licciisee Event 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 UllIT u
ELECTRICAL HAIHTENANCE
SUMMARY
l For
'he ?lonth of Narch 19 81 D""e System Component Nature of llaintenance Operation of The I Reactor Cause of
."fal function Results of a~la 1func tion Action '1'aken To Preclude R currence 3/6/81 EEC14 EEL North header low flow alarm relay (67AL1)
Received a
false low flow annunciation on panel 9-20 for units
'1
&~ 3 None Bad low flow alarm relay coil.
Low flow alarm inoperable.
Replaced relay, alarm system operated pro-perly.
TRI't158585 3/8/81 Fire pro-tection Smoke detector (XS-39-104AA)
Received flase alarms on panels25-325 and 9-8.
!i None!
Increased sensi-Smoke detector actu-tivity of smoke ated 3 false alarms detector.
in a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period.
Replaced the smoke
- detector, performed SI4.11.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,'the Honth,of Harch 19 81 System Component N,.ture of llaintenance Ekred Opcl) t on Sake ation of Reactor Cause of Halfunction Results of Halfunction chic tion Taken To Preclu"e R'currence 3/4/81 Diesel Generators "HVST2 coil" EHX 3 in D/G 3B start failure backup circuit None "llVST2 coil" found to be bad during redundant start test.
This solenoid coil was'ot deteriorated to the point of mak-ing the solenoid inoperable.
The
-coil did cause a
spike on the oscillo graph trace.
Replaced the bad coil, solenoid operated properly.
TR//220503 3/8/81
. Diesel Generators D/G 3A fuel oil pressure annunciator Received a
false fuel oil'ressure annunciation.
Nones Bad annunciator circuit card.
Received a false annunciation.
Replaced the bad circuit card, annunci-ator operated properly.
TRI'I204848 IV 3/10/81 Residual heat re-moval FCV-3-74-74 FCV-74-74 feed er breaker tripped after valve closed during perform ance of SX4.5.B.l.c Unit in limitin condition for operation (TS3.5.B.7)
Unknown RllR valve FCV74-74 feeder breaker trip-ped after the valve closed while per-forming SX4.5.B.1.C The valve operating current was measured and found to be accep-table.
No loose con-nections were pound in the breaker'com-partment.
The valv has been cycled daily, through 3/18/81.
)
TR8204839 LER8BFRO-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 Diesel generator Component 3A D/G annunciator Nature of
';taintenance D/G alarms inoperable Etl Get, on SQre opera,'tion of The,'coactor None<
t3 Cause of
>talfunction Bad annunciator circuit card Results of Na 1func tion Annunciator inoperable Action Taken To Preclude R'currence Replaced bad circuit card, annunciator.
operated properly.
TRfI204821 3/13/8 Rad waste RHR pump room LA-77-25C flood level would not Mnnunciator test r
t I n<<n LA II IJL None Loose connec-tion on annunci ator cxrcuxL" Cnl Annunciator inoper-able.
Corrected connection, annunciator operated rorteiltr TR ($221 558 3/17/81 tlt Itl tent Itt Vntl'3 71
/. /.
<<\\rv& r&
f'vnttrtA nn Vt <<r<<ttt'Q vr ~
FCV-73-44 "Inboard discharge II val've Valve motor lead "A2" was grounded at taped connectior in limitorntte connection com-partment.
Valve was placed in open (operable) po-sition while the conlductor was r'G=
insulated.
Retaped the conductor performed ENI 71, 18, and 18.1, valve Operated
- prOperly, TRf/2O5S09
> 3/17/81 gener'ators D/G 3C Received a
"control power CC a nnJn VLL
<<I ~ I ~IU~ ~t J.<<t tion None t
Bad coil on NVR relay and loose 3558 annunciato card.
Received a false n ~ J A
t jI
<<IIIIIUIIIJ<<tl J.OII I ht<<tt the control power was off.
Replaced the baa
.relay COil andt tight-ened the annunciator
- card, the annunciato I
operated properly.
TR/~205434
'/17/81 480 Volt shutdown nnr,rer Hotor genera-l.or t)a t 3DA Received a
beneLatoi ut ~
dervoltage alarm for no apparent rea-son.
None Bad annuncIatol.
c<<trd =
Received a false undervoltage alarm.
Replaced the bad annunciator
- card,
-annunciator checked OK.
TR//205410
CSSC EOIIIPHEHT NNU!'NS'BNZaT NUCLNAZ PLANT UNIT ELECTRICAL I~IAINTEN/ACE SmIIIARY II JIL I
I D
I System Component Nature of ala'ntcnancc IMtec!t on Sate Opej'ation of Th,i Iicactor Cause of
'.Inlfunc cion Results of Na 1func tion Action Taken To Preclude R'currence 3/19/81 Diesel 38 D/G Generators Received a
overspeed annunciation on 38 D/G None Bad annunciator card Received a false overspeed annuncia-,
tion.
Replaced bad annuncia-tor card, annunciatioi tested and cleared properly.
TR8205511 I3/20/81 I
I Air-condi-tioning (I'oo1ing-heating) 38 control bay 38 control bay hiller chiller trippe None.
K '
A Oil bypass valve open Chiller tripped on low oil pressure.
Closed oil bypass valve and adjusted oil regulator valve, chiller operated properly.
TR8220520 (I3/22/81 IIPCI Low level switch on gland seal condenser Low level switch inoper-able.
None Level switch 73-158 was sticking Condensate pump con-trolled by LS73-158 would not operate automatically.
Freed the switch, the pump 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>" rE OPERPjTIOiV OF TiiE <REACTOR C>>USF O;
t tALFNICTIOtI RESUI.TS OF
>~<<XLFUHCTIO<v<
ACTlOti T<".KE:I TO Pi(ECI.UDE r<FCUIIREtICE l! Fj>>e iir<>toetioh L
Iti V-26-95fi Broken Pin 1'fi Roll Pln Broken Frozen Valve Replaced
)'ins TP
<<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 Header 2
NATURE OF
!-DXI!ITEIIAI!CE Leakage Leal:age EFFI'.CT GN SP2'E Opr.RATION 01'II E 'REAC1OR
'/A N/A CAUSE OF IIALFUIICTION Loose I'acking I.oose Packing RESUI;I'S OF MAI,FU!!CTION Leaking at Stem Packin leal:ing at Stem Pack:in~
~:C 110<1 IA.'r.h TO PRECI.UDE RECI!RPJ HCE Tighten Packin TR !220966
< Tighten Packing TI! ir'220967 2-.19-83 HI'CI RCIC c
Check Valve Check Va lve Test N/A Unknown Unknown Perfor'med SI 3.2.7 on Check Valve'R ff103787 3-4-81 RBCCM Surge Tank Float Hangs Unknown Bene Stem Mas Bindin Straighten Stem TP ff220983 3-7-81 t
3-8-81 CRD r
CRD SDV Drain 6 Vent Valve CRD 34-23 Frozen Valve Morn Parts N/A N/A Non-lubricated Valve Stem Strainer Dirty Non-lubricated Stem Unknown Lubricated Valve Stem TR fi204516 Changed Strainer TR ~'220873 3-9-81 EF.CI" Fisher Contro Valve 50-51.-
Dirty Filter N/A Dirty Filter Unknown Replaced Filter ir 6750-6751 TR fi220845 3-14-8)
EECM FCV 67-51 Change Out St ainer Filter Strainer Dirt ~
Valve MillNot Close Installed New Filter TR Pc221554 3-13-8I Fut.l Pool Cooling.'elium Leak Detector Valve 2B FPC Heat Exch.
Hook Up Helium Leak N/A Need to Hook Up I!elium Detectoi Unknown Removed 1/2" Tubing and Hooked Up Tester TR 8216814 3-20-8.
RBCCII Surge Tank Level Switch Heeds Adjust-ment N/A H
Level Switch Out of Adjustment Swatch Stic! s Adjusted Swit'ch TR 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 OF I'~'A IllTE!tANCE EFFECT ON SP "E OPERATIOl1 OF TIIE",RFACTOR CAUSF. OF l ItlLFL"i)CTIOH RESI)LTS OF Nu<LFUNCTION O'I Tl'~'.r".lt lic h TO PRFCLUDE PZCURPZNCE tt LI OJ 3-27-,81 I
tt 1
01 CI VJ RBCCW gECW RBCCW Dttrrt.t AU'4\\rru t
A tn tttt ttli I V CD Sludge Tank FCV-67-50 A D.W1 ~ Air Com ressor I h-7A 7'A vh tv a u
'rt1 t
ttt 4 t 4 c JOdl D l Jctt Jllb Valve Closed Stopped Up Line Wil 1.Int Act In On Low Level tl(A
- ~
N)A H')
~ tg ljl 1
- 1. 1 nn ~
C r I nl. w nn L JVQt V ~ k\\ tlat ~t)
Valve Was in Closed Pvs Jtlont Blockage BaII wires on Limit Switch "Flo'at Not Sr ickinn Stoppage P lugged I.ine Switch Will Not Function Backflushed Floats TR:7187778 None TR Penn~ I t Backflushed TR tll208404 Installed Limit Switch TR !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')i 011 Sr"'I TION OF LACTO)t ChliSE OF
) )ALEUII(.'TION RHSUI:I'S OF tP.I.FUNC')'ION ACTIOII T:~HEI)
TO FRECLUDE RECURRENCE 2-? 3-81 3-?-81 Fuel Pool Cooling I.PC I N(i Set Pump 1)otor 3B AX liG Set Pump Out of Alignment Lubrication N/A H/A Bent Shaf t Worn Par ts Coupling Needed Greasin Unkno~m Unkn oem Replaced Shaf t, Impel)or, Bearings,
')-2-81 LPCI liG Set 3EA IIG Set Lubrication N/A Coupling Needed Greasin Unknown Greased Coupling TR 8182082 3-3-81 D/C Air Coapressor l!l Leakage
~ ~ N/A Pilot Unloader Bad Air Line Leak Repaired Pilot Valv'R I/22 1503 3-11-81 CRD liodule 38-43 liechanical Problem
, N/A Seal Problem Will Not Withdraw No Problem Found With Normal Pressure TR 8221559 3-11-81 RCIC 3-71-6A Stem Leak Loose Packing Gland Leakage Tighten Packing TR L!221526 3-11-81 CO> Storag
& Fire Protection Cardox Valve A
Venting to Atmosphere N/A Unknown Unknown None TR //220510 3-18-81.
IIPCI 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 Disc TR 8205408 3-18-81 Fire Protection Valve 3-26-1132 Flange Cracked
~
I N/A Unknown Unkno~m New Flange TR 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 lIAI.FUIJCTION RESVI.TS OF IIALFUNCTION AC'1'10:I TAKE:I TO PIIECI.UDE RECUIl"F"C".
2-28-8 EECIJ Strainer C3 Strainer Hal-Iunction Gears Out of Alignment Gears Grinding l)isassembled and0 Turned Gear 180 TP, 1 204851 3-20-8'-14-8 Fire Protection RIIR 8" Strainer 13asket IUIRSIJ Pumps Damaged Strainer Unknown "N/A ~
V/A Unknown Unl'nown Strainer Damaged Unknown Complete per DCR P2473 TRi'3182041 Performed !Cfl 29 TR P 198828 3-14-8 EECIJ C3 EECIJ Pump Pump Not Mork-ing Up to Re uirements 1 J/A Coupling Out of Adjustment Pump Not Heeting SI Requirements Adjusted Coupling to Read
.048 TR Prl99464 3-14-8 F.ECM D3 EECIJ Pump Pump Not IJork-ing Up to Re uirements Unknown Not Pumping Itut 4,000 gpm Checked Coupling t Okay IIHI-29
'fR 8199466 3-22-8 RIIR 3C RIIRSIJ Pump Low Flow
/A Unknown Pump Not Pumping Iebuilt Pump rR 8148095 3-16-8.
I?ECIJ C Strainer lligh DP
, '/A "
'nknown Unknown
'low Going Through 6
D Strainer
)ischarge rR 8103793
CSSC E UIPffENT SYSTEM Unit ]
3-1O Standby Liquid Control.
Standbv 3-17 I.iquid Control n v << t<<<<v' t I L LIIICILy LV Contain-ment Unit 3-3 Radiation Honitoring Standby Liquid rnnt rnl t
3-10 Feedwater Control 3-16 Core Spray 3-12 emergency f'qttinment Cooling Water 3-1 7 Emornen('v Equipment
(<<e<<t I << tt ~ ~
NATURE OF MAINTENANCE COMPONENT TE-63-4 Replace Ronl ace T.T-63-1 R I'alihrot o PT-f/.
(
1
~ L Cl
~ Jk Repair/Replace Calibrate TS-63-4 FH-46-1A Replace Repair FT-75-21 Dm ca 1DD CL Vl JCQ PT-67-68 D
4 I/\\
1 OC PClLL / IJCll. ~
P(f(I-67-R 11 onlnro c'tJi tr hoc tt BROWNS; INSTR I
'ERRY NUCLEAR PLANT UNIT f
fENT HAINTENANCE SAfffARY HONTff OP Harch 19 81 FOQ T1I CAUSE OF 1fALFUNCTION N SAFE ON OF CTOR EFFEC) 0 RESULTS OF HALPUNCTION False Indication Shorted to Ground N ne
'I(
Non t(
Nnn Faulty Indicator Did Not Agree With Redundant Indicator Indicated False High Pressure Tnst rttment Drift IN'aulty Flow Control Honitor High'low Alarm Palse Low Alarm Setpoint Drift ne Did Not Indicate teal ow Paulty Circuit Com(potient ne Faulty Amplifier False Indication of Core Spray ne N
II
, I No II Tnrnrrert Flow Indication 6R 1fad Rad Amplifier, 12B Had Instrument Drift
~ AC Paultv Switrhes Alarm 'ant(1 (f Nnt Cl on ne ACTION TAKEN TO 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 for the'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 rack installa-'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 HDFSS modules'nstalled in August of 1979'ull core, unload capabilities. are
'ow available.for the outage.
&;.SCN.=.F9078=...;Mechanid~a.-prefabr'xc:idion<<worK-is iniprogress;.foi>t,e:
fire protection modification at thei pumpiintake structure.
7.
ECN Ll!329/L1960 - Cooling tower modifications are in progress.