ML18036B006

Monthly Operating Repts for Jan 1981

ML18036B006
Person / Time
Site:	Browns Ferry
Issue date:	02/10/1981
From:	THOM T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025B352	List: ML18025B351 ML18036B006
References
NUDOCS 8102170497
Download: ML18036B006 (46)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT January 1, 1981-January 31, 1981 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By: Plant Manager

~l

'TABLE OF CONTENTS Operations Summary Refueling Information Significant Operational Events Average Daily Unit Power Level~~'Operating Data Reports'18 Unit Shutdowns and Power Reductions.

21 Plant, Maintenance 24 Outage Summary.~~35 0

0 erations Summar January 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 twenty-two reportable occurrences and one revision to previous occurrences reported to the NRC during the month of January.Unit 1 There were no scrams on the unit during the month.Unit 2 There was one scram on the unit during the month.On January 3, the reactor scrammed when the main turbine tripped due to actuation of a breaker failure relay while opening the generator bus tie breaker PCB 5248 for routine maintenance.

Unit 3 There were no scrams on the unit during the month.

O~erations Summary (Continued)

January 1981 Pati ue Usa e Evaluation The cumulative usage, factors for, the Ireactor~vessel are's follows: Location Shell at water line Peedwater nozzle Closure, studs Unit 1 0.00497'.24043 0.19766 Unit 2 0.00381, 0.16191, 0.13426 Unit 3 0.00321 0.11766 0.09916 Note: This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements~.

Common S stem Approximately 5.96E+05 gallons of Maslte liguid Ver'e discharged containing approximately 9.,60E-01 curies of activity.

Ref uelin Information January 1981 Unit 1 Unit 1 is scheduled for its fourth refueling beginning on or about April 10, 1981, with a scheduled restart date of August 23, 1981.This re-fueling will involve loading additional 8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power'supply on LPCI modification, and torus modifications if all approvals are received.There are 764 fuel assemblies in the'eactor vessel.The spent fuel storage pool presently contains 550 spent 7 X 7 fuel assemblies, five 8 X 8 fuel assemblies, and one 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 1193 locations.

Unf t 2'nit 2 is scheduled for, its fourth refueling beginning on or about March 26, 1982, with a scheduled restart date of August 8, 1982.This refueling outage will involve completing relief valve modifications, torus modifications if all, approvals are received,"A," low pressure turbine inspection, and loading additional 8 X 8 R fuel assemblies into the core.There are 764 fuel assemblies 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 discharged cycle.,3.fuel assemblies in the spent fuel storage pool.The present available capacity of the spent fuel pool is 160 locations.

With present capacitv, the 1979 refuel'ng was the Refueli~n information (Continued)

January 1981 Unit 2'(Continued) last refueling that could be discha'rged to'the spent fuel pool without exceeding that capacity and maintaining full Icore dis~charge capability in the pool.However, 949 new high density storage locations have been installed, but cannot be used until Special Test 161 is completed.

Unit 3 Unit 3 finished its EOC-3 refueling outage and began cycle 4 during the month.Unit 3 is scheduled for its fourth refueling beginning on or about September 25, 1981, with a scheduled restart date of February 7, 1982.This EOC-4 refueling, involves loading additional 8 X 8 R (retrofit) assemblies'nto the core, relief valve.modification, turbine inspection, and torus modi-fications if all approvals are received.There are 764 fuel assemblies presently in the reactor vessel.There are 124 discharged cycle 3 fuel assemblies, 144 discharged cycle 2'uel assemblies, 208 discharged cycle 1 fuel assemblies, and 40 new 8 X 8 R assemblies in the spent fuel storage pool.The present available storage capacity of the spent fuel pool is 1012 locations.

With present capacity, the 1980,.refueling will be the last refueling that could be discharged to the spent fuel pool without-exceeding that capacity and maintaining full core discharge capabilf.ty in the pool.

Si nificant Operational Events Unit 1 Date Time Event 1/01 0045 0232 1720 Control rod pattern adjustment complete, commenced power ascension from 58%thermal power.Commenced PCIOMR from 73%thermal power.Reactor thermal power at 87%, holding for maintenance on"Cl" and"C2" high pressure heaters (channel relief valve leak).1/02 0330 1900"Cl" and"C2" high pressure heate'rs back in service, commenced PCIOMR from 87%thermal power.Reactor thermal power at 99%, maximum flow.1/05 1028 1045 Reduced thermal power to 97%for SI 4.3.A-2 (control rod exercise).SI 4.3.A-2 complete, increased thermal power to 99%, maximum flow.1/10 0005 0100 0330 0700 Reduced thermal power to 90%for turbine control valve tests and SI's.Turbine control valve tests and SI's complete, commenced power ascension.

Commenced PCIOMR from 93%thermal power.Reactor thermal power at 99%, maximum flow.1/15 1500 Reactor thermal power at 99%, maximum flow.1/17 2300 2355 Reduced thermal power to 95%for turbine con-trol valve tests and SI's.Turbine control valve tests and SI's complete, commenced power ascension.

1/18 0200 Reactor thermal power at 99%, maximum flow.1/20 1/23 1403 1713 1800 2300 2220 2352 Reduced thermal power to 82%due to condensate demineralizer problems.Condensate demineralizer problems resolved, commenced power ascension.

Commenced PCIOMR from 92%thermal power.Reactor thermal power at 99%, maximum flow.Commenced reducing thermal power from removal of"A" recirculation pump from service for MG set brush replacement.

R'eactor thermal power at 40%,"A" recirculation MG set brush replacement in progress.

~Si~nificant Opexational Events Unit 1 Date.Time Event 1/24 0146 0500 1930'"A" recirculation MG set brush replacement complete, pump-placed:Ln sexmice, commenced power ascension.

Commenced PCIOMR from 64%thermal.power.'eactor therma.'L power at 78%, holding dud to condensate demineralizer problems.1/25 0335 1030 1600 Condensate dern:Lneralizer problems resolved,'ommenced PCIOMR.R!eactor thexma.'L power at 87/, hold'ing due to condensat:e demineralizer problems.Condensate dlemineralizer problems resolved, commenced PCI01&'1/26 0200 0315 1500 2134 2350 Reactor t'herma.'L power at 97%, holding due to problems with condensate demineralizers.'educed therma.'L power to 93/, due to problems with condensate demineralizers.

Reduced thex~.'L power to 91/, holding due to high r:Lver diT.Commenced PCIOMR from 91X thermal power.'educed thermal power from 92%to 90%due to",A" and"B" recirculation MG set scoop tube'ockout due to a bad relay.1/27 0245 0845",A" and"B" recirculation MG sets reset,~commenced PCI01W.Reac.tox thermal power at 99X, thermal 1&aited..1/28 0230 0300 0337 1115 1225 1250 2030 Commenced reducing thermal power due to con~densate demineralizer problems.Reac:tox thermal power at 91%,, holding fox condensate deminera."Lizer problems.Commenced PCIOMR from 91X thermal power.'educed thermal power from!99%to 86%to back-wash and precoat condensate demineralizers.

Condensate c1emineralizer backwash and pracoat completed,, commenced power ascension.

Reactox thexana1.power at 96%, commenced PCIOMR.Reduced thermal power from 98%to 88%due to high r:Lver dT.'1/29 0330 0400 0835 1335 Commenced power ascension from, 88%.Reactor thermal power at 97X, commenced PCIOMR.Reactox'hermal power at 99%, maximum flow.Commenced reducing thermal power due to high river hT.

Date Time Si nificant 0 erational Events Unit 1 Event 1/29 1500 1608 1800 1828 2000 Reactor thermal power at 65%, holding due to high river bT.Commenced power ascension from 65%thermal power.Reactor thermal power at 81%, holding due to high river hT.Commenced reducing thermal power due to high river hT.Reactor thermal power at 64%thermal power, holding due to high river hT.1/30 0100 0700 1700 2230 2300 Commenced power ascension from 64%thermal power.Commenced PCEO~i from 93%thermal power.Reactor thermal power at 99%, maximum flow.Commenced reducing thermal power due to high river hT.Reactor thermal power at 90%, holding due to high river dT.1/31 0615 1414 2400 Commenced PCIOMR from 90%thermal power.Reactor thermal power at 99%thermal limited.Reactor thermal power at 99%thermal limited.

8 Date Time Si~nificant

'Cljeexational Events Unit 2 Event 1/02 2227 2300 Reducing thermal power from 99%for turbine con-trol valve 1 ests and SI's.Reactor thermal power at 84%, turbine control valve tests and SI's in progress.1/03 0050 0245 0730 1124 1605 1843 1930 Turbine control valve tests and SVs complete, commenced power ascension from 84%thermal po~er.Commenced PCIO~i from 97%thermal power.R.eactor t:hermal power,g.99%, maximum flow.Reactor Scram No..112'rom,99%thermal power while opening PCB 5248 to obtain bushing CT o: f.l samples, a 500-kv bus-to-bus rel'ay opera'tidn

'ccurred.This.result',ed in breaker 5244 opening causing the unit to trip.C',ommenced rod withdrawal for start up.Reactor Critical No.123.Hain turbine reste-No.6 combined intermediate valve would not open, startup on hold.1/04 0105 0415 0600 1200 1230 1700'1750 Reactor brought sub-critf.cal for maintenance on I No.6 CIV.Reactor Critical No.1'24 due to cold water in-'ection by reactor feed pumps, E)rought reactor sub-critical and holding;for'wox'k on No.6 CI'V.Maintenance complete on No.6 CIV, commenced rod withdrawal for startup.Reactor Critical No.125.Enrolled T/G..Synchronized genexator, commenced power'asCensiCn.

1'/05 0400 Commenced PCIOMR from 54%thermal power (sequence"A").1/06 0905 2113 2255 Reduced thernml power from 94%to 90%for removal'of"Al" and"A2" high pressure heaters from s'ervice for maintenance.

Reduced thermal power to 64%for control rod adjustment.

Control x'od acljustment complete, commenced pow'er ascension.

1/07 0040 0645 Reactor thermal power at 92%, holding for maintenance on"Al" and"A2" high pres;ure heaters."Al" and"A2" high pressure heaters back in service, commenced PCIO'.IR.1/08 0030 Reactor thermal power at 99%, mavimum flo'w.

Si nificant 0 erational Events Unit 2 Date Time Event 1/08 1428 1500 1605 2000 2030 Reduced thermal power to 55%to withdraw.control rod 34-27 after maintenance.

Withdrawing control rod 34-27, commenced power ascension from 55%thermal power.Commenced PCIOMR from 95%thermal power.Reactor thermal power at 99%, maximum flow.Reduced thermal power to 90%for removal of"Al" and"A2" high pressure heaters from service for maintenance.

1/09 0440 0500 0700"Al" and"A2" high pressure heaters back in service, commenced power ascension.

Commenced PCIQ~from 97%.thermal power.Reactor thermal power at 99%, maximum flow.1/10 0130 0250 0252 0700 Reactor thermal power to 89%for turbine control valve tests and SI's.Turbine control valve tests and SI's complete, commenced power ascension.

Commenced PCIOHR from 97%thermal power.Reactor thermal power at 99%, maximum flow.1/16 2247 Commenced reducing thermal power for control rod pattern adjustment, turbine control valve tests and SI 1/17 0050 0340 0500 0520 Reactor thermal power at 45%, commenced control rod pattern adjustment, turbine control valve tests and SI's.Control rod pattern adjustment complete, commenced power ascension.

Reactor thermal power at 60%, holding for turbine control valve tests and SI's.Turbine control valve tests and SI's complete, commenced PCIOMR from 60%thermal power.1/18 1600 Reactor thermal power at 99%, maximum flow.1/23 2310 Commenced reducing thermal power for control rod pattern adjustment, turbine control valve tests and SI's.1/24 0200 Reactor thermal power at 52%, holding for control rod pattern adjustment, turbine control valve tests and SI's.

10~Si inificant Operational Events Unit 2 Date Time Event 1/24 0335 2030 Control rod pattern adjustment, turbine control valve tests and SI's complete, commenced PCIONR., Reactor thermal power, at 99/-, maximi~.flow.'/25 2200 Commenced reducing thermal power due to high river dT.1/26 0700 1000 2110 Reac.tor thermal power at 67%, hol'ding due to high rive.r dT.Commenced power ascension from 67%thermal power.Commenced PCIGiM from 88%thermal, power.1/28 0348 1340 1412 Reac.tor thermal plower at 99%, maximum flow.Reduceii thermal.plower to 82%due to high river dT.Reduced thermal power to 64%due to high river bT.1/29 0430 0700 0800 0930 1000 1335 1500 1608 1800 1905 2000 Commenced, power ascension from 64%thermal power.Commenced PCIOMR from 97/t'hermal power.Reactor thermal power at 99%, maximum flow.C'ommenced reducing thera~tl power due to ACNE'LPD.Reactor<<hermal power at 98%, maximum flow.C'ommenced reducing thermal power due to'high river b,T'.Reactor thermal power at 54%, holding due t:o high river dT.Coaaaenced power ascension from 64%thermal power.R'.eactor t:hermal power at 91%, holding due t:o high river bT.Coaanenced reducing theranxl power due<<o high river biT,.Reactor thermal power at 63%, holding due t;o high river dT., 1/30'540 0800 0903 1400 1425 2200 2230 2300 Coaanenced power ascension from 63/thermal power'.Reactor thermal power at 94%, holding due t;o high river dT.Coaanenced reducing thermal power due to lhigh river'T.Reactor thermal power at 90%, holding due to high river dT.Coaanenced power ascension from 90%thermal power.Reactor thermal power at 94%, holding due<<o high river dT,.Commenced reducing thermal power due to~high t'iver dT.Reactor thermal power at 82%, holding dUe to high river dT,.

11 Si nificant 0 erational Events Unit 2 Date Time Event 1/31 0213 0435 0600 0608 0830 1050 1440 1500 2400 Commenced power ascension from 82%thermal power.Commenced reducing thermal power from 90%, due to high river dT.Reactor thermal power at 64%, holding due to high river dT.Commenced power ascension from 64%thermal power.Commenced PCIOMR from 94%thermal power.Commenced reducing thermal power from 99%, due to high river hT.Commenced power ascension from 77%thermal power.Reactor thermal power at 87%, holding due to high river hT.Reactor thermal power at 87%, holding due to high river hT, Equipment malfunction (1) 12~Si~~ni'f icant.O~erational Event:s Unit 3 Date Time Event: 1/01 0001 0700 EOC-3 Refuel outage continues.

Filling vessel for hydro.1/02 1230 1300 1540 2300 Began pressurizing vessel for hydro test.'eactor vessel at 100 psig.Reactor vessrel at 500 psig.Decreasing reactor pressure to at:mosphere.

i 1/03 0755 1010 1545 1730 Began raising vesse]L level for hydro test.Reactor vessel at 510 psig, hydro test in progress.Reactor vessel at, 1005 psig and holding for in-spection of drywell,.Hydro test complete,, awaiting CCW repairS.'200 CCW repairs co~mplete, startup te.ts in progress.~

1/14 1420 1945 2238 Dwell leaguc test complet:e.

Drywe13.entry for maintenance on MSIV's.Dwell leaguc test'.complet:e.

1/16 0100 1550 1900 1936 2044 2053 Drywell entry for maintenance on"B" recirculation pumZ>.Maintenance complete on"B" recirculation pump.Drywel,l lea1c test: complet Commenced rod yithdrawali for startup.Reactor Critical No.101., Reactor sub-critical.

1/17 0250 1225 1245'1420 2205 2220 Reactor Critical No.102Reset main turbine.Increasing reactor pressure-to rated.Holcling reactor pressure at 565 psi, SJAE problems.Increasing pressure to rated, 920 psi.Tripped turbine for maintenance.

1/aS 0420 0537 1145 1437 1531 1533 1545 1931 1948 2300 Reset main turbine.Reactor placed in run mode.R.oliLed T/G.Synchronized generator, commenced power, ascension.

Main turbine tripped at 21%thermal power, moisture seperator problems.Main turbine reset.Synchronized generator, commenced power,asc,ension.

Tripped main turbinie for.overspeed trip test at 21%thermal power.Synchronized generator, commenced power ascension.

Reactor thermal powder at 24%, startup tests in progress (control cabell core-A2 sequence).

13 Si nificant 0 erational Events Unit 3 Date Time Event 1/Zl 0515 0750 0845 1130 1500 Commenced'ower Reactor thermal progress.Reduced thermal progress.Commenced power Reactor thermal progress.ascension, startup tests in progress.power at 30%, startup tests in power to 25%, startup tests in ascension, startup tests in progress.power at 38%, startup tests in 1/Z2 1315 1500 Commenced power ascension, startup tests in progress.Reactor thermal power at 52%, startup tests in progress.1/Z3 0951 1230 Startup tests complete, commenced power ascension.

Commenced PCIOMR from 60%thermal power.1/Z5 1330 2350 Reactor thermal power at 97%, maximum flow.Reactor thermal power at 96%, maximum flow.1/26 0700 1550 1900 2330 Reactor thermal power at 94%, mazimum flow.Commenced reducing thermal power due to high river hT.Reactor thermal power at 67%, holding due to high river hT.Reduced thermal power to 55%for control rod pattern adjustment.

1/Z7 0003 0400 Control rod pattern adjustment complete, commenced power ascension.

Commenced PCIOMR from 68%thermal power.1/28 1435 1445 1530 1545 1910 2300 Commenced reducing thermal power from 98%due to high river IT.Reactor thermal power at 93%, holding due to high river dT..Commenced reducing thermal power due to high river'T.Reactor thermal powex at 84%, holding due to high river hT.Commenced reducing thermal power due to high river hT.Reactor thermal power at 64%, holding due to high river hT.1/29 0351 0500 Commenced power ascension from 64%thermal po~er.Commenced PCIO~iK from 83%thermal power.1/30 0100 Reactor thermal power at 99%, maximum flow.

Si~ni.ficant 0~erational Events Unit 3 Date Time-Eveni 1/30 1718 2000 2021 2130 Commenced.

reducing thermal power for Special Test ST 191 on west scram discharge volume header.Reactor thei~l power at 96%,'holding, for ST:L91.ST 191 comp.'Lete, commenced power ascension.

Commenced reducing thermal power from 98%for RTI 32A (Recirculation

'.Pumps).1/31 0140 0515 0700 0800 1930 2300 2400 Reactor thermal power at 63%, RTI 32A in progress, RTI 32A, completecommenced power ascension., R.eactor thermal power at 71%, holding due to high river bT.Cormaenced power ascension from 71%thermal power.C'ommenced PCIOHR from 89%'therma.L power.R.educing thermal power from 92%due to high r:Lver bT.Holding at 74%power.~~

15 AVERAGE DAILY UiVIT POWER LEVEL DOCKET iVO.Browns Ferry-1 DATE 2-1-81 COMPLETED BY Ted Thorn TELEPHONE 205-729-6846 MONTH Januarv 1981 DAY AVERAGE DAlLY POWER LEVEL (MWe-Net)I 874 DAY AVERAGE DAlLY POWER LEVEL (MWe-iVet)

'1050 17 10]2 13 14 15 16 994 1046 1066 1062 1066 1055 1051 1058 1053 1060 1057 1067 1061 1055 1059 18 19 20 21 22 23 25 26 27 28 29 30 31 1058 1045 1017 1049 1041 1009 733 936 990 1052.1017 903 944 1025 INSTRUCTIONS On this format, list the average daily unit power level in M'iVe.Net for cachiday'in'the rcpiirting inonth.Ci>>nputc to the nearest whole me<,awat t.I9(77) 16 AVERAGE DAILY I'JNIT POWER LEVEL DOCKET NO.UNIT DATE COMPLETED BY TELEPHONE 50-260 Brotrns Ferzy-2 2-1-81 Ted Thorn 205-72'9-6846 MONTH January 1981 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)I 108.'2 106,'2 488 98 875 967 1030 1028 1043 I7 19 20 22'23 24 25 AVERAGE DAILY POWER LEVEL (MWe.ilTet)., 729 1009 1065 106:3 1,070 1068 1052 928 1051 IO l2 l3 15 16 1072 107.5 1072 108,1 1'078 1076 1066 26'27 29 30 7'92 1058 905 853 894 910 INSTRUCTIONS On this format,!ist the avcraje daily unit pi>wer lei<<l in MtVe.NIet fIor each day in the rcpt>rting ini>nth.Ci>ihputc rid the nearest whole megawatt.I<)/77 I 17 AVERAGE DAlLY UNIT POWER LEVEL DOCKET NQ.50 296 BI'owns Fex'~-3 2-1-81 DATE COMPLETED BY TELEPHONE 205-729-6846 IO DAY AVERAGE DAILY POWER LEVEL (LII We-Net)I-7-10 DAY AVERAGE DAILY POWER LEVEL (MWe.Net)~~9 l7 61-10-a0 19 20 21 200 183 269 447 IO I2 l3 14 IS 16 23'74 25 26 27 28 a9 30 3l 839 1020 914 805 903 946 1026 800 INSTRUCTIONS ,On tltis format, list thc average daily unit power-'Icicl in Mac.Nct for each;day~in<the rcp'ortinl'lonttl.

Colnputc to the nearest whole megawatt.(t)/77'I 0 4l 18 OPERATING DATA REPORT OPERATIi fG STATUS DOCKET NO.DATE COMPLETED BY Ted Them'.TELEPHONE~~o-6846 Notes 1.Unit iVame: Browns Ferzv-1 , 2.Reporting Period: 3.Licensed Thermal Power (lvIWt)t 3293 4.Nameplate Rating (Gross MWe): 1152 S.Design Electrical Rating (Net MWe):: mm e able a acitv Net hIWe: 7..laxirnum Dep nd C p.()8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report.Give Reasons: NA 9.Power Level To Which Restricted, If Any (iVet ilIWe): 10.Reasons For Restrictions, If Any: This Month 744 31.Hours In Reporting Period 12.iVumber Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On-Line 15.Unit Reserve Shutdown Hours l6.Gross Thermal Energy Generated (MWH)I'7.Gross Electrical Energy Generated (MWH)18.iVet Electrical Energy Generated (MWH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (Using iiIDC Net)22.Unit Capacity Factor (Using DER iVet)23.Unit Forced Outage Rate 0 24.Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration Refuel April, 1981 Yr..to-Date 744 744 744 0 2,291,359 775 790 757,271 100 100 95'95.6 0 of Each):/Cumulative 57,026 35,550.57 5,098.87 34,736.82 0 95,583,720 31 539 080 30,621.088 60.9.60.9 50.4 50.4 28.9 2S.If Shut Down At End Of Report Period.Estimated Date of Startup: 26.Units ln Test Status(Prior to Commercial Opemtiun):

1 Forecast Achieved liNITIAL CRITlCALITY liVITIA L ELECTR ICITY CO~I~IERCIAL OPERATIOiV (4/77)

,OPERATING DATA REPORT DOCKET IVO.50-260 DATE 2-1-81 COi>IPLIETED

'BY~>~hah.TELEPHONE 2Q.'~29=$846 OPERATING STATUS I.Unit iName: Brows Ferr7-2'.Licensed Thermal Power (MWt): 4.Namephte Rating (Gross ilIWe): "*"'*'i'::Pi

"'": 6'.Maximum Dependable t apacity (Gross MWe): 1098.4 Notes, 7.>IIaximum Dependable Capacity (Net>5>I'IVe):

S.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report.,Give Reasons: NA 9.Power Level'To Which IRestric'ted, If Any (Net MWe): 10.Reasons For Restrictiotts, If Any:/This Month Yr..to.Date 744 744 11.Hours In Reporting Period 12.Number Of Hours Reactbr Was Critical.13.Reactor Reserve Shutdown Hoiars 14.'ours Generator On-Line 15.Unit Reserve Shutdown Hours, 16.Gross Thermal Energy Generated (MWH),17.'Gross Electrical Energy Generated (>IIWH)IS.Net Electrical Fnergy Generated (il'IWH), 19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Fac'tor (Using MDC IVet)22.Unit Capacity Factor (Using DIER Net)23.Unit Forced Outage Rate 24.'Shutdowns Scheduled Over Next,6 Montlts~727.17 727.17 16.83...,$6.P3, 713.57 713,.57,'0 2 155~5i'0 2 1~55 570 728 490'728,490 711, 450...'11,, 450 95;9 95.9'9 9~9 89.8)R.H 89.8 9.4.1 4 (Type.Date, and Duration of Each): Cumulative

~51,937 31 470.,78 ,~12,470.,31 II 30 454,.53 0 85 228, 213 28,4!65, 678 27,6I61,757 50.0 32 25.If Shut Down At End Of Report Period, E!>timatedl Dale of Stdrtut5: 26.Units In Test Status IPrior to Comimercial Operation):

INITIAL CRITICALITY l>VITIA L ELECTRICITY COiINIE',RCIAL OPERATION Forecdst Achieved (0)/77) 20 OPERATING STATUS OPERATING DATA REPORT DOCKET NO.DATE 2-2-~L COLPIPLETED I}Y ed Thorn TELEPHONE~O-72-6866 Notes 1.Unit iVame Bzowns Ferrv-32.Reporting Period: Januar 1981 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross MWe): 1152 5.Design Electrical Rating (Net LWIWe): 6.idaximum Dependable Capacity (Gross iPIWe): 1098.4 1065 e a acit iVet 6'PIWe: 7.flax>mum Dependabl C p y ()8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: NA 9.Power Level To Which Restricted, If Any (iVet LPIWe): 10.Reasons For Restrictions, lf Any: 11.Hours In Reporting Period 12.iVumber,Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On Line 15.Unit Reserve Shutdown liours 16.Gross Thermal Energy Generated (MWH)I'7.Gross Electrical Energy Generated (MWH)18.i let Electrical Energy Generated (iPIWH).19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (Using AIDC iVet)~H.Unit Capacity Factor (Using DER iVet)23.Unit Forced Outage Rate 24.Shutdowns Scheduled Over Next 6 Months (Type.This Month Yr:to-Date 744 744 357.32 16.08 320.87 0 671,059 357.32 16.08 320.87 0 671,059 43.1 43.1 26.9 26.9 43.1 43.1 26.9 26.9 0 0 Date.and Duration of Each): 222,610 222,610 213,503 213,503 Cumulative 34 392 26 328.87',826.97 25,710.87 0 75,036,087 24,761,640 24,037 826 74.8 74.8.65.6 65.6 9.7 25.If Shut Down At End Of Report Period.Estimated Date of Startup: 26.Units ln Test Status (Prior to Commercial Operation}:

Forecast Achieved liVITIA L CRITICALITY liVITIAL ELECTRICITY

'CO!PDIE RCIAL OPERATION (o/77) 4h'I UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT hl Off fl I~Jan<a<DOCKET NO.UNlq NAhIE Browns Ferr-1 COhlPLEYEI)

IIY 1caLXhaa-TELEPIIONF 205-729-68th6 IVll.Date a-rh aO fa J V)Liccnscc Event Rcport Er Eh N w Cr 0 C C~O Cause trc Corrective Action lo Prcvcnt Recurrence 163 810123"A" recirculation pump out for brush replacement 164 810129 High river AT I': Forced S: Scheduled<<)/77)Reason: A-EEIuipinent Failure (Explain)ll.hlaintenance or Test.C-Refueling D Regulatory Rest riot iun E-Operator Training h, Uccnsc Exanunation F.Administrative G.Operational Error (Explain)II Other (Explain)hlethod: I-hlanual 2 hlanual Scram.3-Automatic Scram.4 Other (Explaitt)

Exhibit G-Instructions for Preparation ol'Data Entry Sltects for Li>>cnsec Event Report (I.ER)Fil>>INUREG.OI6I)Ezhtbtt I Same Smtn.i UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORThIONTII January DOCKET NO 50-260 DA'T'E 2 1-81 COMPLETED it@Tdd Thorn ,TELEPIIONE 205-729-'6846 Vt!Date r!rn ft L Q tO iu.~III~$I~nnrnn Vrcl~Irur Event.Repoit~I t Ir.EI'0~n O V Q c!I Q CJ Cau'se Ar Corrective AI:lion tii Prevent R'ecuircnce'62 810103 30'.43 PCS 5248 did nioi'open Mithiint sevent (7)rvcles causing breaker failure rela.o erati'on and turbine tri 81011 6 166 810123 1 rl7 Jv r nl A 1')rt 168 810128 169 810129 170 810129 91A111 VJVJVJ 172 810131'63 810106 164 , 810108'F D D Control rod attern ad ustment 1<ithdrawal of control rod 34-27 after~rr n i tt t nun n rr n~IIV irrut nrt n Control rod-.pattern-'djustments, tur-I 4 nAnnt rtl trnl ttn I nut'u nnrt UJllC VVllVLVJ ttlltv~va~ST Is High river'hT..Hi h river hT'i'river AT t~u 1 r Artt Il J Ii r JVer rJ J Hiitii river AT High river AT , Control rod pattern',adjustm'ents, tur-bine control valve tests and SI's I'!!rr crt S: Sclicduled RC1son A.Equipment Failure (Explain)t84Iaintcnancc otr Tr st C.Refueling D.Regulatory Restriction.I;.OpCiatiif Traimfig ou(Lreeitse FXaliililutlunt F-Adnunist rat lac G Opcratioiial Error (Explain)it-Otlrnr (Explahi)3 hlethod: I.Manual\t~...I'Q.J tt tuituu t v Cr u it~3-Autoiitatic Scram'.4 Other (Explain)-Exllibit G-Instructions fiir Picparation of Data-.-Etttrv'SI!eels toi.!.me!!sec Event Rcpo'll (LLIR)File,(NUREG

'16I)Exhtrbit,l

~Sante Source UNIT Sl(UTDOiVNS AND PONIER REDUCTlONS REPORT hhON'Phh~haaaaa DOCKET NO.Brotrns Ferr-3 DATE 2-1-81 COhlPLETED BY Nhh.l)atc hah rh aa Ph Llcenscc Fvent Report Er Eh Rh'EE aa m Cr hh ()Rh r Q CJ Cause k Corrcctivc Action to Prcvcnl Rccurrcnce 154 155 157 810126 810128 810130 S 810131 D B Hi h river hT Ili 4 river AT S ter to test RTI-.32A lligh river AT F: Fiirced S: Sclieduled (h)/77)Reason: A-Equipment Failure (Explain)B.h(aintenance or Test C-Refueling D Regulatory Restriction E Operator Training k, Liccnsc Examination F.Administrative G Operational Error (Explain)I l.Other (Explain)hlethod: I hlanual 2 hlanual Scram.3-Auloinatic Scram.4 Otllcf (Explalll)

Exhibit C-instructions for Preparation of Data Fntry Sheets for Licensee Ev nt Report (LER)Fil'(NUREG-0161)Exhibit I~Samnite Shiiirh,c 0

BRO!'HS FERRY NUCLEAR PLANT UNIT 1 ELECTRICAL HAIHTEHANCE SVlQ'fhRY poo Ohe Hooch of~Jannao 19 81 D, re 1/5/81 System Fire Protection Component Fire protec-tion batteries in panel 1-25-286 Hature of Haintenance Meekly battery check EMI 4A Etkect on a e Operation of The Reactor None Cause of Halfunction During mainten-ance check the specific gravity of two batteries was found to be lowe~Results of'Halfunction Two batteries were incapable of main-taining a sufficient charge.Action Taken To Preclude R=currence The batteries were replaced.TR8193765 1/14/81 Fire Smoke Detector Protection XA 39-29-B Smoke detector alarmed and would not clear in the relay room.(Control Bay Elev.3C)This alarm would have masked alar'signals from detectors in the r'clay room.Bad smoke detec-, tor.An inadvertent alarm.Replaced smoke detec-tor.TRII189453 BFRO-50-259/8102 ll/19/81 I I I I Core Spray 1land Control HS 75-5A errat Cooling Switch for lA ic.Core Spray Pump None, the mode of failure did not make the Core Spray Pump inoperable.

HS 75-5A operat-Difficulty in trip-Replaced the hand ing erratically.

ping breaker with switch per EHI 23.hand switch.TR8203203 1/21/81 Radiation Honitoring System Annunciator Alarm for the Stack Gas Radiation Honitor Annunciator Alarm Inoper-able None Loose annuncia-tor card Alarm inoperable Tightened annunciator card, the alarm was tested and operated properly.TR//188911 1/16/81 250 Volt DC Board Normal feeder breaker for Vnit 1 back-up Control Center panel 23-32 Breaker inoperable None Morn stops on main line contac bar and the brea er was out of alignment.

Normal feeder break er inoperable Repaired stops aligneP breaker and performedi EHI 7, breaker operat ed properly.TR818946 TR8203426 BRO!lNS'FERRX'UCLEAR PL~lT.UNIT'.ELECTRICAL MAINTENANCE St&IHARY For the Honth of January 19 81 Ie I I I I I Date System Component E ect.on a e Nature of Operation of Haintenance The Reactor Cause of:falfunction.

Results of ,efalfunc tion Action-Taken'o Preclude R-currence 1/8/81 Fire rotection attery-in'anel 2-25-303 I!ell Ill Loose terminal post None Loose terminal post Loose.terminal, post, connection.was: not broken.Replaced bat'tery-.

TR8106475 I (/12/81 Core Spray-, 1 4'4UV J.l.lib CV2-.75-22'lve,would'ev rr I'e vie L4e e electrically None The feeder break ov rraee 1 rroao\e~)thus not making.proper connectio vaive wouid'ot operJ-'ot o ol ort vlrllllv r Jglll elleu'lrcu J.l or valve'o6erated properly..-

TRif203338 JI./29/81 ontrol od Dri.ve., y s t eiTr RD Water Tran er Valve 85-8 Valve would not electri-.Cally operae.e None Feeder breaker no fully racked in Valve-85-8:woul'd'oi eiectricaiiy.Operate Properly racked in breaker, va~ve;opeyated properly TR8221135-~

BROWNS FERRY NUCLEAI'LANT U!IXT 3 ELECTRICAL HAINTENANCE SUMIARY Dn'I'1/1/81 System Core Spray Cooling Component FCV-3-75-51 Nature of Haintenance FCV-3-75-51 would not operate from control switch E eeet on a e Operation of The Reactor None Cause of Nalfunction Broken wire in cable.Results of Nalfunction Valve interlock between FCV 75-51 and FCV 75-53 inoperable Action Taken To Preclude Recurrence Replaced broken cable valve operated proper i TR8203135 TR/)142229 1 il/5/81 I I I Diesel Generators 3EC Diesel Generator Annunciator Panel Annunciator inoperable None Bad annunciator power supply.annunciator inoperative Replaced power supp y annunciator alarms operated properly.TR8203159 Il/6/81 IIPCI I I I I I I HPCI Governor EHI 36'/on-Unit in cold shutdown During perform-ance of IIPCI overspeed test, the IIPCI failed to trip due eo a bad coil and diode in the PCV 73-18B circuit Trip circuit inoperable Replaced the bad coil and diode.Completed overspeed test.TRPi219303 TR8190632';-

='.1/9/81 Control Bay Panels Scram reset switch on panel 9-5 Switch binding None and stiff Switch operator spring broken Switch operated stiff and binding Replaced switch oI tor, switch operated properly.TR8203147 (1/10/81 Diesel Generator DG 3A While perform-ing (SI 4.9.A.1.B)

Load Accept-ance Test DG3A tr'ipped.Hone SSPl and SSP2 out of adjust-ment which cause the generator breaker to close too soon.DG 3A tripped Adjusted settings as specified in ENI 72, performed SI4.9.A.l.g DG operated properly TR8163870 BFR0296/8104 BRO!iHS PERRY NUCLEAR PLANT UNIT 3 ELECTRICAL HAIHTEHAlVCE SU?R{ARY.Por the?{Onth of January 19 81 Date System Component Nature of Haintenance Et ect on G e.Operation of The Reactor Cause of<<fnlfunction Results of~<<{al func t ion Action Taken To Preclude Recurrence

.1/10/81 Core Spray Cooling HCV 75-1&Inoperative HCV 75-12 indicating indicating lights for l I C"4 I ilrlf 7I 1 X.LLGaa4 4LL4ul.4LgaaaaV I J=J.aa IHCV 75-12 None Bad cable from Panel 9-3 to JB 3It79 Inoperative indicating

=light circuit.Replaced the bad cabl lights operated p'rope Ilnhh1hh maalfhnhlah L ti tt C V 3 J 0 0 h f<<ft C V J J 07 TA II2041 58 TR8204157 1/10/81 Reactor 5AR13C relay Problem in'ro'tection on panel 9-.15 resetting<scram None Relay contacts burned Problem in resetting g scram when brought in by C Startup Rang hfhnitnv~a Replaced burned conta)t returned to service.TRft2v3102 P rima rai Containment DCO-6l-16 otor React nr anne pressure limit-er open would not annunciate Hnne PDCO-64-16 motor inopera-tive Damper inoperable Replaced omdutrol motor, dampers operated properly mn Ii 1 C a'h 1 lKftl0077l, I~a Ih~'LI LLI OL iesel.eneratnrs C Diesel'nelato1 xhaust fan='ndicating

?Light circuit Oth 1ed'nd fareen indicat-ing lights burn ontinually Hone Auxihliary contacts sticking aalu 1~f a 4 aa~t aalu JUII L L4Q 4 4d indicating lights inoperable auxiliary contact mechanism, contacts worked properly.mnIInnh1nn If<<ffCV J J77 Local Aolll LV J aW Jl l~l'Clealleu/15/81<<eactor 4ailding losed ooling iater oolillg unl.t 2 fan damper Indicating light inope1-able on panel'-25 Hone Actus tiiig G1iii on damper shaft bent thus not contacting with position switc?1 dffrinfi nneratinn cycle.Indieatinag ligaat circuit inoperable Adjusted and st raioht" ened act'uator switch, indicating light operated properly mRga{)'l877 I s~~ERO'RTIS PERRY UUCEEiii PI.RRT UUXT'ELECTRICAL HAINTENANCE SUl MARY For the.'month of January 19 81 Date 1/15/81 System Reactor Control Conponent Relay 3BKl relay (Pnl9-5)Nature of.lfaintenancc Unit preferred breaker 602 tripped when fuse failure alarm came in E lect on'a e Operatio>>of Thc Reactor Cause of",fal func tion Instruments and controls Bus A an Unit Preferred Bus tied together through relay 3BK1 due to in-proper wiring Results of Nalfunction Relay contacts damaged due to impro per voltages and the tripping of breaker 602.Action Taken To Preclude R"currcnce Corrected wiring and replaced burned con-tacts.TRIY203869 1/16/81 Battery Board 3 eactor Bldg.nwatering ump"B" losing ircuitry Ground on 480V Common Hd.3 Control power None Terminal block in Unwatering Pump Control Station grounded due to corrosion.

This ground caused a ground on II3 Battery Hoard Replaced the bad 12 point terminal block, ground cleared.TR8203880 1/17/81 80 Volt hutdown oard ormal feeder Inoperable reaker 480V Breaker hutdown Bd.3A None The breaker was out of alignment and had worn stop.on main line con-tact bar.Normal supply breake inoperable.

Repaired stops and~realigned breaker, perform B!I 7, break-;er operated properly.'R8204021 TR8190530I PIRO!'AS PEP%X'UCLEA1'-

PLANT UNIT Common ELECTRICAL MAINTENANCE SU?&fARX For the?fonth of.'anuarY 19 81 System Component Na'tur e., o f.Haintenance f?feet on-.ate'peration of.The Reactor Cause of".falfunction Results of Ifalfunction Actiotl Taken To Preclud'e Recurrence 1/13/81 ,~High Pres--sure Fire'rotection

'A" Fire Pump trainer ACB Strainer inoperable None Foward contactor use hung open.and the coniacis vere hnrned.The strainer was inoperable to-rotate LUL Iadl D,WdDI~\gCJCa Cleaned and lubricate mechanical parts of led new co'ntacts, strainer operated.properly.TR//20391~

'1/19/81 Air-Condi-tioning iieating)B,.Control Ba Chiller'Oil~Imn Chill'er would not start None Oil pump motor sllaL L Woe ULula,CII Control Bay Chiller Ill DII~,'~%%%nt'1%%Jaa wad JIIUtacL aaa Jc Replaced pump moior;nina%%a%A nil fi1t'aar ahA 4%%%~~%%%%%replaced the recycle'tim'er,-, chiller operat~properly..

TR8190525'aRI'I190526 u./L3/ul I I tandby Gas ran t maanl rain C t,'Relay R70B)umidity iieater innnerabl'Ia iiumidity Heaier{nnnlartlblta n 2 1'1 Ddlt Leldg I UJJ IIUIIIJaa JI y aacaa.cro II" O'A4 a U%%sa r%%.inoperable due to bad relay coil Dn%%t s%%nA%%%a%an%at 4 n h1 nkf a'%%%L%%%%%%~%%%%+%~on relay, relay operab properly.TRf/220912 1 DD O'VD A<A't I%0 I Al AA I.LILIX aaa aav Jv.a 4 J t%a@v~

CSSC E UIPHENT~~~~DROWNS FERRY NUCLEAR PLANT UNITs 1,2&3 INSTRlktBNT MAINTENANCE SlkkfARY FOR THE MONTH OF JanuarY 19 81 DATE SYSTEM Unit 1 1-15 Core Spray 1-23 Radwaste COMPONENT PDIS-75-28 LA-77-14A NATURE OF MAINTENANCE Replace Replace EFFECT ON SAFE OPERATION OF THE REACTOR None None CAUSE OF MALFUNCTION Switch Would Not Repeat Faulty Meter'elay RESULTS OF MALFUNCTION Two Previous LER's Alarm Would Not Clear ACTION TAKEN TO PRECLUDE RECURRENCE None None Unit 2 1-5 Radiation Monitor RE-90-132A Repair None Faulty, Reed Sw.Low Flow Alarm Would Not Clear None 1-20 Feedwater Control FM-46-4A Repair None Faulty Modifier Indicated Low Flow None Unit 3 1-6 Radwaste Core Spray LS-77-149.Jz FI-75-21 Calibrate Calibrate None None Setpoint Drift Instrument Drif t Pump Would Not Cut Off Did Not Indicate Correct Flow None None 1-12 Radwaste FT-77-16 Replace None Faulty Trans-mitter Indicator Showed Flow with Pump Off None BROWNS FERRY NUCLEAR'LANT UNIT 1, llECHANICAL llAINTENANCE

SUMMARY

For the month of January 19 81 DATE SYS TEN COMPONENT NATURE OF lfAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION

'CTION TAKEN TO'PRECLUDE RECURRENCE 1/2/81 RCIC Turbine&Pump 1/5 Diesel Gen.C diesel Gen.Low on oi-1 Blown gasket None None Low oil level Unknown Low oil Blown.gasket Add 3 pin'ts TR 198979 Unknown TR 189426 1/15 RHR Servic wat er 1/18 Diesei Air nnntnreeenv

~L%VVVL 1/15 HPCI Off iine mnnHtnr Drain Valve'Diesel Gen Smali ieakage Leakage Compressor t-eA 1&A 4 CJ A 4,%lJ None None None Fittings need cane Blown out Line leakage Steam leak ackin Bad compressor-Bearings worn out Capped iines Ttt 10OAA7 Repaired Valve TR 198075 Replaced compressor

'Pl?1001ttt~JWJ/JkJV 1/18 Diesel Gen U 1&2 C H&vent-diesel en Worn compress r None Worn bearings Bad:compressor-Replaced air compressor TR 199118 1/20 FPC 1/24 Control bai H&vent&AC 1/20 FPC 1/21 Off gas Valve 78-68 llcv-78-551 Suction pumper a--ran 18 control bav chiller Leakage Leakage Fan not closit-ee orr Stopped up strainer None None g None Nnne Unknown Unknown 11{rt v et rn4ner Slnw flnw Loose packing Packing leaking.Loose nacking Packing leaking Tightened packing TR 203446 Tightened packing~,TR'98075 Visually Inspected TR 188916 Cleaned strainer TR'190533 1/24 Controi'ag H&vent&I AC iB controi bay c hiller Broken vaive None Unknown BroKen valve Replaced valve TR 190533 CSSC E UIPHEHT BROWS FERRY NUCLEAR PLANT UNIT 2 I fEClIAHICAf MAINTENANCE SUM fARY For the Honth of January 19 81 SYSTEH COMPONENT NATURE OF 1'fAINTENANCE EFFECT ON SAFE OPERATION OF TllE REACTOR CAUSE OF HALFUHCTION RESULTS OF lfALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 1/6/81 1/8 NPCI CRD Pipe on bottom Leak oil tank Leak CRD module None None Unknown Deep cut in accum.wall Pipe union leaking Bad leak Tighten union I'R 102889 Installed new accumul-ator TR 188935 1/14 1/16 HPCI CRD Turbine oil sum 1" vent to drain Leak Loose clamps None None Loose union Unknown Union leaking Unknown Tighten union TR 217584 Replaced clamps TR 174222 1/22 1/24 Rx buildin cc water Tank Rx bldg El 593'ontrol ai Purge.Valve Leak Broken valve None None Cap off line Valve broken Unknown Replaced valve TR 190533 Valve leaking througl Placed cap on line CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 3, MECHANICAL MAINTENANCE SUffMARY For the Month of January 19 81.Page 1 of 2 SYSTEM COMPONENT EFFECT ON SAFE NATlJRE OF OPERATION OF ffAINTENANCE THE REACTOR CAUSE'OF MALFUNCTION RESULTS.OF MALFlJNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 1/3/81 CRD FCV-85-37A Valve locked in open posit on None Locked valve Valve not operating Repositioned ha'nd-wheel TR 1/6 1/7 Rx bldg vent Rx water vn 4vn a.'Gu JL4 Main steam I a'nI>>T aaa art.HP Fire rotection hPCI FSV 3-64-19 Marada valve n)X.'Q7 nrrl a>>a u ar r traa~25-70 Valve 1-253A nrrt 1 11 fa7V J IJ aa Fire pump strainer'FCV-I 3-].9 Faulty valve Vaive.not rrnrkinn Out of adjust ment Ltn vnl nt4nn>>a a%aaa L v a aa l k a at5 Seal leaks valve not None None None I>>Inn a a>>>>r a a%None Nonae Bad valve Unknowli Unknown Rl rat aa 1 nnan Loose packing land'Won-"e" ti"g Pressure port would no't close.Sl icking'valve Isolation valve c].osed ROtatinar;, St em Leakage Sterna As Lo tat J nt5 Replaced solenoid valve TR 198984 cI>>J44 cu va Jv'c R 1 n A~1 rn TR 158546 Opened valve mn]c86'r9 ,Atliusted plate TR 202967 Tightened TR 203006 Adjuated n<late TR 202967 1/8 EECW 3-67-769 valve Chiller leak None Valve seat bad Leaking through, Installed new valve TR=137275 EECW 3-67-770 valve Chil.ler leak None Valve seats bad.Leakiaag.

a.alrougha IaaatallQCul aaQ~w>>Val>>>>Q TR 137280 1/8.1/8 1/8 EECW EECW EECW Valve 3-67-763 Chiller leaK'4 d vra Valve'3-67-773 Chiller 38.leak Valve 3-67-779 Chiller 38 leak Valve 3-67-760 Valve leaking None None None'one Seats bad Seats bad Seats bad Seats bad Leaking valve Chi].ler leaking Chiller'lealcing ClIiller].eakage Installed new valve TR 137274 Installed llew valv TR 137277 Installed'new valve TR 137284, Instaiied new vaive TR 13/279 Secondary Containment Equip.Air loc-Comes open wh n None Rx other are clo ed Worn foot bolt'Door wouldn't close New.foot bolt.&adjust-ed door TR 198986 1/8 1/8 1/8 Fire Pt'ot crt inn CRD HP coolant T lnnt'lnn a.~a J%'4 t>>>rr~l.-rave pump CRD,Pump 3A HCV 73-201A Seal ieark Dirty filter Valve packing 1 aalr None None None nr 3.~i aa Jtatlaa.Uaa I v I GliQnment Worn filter Handwhee].

missi needed nat kinar 4eatcabe Unkno'w'n'ealcage nn 1 i 2 anl inn nl an>>I<<uaikgned Puu<<karl gl,ualu TR 203019 Replaced filter TR 203173 Rep]aced handwheel.

&added packing TR 202968

~~~~~~I I I~I~~s~I I I I'I I~I'~I~~'4~~~f~~~I~~, I~~~4~I~~~~~4 Cl 0~0 35 OUTAGE SUiiRY January 1981 The Unit 3 cycle 3 refueling outage which started November 23, 1980, was com-pleted January 18, 1981.The outage duration was 55 days which was 12 days longer than the 43 day duration projected prior to shutdown.This schedule overrun was primarily due to: 1.Delays in completion of the TIP work which, in turn, delayed Hydro.a.CRD timing and friction testing combined with PCIS testing restricted drywell access.b.Repairs to valve 85-37A, LPRM'onnectors repairs, additional repairs to"D" indezer and hydraulic control unit maintenance.

2.Equipment problems during H2/02 surveillance instructions (SI's)(relay failures)which held up completion of PCIS SI's.This work was an RPV Hydro prerequisite.

3.Mi'sce3:laneous equipment failures and setpoint adjustments required several unplanned drywell entries prior to startup.4.Additional HPCI turbine testing, which resulted from the late arrival of repair parts, and unscheduled maintenance on 3C turbine stop valve further delayed the unit 3 return to service.Major work items accomplished during the Unit 3 cycle 3 outage included: 1.Refuel Floor-Routine disassembly, LPRM replacement (8), fuel shuffle, invessel TV inspections, and reassembly.

2.Turbine Floor-Principal effort was limited to reactor feed pump maintenance since turbine inspections were deferred.3.Main Steam Isolation Valves-7 (of 8 total)failed initial leak rate testing and were subsequently dis-assembled, refurbished, and tested satisfactorily.

4.Control Rod Drive Maintenance

-Replaced 6 CRD's (34-31, 34-39, 30-03, 30-39, 26-43, and 30-23).

4I 36 OUTAGE.

SUMMARY

(Continued)

January 1981 5.Low Pressure Coolant In ection Modificatiun (P0141/L1845)-

This work modifies the automatic transfer scheme (swingbus).used in the power supply system to selected LPCI valves and, provides new batteries and a battery room in the miscellaneous equipment room of the diesel generator building Unit 3.6.Balance of Plant-Routine heat exchanger disassemblies, eddy-current inspections, repairs as required, and reassemblies.

No major problems detected.7.Condenser Circulatin Water CCW)Inlet Tunnel-The need for repairs on 4 joints was identified late in the outage which involved'pproximately 6 days additional (unscheduled) work.8.Raw Coolin Water Modification Preparations are underway for the upcoming Unit 1 cycle 4 outage scheduled to begin April 10, 1981.These preparations include: 2.3.Ordering, receiving, and staging material.Procedure preparation.

Prefabrication work.4.Modifications that do not require unit shutdown.5.'Personnel training.

45 4I JCi