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 ... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
Refueling Information ~ ~ ~ ~ ~ ~ ~
Significant Operational Events ~ ~ ~ ~ ~ ~ ~
Average Daily Unit Power Level ~ ~ ~ 15, Operating Data Reports ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 18 Unit Shutdowns and Power Reductions. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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 0.00501 0.00393 0.00331 Feedwater nozzle 0. 24257 '
'.'16960' 0. 12530 Closure studs 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.
Si nifi'cant 0 erational Events Unit 1 Date Time Event 3/01/81 0001 Reactor thermal power at 98%, maximum flow, rod limited.
1500 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 Commenced reducing thermal power for (MSIV closure timing) SI 4.7.D.l.B-2 and SI 4.1.A-11.
0300 Reactor thermal power at 65%, holding for MSIV SI's.
0310 MSIV SI's complete, commenced power ascension.
0400 Reactor thermal power at 76%, holding for turbine control valve tests.
0420 Control valve tests complete, commenced PCIOMR (sequence "B").
3/09/81 0335 Reactor thermal power at 99%, maximum flow, rod limited.
2300 Reactor thermal power at 98%. EHC vibration limited.
3/~13 81 2300 Reactor thermal power, at 97%,,EHC,.vibration limited.
3/15/81 0025 Reduced thermal power to 85% for turbine control valve tests and SI's.
0145 Turbine control valve tests and SI's complete, commenced power ascension.
0202 Reactor thermal power at 97%, EHC vibration limited.
3/17/81 0840 Commenced reducing thermal power for a control rod pattern adjustment.
1000 Reactor thermal power at 64%, holding for control rod pattern adjustment.
1012 All rods out.
1030 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 Reactor thermal power at 99%, maximum flow, EOC-4 c'oastdown ~
1924 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., e Reactor feedwater pumps and recixculation MG sets
~
1945 back to normal and unit prefez;red power placed on 1002 breaker, conmlenced power ascension.
2300 Reactor thermal power at 98%, maximum flow, EOC-4 coa.'tdown 3/21/81 0115 Reduced thermal power to 85% for turbine control valve tests and SI's.
0155 Turbine control valve te. ts and SI's completed, commenced power ascension.
0230 Commenced PCIOMR from 96% thermal power.
0700 Reactor thermal power at 98%, maximum flow~ ETC~4 coastdown.
3/23/81 0815 Condensate demineralizer momentarily bypassed, re-ducied thermal power to 91%.
0825 Commenced power,ascen: ion from 91% thermal power.
0900 Reactor thermal power at 98%, maximum flow, EOC-'4 2300 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 Reactor thermal power at, 98%, maximum flow, EOC 4 coa s t(Iown ~
2300 :Reactor thermal power at:.98%, EOC-4 coastdown.
3/28/81 0100 Corrtmenced reducing thermal power fox turbine~control, valve tests and SI's.
0121 Reactor power at 82%, hplding for turbine control valve test.; and SI's.
0500 Turbine control valve tests and SI's completed,~
commenced PCIOMR.
0700 Reactor thermal power at 98%, maximum, flow', EOC~4, coastdown.
Si nificant 0 erational Events Uni't 2 Date Time Event 3/18/81 2000 Reactor thermal power at 99%, maximum flow, rod limited.
3/20/81 1225 Reduced thermal power to 97% for control rod ad-justments.
1235 Commenced power ascension.
1240 Reactor thermal power at 99%, maximum flow, rod limited.
3/21/81 0205 Reduced thermal power to 91% for turbine control valve tests and SI's.
0336 Turbine control valve tests and SI's complete, commenced power ascension.
0430 Commenced PCIOMR from 96% thermal power (sequence I IEI I
)
0600 Reactor thermal power at 99%, maximum flow, rod limited.
3/26/81 1555 Reduced thermal power to 82% for removal of Cl and C2 high pressure heaters from service for Ilail relief valve maintenance.
1650 "C" string high pressure heater isolated, reactor thermal power at 82%, holding for relief valve maintenance.
220.0. "C".. string high pressure&eaters, back in service.
commenced 'power ascension.
3/27/81 0300 Commenced PCIOiiK from 97% thermal power (sequence I
)
0700 Reactor thermal power at 99%, maximum flow, rod limited.
0820 Reduced thermal power to 83% for removal of "C" string high pressure heaters from service for maintenance on heater drain line.
2138 "C" string high pressure heaters back in service, commenced power ascension.
2325 Reduced thermal power from 96% to 82% for turbine control valve tests and SI's.
3/28/81 0025 Turbine control valve tests and SI's complete, commenced power ascension.
0900 Reactor thermal power at 99%, maximum flow, rod limited.
1252 Reactor Scram No. 117 (3) 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 Power ascension in progress from 0 power. (Startup from scram on February 28, 1981).
0910 Commenced PCIOMR from 64% thermal power (sequence I IBII
)
3/02/81 2010 Reactor thermal power at 99%, maximum flow, rod limited.
2047 Both recirculation pumps tripped reducing reactor thermal power to 36%.
2225 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 SI 4.6.A.6 and 7 complete for "B" recirculation pump, "B" recirculation pump placed in service.
Commenced power ascension.
0700 Reactor thermal power at 87%, holding to maintain core limits.
1230 Commenced PCIOMR from 87% thermal power (sequence IIBII) 3/04/81 0700 Reactor thermal power at 99%, maximum flow, rod limited.
1500 Reactor thermal power at 98%, maximum flow, rod limit;ed-;. -
2300 Reactor thermal power at 97%, maximum flow, rod limited.
3/05/81 0700 Reactor thermal power at 98%, maximum flow, rod limited.
1500 Reactor thermal power at 99%, maximum flow, rod limited.
2300 Reactor thermal power at 98%, maximum flow, rod limited.
3/07/81 0408 Reactor Scram No. 115 (1) from 98% thermal power 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.
1430 Commenced rod withdrawal for startup.
1720 Reactor Critical No. 128.
2115 Rolled T/G.
2142 Synchronized generator, commenced power ascension.
3/08/81 2230 Commenced PCIOMR from 75% thermal power (sequence II Bl I )
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 Commenced reducing thermal power to test MSIV thermal power at 73X, holding to tekt P1SIV 1-26.'eactor 2237 1-26.
2243 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 Commene;ed reducing thermal power to remove both recirculation pumps from service fox bruah replaCe-ment oii recirculation 'Ig set.
2259 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 Commenced rod withdrawal for startup.
1515 Reactor Critical Noa 129.
1830 Rolled T/G.
1915 Synchronized generator, commenced power ascension.
3/15/81 0330 Commenced PCIOMR from 67X thermal power,'(S'eqdence 'I pll )
3/16/81 0021 Commenced reducing thermal power from 87X p~ower" for contro3.
Idyll rod pattern adjustments.
0026 Reactor. thermal power at 78X for control rod adjust',
ments.
0112 Rod adjustments complete, commenced power a'scenieon.
0200 Commenced PCIOiK from 81% therma3. power '(se~quenc'e IIBII) 0800 Reactox thermal power at 99%,. maximum flow, rod limited.
3/17/81 0600 Reactor thermal power at 98%, maximum flow, rod limited.
1500 Reactor thermal power at 97%, maximum flow, rod limited.
3/18/81 1018 Commenced reducing thermal power fox a contro3.
rod pattern adjustment.
1045 Reactox'hermal power at 73%, holding for control rod pattern adjustment.
1335 ,Contro3. rod pattern adjuc>tment complete, commenced power ascension.
1355 Commenced PCIOMR from 89% t'hex'mal powex'sequence I
),
Si nificant 0 erational Events Unit 2 Date Time Event 3/28/81 2035 Commenced rod withdrawal for startup.
2358 Reactor Critical No. 130.
3/29/81 0455 Rolled T/G.
0517 Synchronized generator, commenced power ascension.
1200 Commenced PClOMR from 67% thermal power (sequence I I Bl I
)
3/30/81 2030 Reactor thermal power at 99%, maximum flow, rod limited.
3/31/81 1245 Reduced thermal power to 87% for control rod pattern adjustments.
1320 Control rod pattern adjustments completed, commenced PCIOHR (sequence "B").
1930 Reactor thermal power at 99%, maximum flow, rod limited.
2400 Reactor thermal power at 99%, maximum flow, rod limited.
~EI ~nifinant OEaratienal Evente Unit 3 Date Time Event:
3/01/81 0001 Control rod pattern adjustment complete, in'cre'fasted therma.'L power to 70/, holdiiag fok t'urbine 'eactor control valve tests and SI"..
0100 Turbine control valve tests and SI's complete,',
commenced PCI011R, (control cell core).
0105 Stopped PCI01IR at 71% thermal power, computer out of service.
0230 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 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 and precoat: condensate demineraliz'er vessels 'ackwash I II II I
l]l1I and J 0615 Condensrate demineralizer proble'm resolved, commenced power ascen ion.
0705 Commenced PCIOlifR from 96X thermal power '(co'ntrol'ell core) .
1005 Reac:tor thermal power at 99%, maximum flow, r<>d limited.
"KH 3/07'/81 2340 Commenced reducihg;'thermal power for turbine- con'troI valve tests and SI's.
3/08/81 0035 Reac:tox thermal power at 64%, turbine control valve tests and SI's in progress.
0120 Turbine cont:rol valve tests and SI's complete, commenl.ed power ascension.
0430 Commenced PCIOllfR from 97%'lhermal power (cdnt&ol chil'ore.)
0800 Reac,tor thermal power at 99%, maximum flow, rod limited.
2011 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 Commenced rod withdrawal for stax'tup.
2230 Reactox Critical No. 106<<
3/10/81 0242 Rolled T/G.
0310 Synchronized gene.rator, commenced power ascension.
2210 thermal power from 73% to 64% for control 'educed rod adjustments.
2300 Rod adjustments completel commenced power ascension.
13 Si nificant 0 erational Events Unit 3 Date Time Event 3/11/81 0100 Commenced PCIOi~K from 76% thermal power (control cell core).
2300 Reactor thermal power at 99%, maximum flow, rod limited.
3/12/81 1445 Commenced reducing thermal power due to high river ~
~
hT.
1520 Reactor thermal power at 73%, holding due to high river hT.
2130 Commenced po~er ascension from 73% thermal power.
2300 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 Reduced thermal power to 82% for turbine control valve tests ans SI's.
0036 Turbine control valve tests and SI's completed, commenced power ascension.
0040 Reactor thermal power at 96%, holding for control rod drive exercise.
0135 Control rod drive exercise complete, commenced power ascension.
--=,.- ..-0200- -- ~ .-.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 Reactor thermal power at 87%, turbine control valve tests and SI's in progress.
0028 Turbine control valve tests and SI's complete, commenced power ascension.
0035 Reactor thermal power at 91%, holding for control rod drive exercise.
0105 Control rod drive exercise complete, commenced power ascension.
0115 Commenced PCIOifR from 97% thermal power (control cell core).
0415 Reactor thermal power at 99%, maximum flow, rod limited.
0740 Commenced reducing thermal power for unit shutdown due to high level alarm in east side scram discharge header (personnel error).
0743 Plant personnel were performing TI-58 on scram dis-charge header. Stopped reducing thermal power at 73%
upon discovery of personnel error.
14
~Si ~~nif icant O~erational Event:s Unfi.t 3 Date Time Event:
3/21/81 0750 Commenced power ascension from 73% therm@1 ipoker'.
0835 Reactor t'herma.'L power, at 99%, maximum flow, rod limited.
3/25/81 1720 Commenced reducing t:hermal power due to gen'erAtoL bus duct cooling fan siinoking.
1755 Reactor therma.'L power at 54X.
3/26/81 0700 Reactor therma.'L pbwer ,at 55%.
15OO Reactor thermal power ,at 58% due to bus duct cool-ing fan problems.
1800 Bus duct cooling fans back:in service, poweir ascension.
c*mmiended'5%
2200 Commenced PCIO],"R from thermal power (co'ntrol GAIA cell. core).
3/27/81 1306 Reactor thermal power at 99%, maximum flow, rod limi.ted-3/28/81 0010 Commenced reducing thermal power for turbin'e don<
trol valve t:ests and SI's.
0020 Reactor thermal power at 82X, holding for. turbine control valve tests and SI's.
0035 Turbine control y'alve tests and SI's complete
.commenced-power.
~
,ascension 0700 Reac:tor thermal power't'99X.; maximum flow, rod limi.ted.
3/30/81 0357 Reduced reactor thermal power to 71% when 3iA reactor. feedwater pump tripped '(hi vibrat;io'n).',
0555 Roll,ed 3A reactor feedwater pump for vibiat'iotIi cihecks,,
0625 3A reactor feedwater pump tripped on high v'ibr'ation.
0915 Rolled 3A reactor feedwater pump, commended power asceinsion.
1130 Commenced PCIOl!fR from 93% thermal power ilcontrol cell. core).
1700 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 A VERAGE DAILYUNIT POWER L'EVEL DOCKETNO.
Brotens Perry 1 4-1-81 COMPLETED IIY Ted Thorn TELEPHONE IONTH March 1981 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL
() I We.)bet) (MWC-Net I 1045 17 859 1061 IS 983 1053 19 1042 1048 20 1048 1047 1038 21 1042 1047 1031 23 1038 912 1075 1057 '75 1045
~A 10'40'*
10 "1057'041 26 1041 27 1046 1023 12 2S 13 1044 ')9 1033 1031 30 1027 15 1032 31 1025 16 1033 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 DAILYUNIT POWER LOVEL DOCI'ET NO.
f r owns, y DATE CoiIPLETED BY Te.d Thorn TELEPHONE March 1981
'AY DAY AVERAGE DAILYPOPOVER'EVEL -AVERAGE DAILYPOWER
(~I We.Nct I LEVEL')))IWe*Net) 719 17 i 1048 878 999 833 1066 l9 1056. OP, ~QZ) 1062 21 1056 1058 1062 201 1064 23 559 24 106rI 9.52 )5 1070
":10'69 1007 26 ll 1055 27 958 I2 10i60 28 552 l3 10,11 ') 9, ,508
'93 978 l4 I5 8i66 1~02 IG 1043 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 DAILYUNIT POWER UsVEL 50-296 DOCKET NO.
UNIT Browtls Ferry 3 4-1-81 COMPLETED BY ~mt 'Ehom TELEPHOiNE 205-729-6846 MONTH We-Net DAY AVERAGE DAILYPOWER LEVEL DAY -AVERAGE DAILYPOWER LEVEL (hlWC-Net) ' (ill )
901 17 1079 1042 18 1071 1031 19 1074 1072 ap 1079 1080 1053 1082 1066 22 1077 23 1068 864 24 1072
-14 25 931
==.487 652
10 26 959 1028 27 978 28 1056 13 1053 59 1068 1068 971 3P IS 1064 1067 31 1071 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 lo lhc Ilcarcst Ivhiilc>>lc~aN:Itt.
I'II77 )
18 OPERATING DATA REPORT 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): 1098.4
.(
7 ~fazin>um De p endable Ca p acitv Net i~Ice: )
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
iIA
- 9. Power Level To.Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month. Yr.-to.Date
~
Cumuh tive
- 11. Hours ln Reporting Period 2,160 58,442 56, 950,15
- 13. Reactor Reserve Shutdown Hours 5,115.29
- 14. Hours Generator On-Line 744
- 15. Unit Reserve Shutdown f fours . 0 0
- 16. Gross Thermal Energy Gencratcd (MWH) 377- 054 99 972 699
- 17. Gross Electrical Energy Generated (l>IWII) 786,760 2,226,870 32,990 160
- 18. Net Electrical Energy Generated (MIVH) 764,657 32,035,015
- 19. Unit Service Factor 61.8
- 20. Unit Availability Factor 100.0 99.1 61.8.
- 21. Unit'Capacity Factor (Usi>>g i>IDC Net) 96. 5 94.4
- 22. Unit Capacity Factor (Using DER Net) 96.5 94. 4 51. 5
- 23. Unit Forcegc Rate 0 0.9 28.1
- 24. Shutdo>vns Scheduled Over Next 6!>Ionth>> (Type. Date. and Duration of Each):
Refue1in A >.il 1981
- 5. If Shut 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 Clf IT ICA LIT Y INll'IAL ELECTRICITY CO.'VDIERCIAL OPI! RATION (o/77)
OPERATI>NG DATA REPORT DOCKET >NO. 50 260 CO.'>IPLETED BY ~~It'horn TELEPHONE M>~~29-6846 OPERATING STATUS
- 1. U it N . Brogans Ferry 2 bootes Reportfnn Per>od; I'farch 19'81
- 3. Licensed Thermal Povver (!>I)Vt):
- 4. 1152 nameplate Rating (Gross -11)Ve'):
- 5. Design Electrical Rating (iNet 5'IWe): 1065
- 6. Ifaximu>n Dependable Capacity (Gross IIIVfe): 1098.4 7 hfaximum De P endable Ca P acitvu( i%et slftVe: 1065
)
- 8. IfChanges Occur, in Capacity Ratings (Items IIIumber 3 Through 7) Since Last Rel>ort. Give Reasons:
- 9. Po>ver Level To )Vhich Restricted, If Any (Net MM(e):
- 10. Reasons For Restrictions. If Any: NA.
This lpfonth Yr. to.Date
~
Cun>uiative I i. Hours In Reporrie8 period 744 2 1'60
~ -1'.* 13.
14.
15.
Reactor Reserve Shutdown Hours Hours Generator On-Liine Unit Reserve Shutdown Ilours 689.75 i i, 2040.99 0 ,
.31 781.95 0
- 16. Gross Thermal Energy Gencratcd (ilfWH) :! 092 498 . 6 232 974, 99 803 617 17.
18.
19.
20.
Gross Electrical Energy Generated (ilf)VH)
Yet Electrical Energy Gencratcd (I>if)VII)
Unit Scrvicc Factor l'nit Avaih>l>ility Factor 672,804 92.7
- 92. 7
'4.5 2,031,060
'94. 5 29,981,367 59.6
- 59. 6
- l. Unit Capacity Factor (Use>> l4IDC Nct) 84.9 l l l l 88 i3 51.0 2.
23.
Unit Capacity I'actor IU5i>>g DER hct)
Unit Forced Out:> c Rate .
84.9 7.3. '5.5 88.3
~ .
5r .0 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. If Shut 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 I YITIAL Cft'.ITIiCALIT Y I Yll'IAL EL,EC'I'R ICITY COiliIERCIAL Ol'FRA TIO.4 (4)/77)
4 20 OPERATING DATA REPORT DOCKET NO.
DATE COlifPLETED LtY Ted Thorn TELEPHONE ~~o- 46 OPERATING STATUS 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 7..fasnnn >> D e p endable Ca p acit y(Net iaaf lVe:
)
1065
- 8. If Clianges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
NA
- 9. Povver Level To Which Restricted, If Any (Net bfWe): NA
- 10. Reasons For Restrictions, If Any This ilfonth Yr.-to.Date Cumulative
- 11. Hoiirs In Reporting Period 744 2 160 58;442
-.-2-7-- 605 88--
- 13. Reactor Reserve Shutdown Hours 1 966.46
- 14. Hours Generator On. Linc 713.02 1 573.99 ~26 6
- 15. Unit Rescrvc Shutdown floors 0 0
- 16. Gross Thermal Energy Gencratcd(MWH) 2 207 040 4 488 641 788 6 I i. Gross Electrical Energy Generated (iaaf WH) 744,730 1 511 950 26 050 980
- 18. Net Electrical Energy Gencratcd (illWkl) 722,574 1 465,667 25,289,990 I 20. Ulllt Availability Factor 95. 8 7
- 21. Unit Capacity Factor (Using i~IDC Net) 91. 2 63. 7 66.3
- 22. Unit Caixicity Factor (Using DER Nct) 91. 2 66 '
- 23. Unit Fr)reed Outage Rate 4.2 9.4 9;"7
- 24. Shutdoivns Scheduled Over Next 6 iifonths (Type. 1)ate, and l)oration of Eaclt I:
- 5. If Shut 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 ICA LITY INITIAL ELECTltlCITY COil it ii I(CIAL Ol'E RATION (i)/77)
DOCKET NO.. 50-260 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNll NAME DArE r- -81 l COhll'I.ETED IIY I e(I . I holll.
REPO T MON'fll TI!I.EI'IIONE I
fP c'
f J Lie cnscc Cause A Corrcclivc ff CP l)ale I:. vent Action lo Rc ort ~ IJI' F O
IJ Prevent Rccufrcncc CfI t
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 4
F: I'orccd Reason: hlcthod: Exhibit G - Instructions S: Schcdpled A.EIIuipmcnt Failure (Explain) I hlanual for Preparation ol'Data B.Maintenance or Test 2.hlanual Scram. linlry Sheets I'or Licensee C. Rc fuel inI; 3-Automalic Scram. fvcnt Rcport (I.l!R) File (NURI'.G.
D.Rct,ulatory Restriction I'i 4.Other (Explain) 016 I )
Opcfalor Training h. Liccnsc Fxanthtatlon~
()/77)
F.Adtninistrativc G Operational Error (Explain)
I I Other (Explain) f Exhibit I ~ Sant' Iur '
DOCKET NO 50" 260 VNITSIIUTDOWNS CND POWER REDVCTiONS REP RThlON'fll COh(PLETEI) N'ed Thorn
'rr, LI ccnscc r. Cause Lrr. Corrective liat e vcnI 0 ~ Acti(ill Io R nnrl A r
C Q Prcvcnt Recurrence v1 G
179 3-2-81 Derated due to oA" and oBO recircula-.
tion pumps tripping 180 3- I-81l JlI Jl 1
~
C 1 A
n ral 4 1 n 11 ~ ILLS nnvI nv'Illa 11n vL Ir4LLvLllILll5 CT llI L
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1
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d 1 1 board MSIV continued to go closed aftet pushbutton was released, resulting in a full isolation and scram 181 3-'11-81 Derated to test MSIV 1-26 182 3-13-81 19 2I
~
Cnvne lI In ~ LO hallh llatnr 1 errel 'indi Ca tion which caused the main turbine I and reactor feedwater pumps to trip.
I Equalizing valve on level indicator was open ~
I 183 3-18-81 S B Control rod adjustment I 3 F: Forced Reason: Method: Exhibit G Instrui.lions S: Scheduleil A Equipmcnt Failure (Explain) i h(anual for PICp:IIJIniil ol Dal J Bt.h(aintcnancc ol Test 2.Manttal Scram. Entry Siiccts I'or Lieciisee C Refueling 3.AUtolll'll!cScf Jnl. Event Report (Ll!R) File (NVREG-ii.iRcgulatory Restriction 4 OlhCf (I'xpiJIII) 036rl-)
I!.Operator Training k Lii:ense Fxamination F.Administrative 5 G upcrat(ona( Error (Expiain)
Exhi'Ml I - Sa;Ile Soliree I I Oilier (Expl Jill)
l)OCKET NO. 50-260 UNIT SIIUTI)Olt'iVS AND POIVER REI)UCTIONS UNI'I' Ahl E I)ATF 4-2-81 COhlPLETEI)!IY Ted Thorn REPO RT hlON fll I larch h
~ A CI a cciiscc Cause A ('orrcclivc I)atc I vc iil Aclioii lo J V Vi Re pofl Prevent Rccurrcnce 184 3-28-"gl 16.42 Scram due to turbine trip while working on thrust bearing wear detector I': Fiirced Reason: hlcthod: Exhibit G - Instructions S: Schedulcil A.Equipmcnt Failure (Explain) I MJnual for Preparation of l)at J I).hlaintenancc or Test 2 hlanual Scram. Entry Sliecls Ior Licciisee C.Refueling 3 Auloinalic Scram. Event Report (I.I!R) Fil>> (NLIREG.
I).Regulatory Rcstri<<lion, I L Opcral<ir Training 8; Liccnsc Exaniination 4 Otl)cf (ExplJiii) OI6I)
F-Administ rat ivc G Operational Error (Explain) Exhibit I ~
Siuue Source (9/77) I I Other (Explain)
o
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I I
vJ BRO'ZNS FERRY lUCLEA1'. PLANT UllIT u
ELECTRICAL HAIHTENANCE
SUMMARY
l For 'he ?lonth of Narch 19 81 Action '1'aken D""e System Component Nature of Operation of Cause of Results of To Preclude llaintenance The I Reactor ."fal function a~la 1 func t ion R currence 3/6/81 EEC14 EEL North Received a None Bad low flow Low flow alarm Replaced relay, alarm header low false low flow alarm relay inoperable. system operated pro-flow alarm annunciation coil. perly. TRI't158585 relay (67AL1) on panel 9-20 for units
'1 &~ 3
!i 3/8/81 Fire pro- Smoke detector Received None! Increased sensi- Smoke detector actu- Replaced the smoke tection (XS-39-104AA) flase alarms tivity of smoke ated 3 false alarms detector, performed on panels detector. in a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> period. SI4.11.C.1 & 5.25-325 and TR8204709 9-8.
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BROMNS FERRY NUCLEPJ; PL!>NT U?lXT CSSC EOUIPi'1ENT EKEECTRXCAL >lAXNTENr~CE SUlAlARY For,'t he Honth,of Harch 19 81 Ekred t on Sake chic t ion Taken N,.ture of Opcl) ation of Cause of Results of To Preclu"e System Component llaintenance Reactor Halfunction Halfunction R'currence 3/4/81 Diesel "HVST2 coil" EHX 3 None "llVST2 coil" This solenoid coil Replaced the bad coil, Generators in D/G 3B found to be bad was'ot deteriorated solenoid operated start failure during redundant to the point of mak- properly. TR//220503 backup circuit start test. ing the solenoid inoperable. The
-coil did cause a spike on the oscillo graph trace.
3/8/81 . Diesel D/G 3A fuel Received a Nones Bad annunciator Received a false Replaced the bad Generators oil pressure false fuel circuit card. annunciation. circuit card, annunci-annunciator oil'ressure ator operated properly.
annunciation. TRI'I204848 IV 3/10/81 Residual FCV-3-74-74 FCV-74-74 feed Unit in limitin Unknown RllR valve FCV74-74 The valve operating heat re- er breaker condition for feeder breaker trip- current was measured moval tripped after operation ped after the valve and found to be accep-valve closed (TS3.5.B.7) closed while per- table. No loose con-during perform forming SX4.5.B.1.C nections were pound ance of in the breaker'com-SX4.5.B.l.c partment. The valv has been cycled daily, through 3/18/81. )
TR8204839 LER8BFRO-50-296/8113
'Y rr B ;30.:NS,,PER
'Al - .
tlJCLB/ P PLItt 0!r TT CSSC EOUIPINENT ~
ELt:,CTRICAL tiAINTENANCE Sulau.RY
- il Etl Get, on SQre Action Taken System Component Nature of opera,'tion of Cause of Results of To Preclude I
';taintenance The ,'coactor >talfunction Na 1 func tion R'currence 3/13/83 Diesel 3A D/G D/G alarms None< Bad annunciator Annunciator Replaced bad circuit generator annunciator inoperable t3 circuit card inoperable card, annunciator.
operated properly.
TRfI204821 3/13/8 Rad waste RHR pump room LA-77-25C None Loose connec- Annunciator inoper- Corrected connection, flood level would not tion on annunci able. annunciator operated Mnnunciator test ator cxrcuxL" rorteiltr TR 221 558
($
t I n<<n LA II IJL r
Cnl 3/17/81 tl t I tt tl ntl'3 71 f'vnt tent I V
<<\rv& r& /. /. trt A vr Vt <<r<<ttt'Q nn~ Valve motor Valve was placed in Retaped the conductor FCV-73-44 lead "A2" was open (operable) po- performed ENI 71, 18, "Inboard grounded at sition while the and 18.1, valve discharge taped connectior conlductor was r'G= Operated prOperly, val've II in limitorntte insulated. TRf/2O5S09 connection com-partment.
3/17/81 D/G 3C Received a None Bad coil on NVR Received a false Replaced the baa gener'ators "control power t relay and loose n JJ.OII
<<IIIIIUIIIJ<<tl
~ jI A tI ht<<tt .relay COil andt tight-I IUnnJn VL CC L <<I ~ a
~ ~~ t J.<<t 3558 annunciato the control power ened the annunciator tion card. was off. card, the annunciato I operated properly.
TR/~205434
'/17/81 480 Volt Hotor genera- Received a None Bad annuncIatol. Received a false Replaced the bad shutdown l.or t)a t 3DA beneLatoi ut ~ c<<trd = undervoltage alarm. annunciator card, nnr,rer dervoltage -annunciator checked alarm for no OK. TR//205410 apparent rea-son.
NNU!'NS'BNZaT NUCLNAZ PLANT UNIT CSSC EOIIIPHEHT ELECTRICAL I~IAINTEN/ACE SmIIIARY II JIL I IMtec!t on Sate Action Taken I
Nature of Opej'ation of Cause of Results of To Preclude System Component Na 1 func t ion D
I ala'ntcnancc Th,i Iicactor '.Inl func cion R'currence 3/19/81 Diesel 38 D/G Received a None Bad annunciator Received a false Replaced bad annuncia-Generators overspeed card overspeed annuncia-, tor card, annunciatioi annunciation tion. tested and cleared on 38 D/G properly. TR8205511 I3/20/81 Air-condi- 38 control bay 38 control bay None. Oil bypass valve Chiller tripped on Closed oil bypass I tioning hiller chiller trippe open low oil pressure. valve and adjusted I
(I'oo1ing- K '
oil regulator valve, heating) chiller operated A
properly. TR8220520 I3/22/81 IIPCI Low level Low level None Level switch Condensate pump con- Freed the switch, the
(
switch on switch inoper- 73-158 was trolled by LS73-158 pump operated properl>
gland seal able. sticking would not operate TRPT205499 condenser automatically.
- ><<. >><<i~> r < ,,i..i II'. Ii i I KCllAi<'ICAL Nu'<ItlTEYVICE SU<~i
- IARY For tl>e .Hont.h of Narc'9 81 EFFI:G'Ll Otl S>" rE ACTlOti T<".KE:I C>>USF O; RESUI.TS OF TO Pi(ECI.UDE DATE SYS'1<;H COt IPO"<EHT ltATURE OF OPERPjTIOiV OF t tALFNICTIOtI >~<<XLFUHCTIO<v< r<F CUIIREtICE
'l PAIttTEt<AIICE TiiE <REACTOR L
l! Fj>>e I ti V-26-95fi Broken Pin 1'fi Roll Pln Broken Frozen Valve Replaced )'ins iir<>toe t ioh TP <<KG<<512
/
5I((1s ~ ~ ),) I l.lie'iL siw:I.!..aci t s .>~a a use > A
>K(:IIAI'ICALIM.INTEV~QlCE SUI Il bhliY CSSC ~l'.( UI. VI I".NT For 'the Honth of .. Harch 19 81 EFFI'.CT GN SP2'E ~:C 110<1 IA.'r.h Opr.RATION CAUSE OF RESUI;I'S OF TO PRECI.UDE D."i'l'. SYG TE! I COHPO!KalT NATURE OF E 'REAC1OR 01'II IIALFUIICTION MAI,FU!!CTION RECI!RPJ HCE
!-DXI!ITEIIAI!CE 3-2-81 C RD H20 Header Leakage '/A Loose I'acking Leaking at Stem Tighten Packin Packin TR !220966 3-2-81 (:RI) H 0 Header Leal:age N/A I.oose Packing leal:ing at Stem <
Tighten Packing 2 Pack:in~ TI! ir'220967 2-.19-83 HI'C I Checkc Valve Check V a lve N/A Unknown Unknown Perfor'med SI 3.2.7 RCIC Test 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 Drain Frozen Valve N/A Non-lubricated Non-lubricated Stem Lubricated Valve rCRD SDV Vent Valve 6
Valve Stem Stem TR fi204516 t
3-8-81 CRD CRD 34-23 Morn Parts N/A Strainer Dirty Unknown Changed Strainer TR ~'220873 3-9-81 EF.CI" Fisher Contro Dirty Filter N/A Dirty Filter Unknown Replaced Filter ir Valve 50-51.- 6750-6751 TR fi220845 3-14-8) EECM FCV 67-51 Change Out Filter Strainer Valve Mill Not Close Installed New Filter St ainer Dirt ~ TR Pc221554 3-13-8I Fut.l Pool Leak Hook Up N/A Need to Hook Up Unknown Removed 1/2" Tubing Cooling.'elium Detector Helium I!elium Detectoi and Hooked Up Valve 2B Leak Tester FPC Heat Exch. TR 8216814 H
3-20-8. RBCCI I Surge Tank Level Switch N/A Level Switch Out Swatch Stic! s Adjusted Swit'ch Heeds Adjust- of Adjustment TR ff207824 ment
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~ti
? IEQUd; ICAL III'AI)ITEtI'AI11CE SUM'I'1RY CSSC I'.OUIPlI1'.NT For 'the'onth of iIarch 19 81 lic h O'I Tl'~'.r".lt EFFECT ON SP "E CAUSF. OF RESI)LTS OF TO PRFCLUDE DATIr'. S YS'1 A..t! CO'I "0" FNT IMMATURE OF OPERATIOl1 OF PZCURPZNCE I'~'A IllTE! tANCE TIIE", RFACTOR l I tlLFL"i)CTIOH Nu<LFUNCTION tt LI OJ RBCCW tttli ItnV tttt A
CD
'rt1 c JOdl t ttt 4Jcttt 4Jllb Dl
- 1. 1 L
nn JVQt ~ C r I nl.
V ~ k\ tlatnnt) w
~
"Fl o'at Not Sr ickinn Backflushed Floats Sludge Tank TR:7187778 gECW FCV-67-50 Valve Closed tl(A Valve Was in Stoppage None Closed Pvs Jtlont TR Penn~ It
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3-27-,81 RBCCW A D.W1 ~ Air Stopped Up N)A Blockage P lugged I.ine Backflushed Com ressor Line TR tll208404 I ttCI1 VJ 01 Dttrrt.t A U '4 \r ru Ivhh-7A tv 7'A a u Wil 1 .Int Act H')
~ tg BaII wires on Switch Will Not Installed Limit In On Low Limit Switch Function Switch Level TR !I208407 l
jl 1
! 8( !:c'!'1p'.1 )KC)IJd 1.('AI )I.~T.'"P"JUDICE SU~ V~(Y For thc Month of - )')arch 19 81 011 Sr"'I ACTIOII T:~HEI)
DATI'. 8'iS') r.) I CO"(PL~') ~i') i TION OF LACTO)t ChliSE OF
) )ALE UII(.'TION RHSUI:I'S OF tP.I.FUNC')'ION TO FRECLUDE RECURRENCE 2-? 3-81 Fuel Pool Pump 1)otor 3B Pump Out of N/A Bent Shaf t & Unkno~m Replaced Shaf t, Cooling Alignment Worn Par ts Impel)or, Bearings, Sleeves, Wear Rings and Itepacked TR 8136719 3-?-81 I.PC I AX liG Set Lubrication H/A Coupling Needed Unkn oem Greased Coupling N(i Set Greasin TR I)182062
')-2-81 LPCI 3EA IIG Set Lubrication N/A Coupling Needed Unknown Greased Coupling liG Set Greasin TR 8182082 3-3-81 D/C Air Coapressor Leakage
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N/A Pilot Unloader Air Line Leak Repaired Pilot l! l Bad I/22 1503 Valv'R 3-11-81 CRD liodule 38-43 liechanical , N/A Seal Problem Will Not Withdraw No Problem Found Problem With Normal Pressure TR 8221559 3-11-81 RCIC 3-71-6A Stem Leak Loose Packing Leakage Tighten Packing Gland TR L!221526 3-11-81 CO> Storag Cardox Valve Venting to N/A Unknown Unknown None
& Fire A Atmosphere TR //220510 Protection 3-18-81. I IP CI 73-16 Leak Loose Packing . Packing Leak Tigl>ten Packing.
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TR 8205407 3-17-81 )/PCI Turbine Exhaus Disc Blown N/A Ruptured Disk Blown Disc Replaced Disc TR 8205408 I
3-18-81 Fire Valve Flange ~
N/A Unknown Unkno~m New Flange Protection 3-26-1132 Cracked TR 8199138
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Bf(OIJNSi iiERRY: Ui;Li!AR Pl 'IIT Qil": )a.:
CSSC F UTPIF'IT 5L<$ IANICAL IIAINTENANCE SUt'~fhRY For tlie Honth of- ~ Harch 19 81 AC'1'10:I TAKE:I EFFI'.CT 'l GN SAFI?
TION QF ChUSE OF RESVI.TS OF TO PIIECI.UDE DATE SYS'ia.if COI I PO".1ENT llATURE OF OPE
'1"ifE: REACTOR l IAI.FUIJCTION IIALFUNCTION RECUIl"F"C".
t IAIttTENANCE 2-28-8 EECIJ Strainer C3 Strainer Hal- Gears Out of Gears Grinding l)isassembled and 0
Iunction Alignment Turned Gear 180 .
TP, 1 204851 Fire 8" Strainer Damaged "N/A ~ Unknown Strainer Damaged Complete per Protection 13asket Strainer DCR P2473 3-20-8'-14-8 TRi'3182041 RIIR IUIRSIJ Pumps Unknown V/A Unl'nown Unknown Performed !Cfl 29 TR P 198828 3-14-8 EECIJ C3 EECIJ Pump Pump Not Mork- 1 J/A Coupling Out of Pump Not Heeting Adjusted Coupling to ing Up to Adjustment SI Requirements Read .048 Re uirements TR Prl99464 3-14-8 3-22-8 F.ECM RIIR D3 EECIJ Pump 3C RIIRSIJ Pump Pump ing Re Not IJork-Up to uirements Low Flow /A Unknown Unknown Not Pumping Itut 4,000 Pump gpm Not Pumping Checked Coupling Okay IIHI-29
'fR 8199466 Iebuilt Pump t
rR 8148095 3-16-8. I? ECIJ C Strainer lligh DP ,
'/A " 'nknown Unknown 'low Going Through
- 6 D Strainer
)ischarge rR 8103793
tt BROWN S; 'ERRY NUCLEAR PLANT UNIT f
INSTR fENT HAINTENANCE SAfffARY I
CSSC E UIPffENT FOQ T1I HONTff OP Harch 19 81 NATURE EFFEC) 0 N SAFE CAUSE ACTION TAKEN SYSTEM COMPONENT OF ON OF OF RESULTS OF TO PRECLUDE MAINTENANCE CTOR 1fALFUNCTION HALPUNCTION RECURRENCE Unit ]
3-1O Standby TE-63-4 Replace N ne Shorted to False Indication None Liquid Ground Control.
'I
(
3-17 Standbv T. T-63-1 R Ronl ace Non Faulty Indicator Did Not Agree With None I.iquid Redundant Indicator Control t(
LV In vL <<LIIICIL t<<<<v' t y
PT-f/.
~ L Cl ~ Jk1
(
I'al ihrot o Nnn Tnst rttment Drift Indicated False High None Contain- Pressure ment I
Unit 3-3 Radiation Honitoring Repair/Replace N'aulty Flow Control Honitor High'low Alarm None
~ ~
Standby TS-63-4 Calibrate ne Setpoint Drift Palse Low Alarm None Liquid rnntt rnl 3-10 Feedwater FH-46-1A Replace ne Paulty Circuit Did Not Indicate None Control Com(potient teal -
ow 3-16 Core Spray FT-75-21 Repair ne Faulty Amplifier False Indication None of Core Spray 3-12 emergency Dm CL ca Vl 1DD JCQ D OC PClLL 4 I/\ 1
/ IJCll. ~ N ~ AC 6R 1fad Rad Tnrnrrert Flow None f'qttinment PT-67-68 Amplifier, 12B Indication Cooling Had Instrument Water ,
II I
Drift 3-1 7 Emornen('v P(f(I-67-R 11 onlnro c'tJi tr hoc No ne Paultv Switrhes Alarm 'ant(1(f Nnt Cl on Nnno Equipment
(<<e<<t I << tt ~~
II
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
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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 1979'ull modules'nstalled in August of core, unload capabilities. are available .for the outage.
'ow
&;.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.