ML18025B397
| ML18025B397 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/01/1981 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B396 | List: |
| References | |
| NUDOCS 8103170550 | |
| Download: ML18025B397 (46) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT February 1, 1981 February 28, 1981 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68',t By. 'ubmitted Plant Superintendent 8> 0817 0550
0 C
TABLE OF CONTENTS Operations Summary Refueling Information Significant Operational Events Average Daily Unit Power Level 16 Operating Data Reports 19 Unit .Shutdowns and Power Reductions. 22 Plant Maintenance ~ ~ ~ ~ ~ ~ ~ 25 Outage Summary . ~ ~ ~ ~ 37
4l 4k
I 1
0 erations Summar February 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 eleven reportable occurrences and four revisions to previous occurrences reported to the NRC during the month of February.
Unit 1 There was one scram on the unit during the month. On February 21, the reactor was manually scrammed so Unit 1 could swap from the spare phase trans-former back to "B" phase transformer and free the spare transformer for use by Unit 2.
Unit 2 There were two scrams on the unit during the month. On February 25, the reactor was manually scrammed so Unit 2 could swap from the "2C" phase trans-former to the spare transformer and free the "2C" transformer for use by Unit
- 3. The reactor was scrammed on February 28, due to a personnel error which led to having two inoperable APRMs in different RPS channels simultaneously out of bypass.
Unit 3 There were three scrams on the unit during the month. On February 3, the reactor scrammed due to an APRM HI HI flux from a change in the "B" recirculation flow when the "B" recirculation HG set switched feeder breakers due to a spurious signal of unknown origin. The reactor was manually scrammed on February 7, for a drywell entry to repair equipment. and check for drywell leaks. On February 23,
Operations SuImnarg (Continued)
February 1981; the reactor was manually scrammed to place Unit 3 on the- "2C" phase -.tr'an4-former 'because the Unit. 3 phase transformer began generating combustibl'e gases and to performed needed:niaintenance'. 'Unit 's'tartup was- subsequently delayed due to coupling pi..obleins on the L'PCX MG sets.
W ~* I t& P 4p=*
0 erations Summa (Continued)
February 1981 Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:
Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00501 0.00383 0.00329 Feedwater nozzle 0.24255 0.16511 0.12351 Closure studs 0.19832 0.13494 0.10049 Note: This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.
Common S stem Approximately 3.64E+05 gallons of waste liquid were discharged containing approximately 5.42E-Ol curies of activity.
Refuelin~Infor'mation February 1981'nit 1
Unit 1 is scheduled:Eor its fourth r'e'fueling beginning on or about April 10, 1981, with a scheduled'estart date. of July 23, 1981. This will involve loading additional 88 R (retrofit)
're'ueling
'.Euel assemlbies into, the core, the final:Eix os the sparg'er modification, power supply on LPCI modification generator brea'ker and ~unit station 'transformer tie-in (requires .Unit 2,to be,,shutdown)- and,tor'us.Imodifichti'ons,if,all,approvals are received.
There, are 764 fuel assemb>Lies in the'.reac'tor vi ssel. Th', spent fuel
-storage pool presently contains 550 spent' 'X 7 fuel assemblies, .fiv'e 8 X fuel 8'pent assemb/Lies, 72 new 8 X '8 R fue1 assemblies, arid one, spent 8 X 8 R fuel assembly. Because of modification work to increa e spent 'fuel pool to 3471 assemblies, present available capacity is limited'o 465 'apacity locations.
Unit 2 Uni't 2 is, scheduled:Eor its fourth r'efiheling'eginning on or about March 26, 1982, w:Lth a scheduled restax't date .of August 13, '1982. This refuel'ing outage will involve completing 'relief valve modifica'tions, torus if all approvals are received, "A" low pressuxe turbine in II
'odifications spection, MG set:Lnstallation for LPCI mo'dification and loading additional 8 X 8 R fuel assemblies into the coxe.
There are 764 fuel assemblies in the reactor vessel. ~~it the end of the month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharg'ed 'cycle 3 fuel assemblies in the
Refuelin Information (Continued)
February 1981 Unit 2 (Continued) spent fuel storage pool. The present available capacity of the spent fuel pool is 160 locations. With present capacity, the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capabiltiy in the pool. However, 949 new high density storage locations have been in-stalled, but cannot be used until Special Test 161 is completed.
Unit 3 Unit is scheduled for its fourth refueling beginning on or about September 25, 1981, with a scheduled restart date of February 7, 1982. Thi's refueling involves 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 modifications 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 fuel assemblies, 208 dis'charged 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.
Si nificant 0 erational Events Unit 1 Date Time Event 2/04/81 1915 "Al" and "A2" high pressure heaters placed in ser-vice, holding at 95% thermal power due to condensate demineralizer problems.
2/05/81 1600 Commenced PCIOHR from95% thermal power.
2200 Reactor thermal power" at 99%, maximum flow.
2/07/81 0155 Reduced thermal power to 77% for cntrol rod pattern adjustment.
0305 Increase thermal power to 90%, holding for CRD exercise.
0550 CRD exercise complete, commenced PCIOHR.
1030 ,Reactor thermal power at 99%, maximum flow.
2/08/81 0005 Reduced thermal power to 70% for turbine control valve tests and SI's.
0112 Turbine control valve tests and SI's complete, commenced power ascension.
0240 Commenced PCIOMR from 91% thermal power.
0700 Reactor thermal power at 99%, maximum flow.
2/10/81 1010 .Reduced thermal power to 93% for removal of "A" string high pressure heaters from service for maintenance.
2/11/81 0345 "A" string high pressure heaters in service, commenced power ascension.
0700 Reactor thermal power at 99%, maximum flow, rods limited.
2/13/81 0700 Reactor thermal power at 98%, maximum flow, rods limited.
2255 Commenced reducing thermal power for "B" recirculation MG set brush replacement.
2/14/81 0100 Reactor thermal power at 40%, holding for "B" recir-culation HG set brush replacement.
0250 "B" recirculation HG set in service, commenced power ascension.
0330 Reactor thermal power at 50%, holding for turbine control valve tests and SI's.
0520 Turbine control valve tests and SI's complete, commenced power ascension.
0830 Reduced thermal power from 68% to 64% for control rod pattern adjustment.
0900 Commenced power ascension from 64% thermal power.
1230 Commenced PCIOHR from 67% thermal power.
2/15/81 2230 Reactor thermal power at 99%, maximum flow rods limited.
44 V
Ei'~niffcant O~etatfanal Events Unit 1 Date Time Event 2/16/81 2300 Reactor thermal empower at 98%, maximum flow,', r'ods limited.
2/17/81 0700 Reactcir thermal ]power at 97%, maximum flow, rods limited.
1930 Reduced reactor thermal power to 78% for'bnt'rol rod power'haping.
2200 Control rod power shaping complete, commenced'CI~OMR.
2/18/81 1312 Reduced thermal ~power from 98% to 90% fdr kontrdl rod power'haping.
14'30 Control rod'ower shaping complete, commenced'CIiOMR.
2300 Reactor thermal power at 99~%, maximum flow,, rt>d
'imited.
2/19/81 1500 Reactor thermal powr at '98%, maximum flcIw> rod limited.
2/20/8i 2300 Reaictor thermal power at 99~%, maximum fl'ow,', rbd
'imited.
2/21/81 0001 Connnenced reducing thermal power for shutdt>>wn td place the unit on 1B main transformer fr'om'the spare transformer.
0145 Reactor Scram (manual) No. 140 frcim 35% po~er to place the unit on 1B main transformer fr'om'th'e spare transformer in order t:o spare out 3A mai~n trahs>
forfner for maintenance (there was a buildup of com-bustible gases in 3A t:ransformer).
1050'345 Connnenced riod withdrawal for startup.
Stopped withdrawing rods due t:o problems with'od
'700 18-31.
Commenced rod withdrawal for startup, rod 18-31 tagged.
1810 R'.eactor Critical Ho. 1.'61.
2130 R.ol;Led T/G.
2148 Synchronized generator, commenced power ascension.
2300 Reactor thermal power at 15%, holding due to pro-blems wit:h control rod. select P.B. for rod 58-19, (wi:Ll not: deselect) .
2344 Rod 58-19 deselect problems resolved, commenced power ascension.
2/22/81 2230 C'ommenced PCIOt>K friom 69% thermal power.
2/23/81 2300 Reactor thermal power at 99%, maximum fliow, rod limited.
Si nificant 0 erational Events Unit 1 Date Time Event 2/24/81 -
2335 Reduced thermal power to 96% for SI 4.3.A.2 (CRD exercise).
2/25/81 0035 CRD exercise complete, commenced power ascension.
0100 Reactor thermal power at 99%, maximum flow, rod limited.
2/28/81 0005 Reduced thermal power to 86% for turbine control valve tests and SI's.
0055 Turbine control valve tests and SI's complete, commenced power ascension.
0700 Reactor thermal power at 99%, maximum flow, rod limited.
2400 Reactor thermal power at 99%, maximum flow, rod limited.
Sfgnifi ant Operatfonal E~re<<<<<<s
'Unit 2 Dace . Time Event 2/01/81 0001 Commenced reducing thermal powei from 87%, due to high river hT.
0200 Reactor thermal power at 63%, holding due to high river hT.
0812 Commenced. power ascensioti from 63%'hermal power.
1100 Commenced PCIOHR from 91% t'hermal power.
1600 Reactor thermal power at 94X, holdf.ng due to high river,dT.
1805 Commenced, reducing thermal power due t:o lhigh rfver hT.
2300 Reactor th'ermal power at 67%, holding due to high river hT.
2/02/81 0300 Commenced power ascension from 67% thermal po~er.
0400 Commenced PCIGHR from 89% thermal power.
0800 Reactor thermal power at 91%, holding due to "C" string high pressure heat:ers being out of s'ervice.
1430 Commenced reducing reactor thermal power'o placIe "C" string hig'h pressure heater in thermal power at 83X, "C" string high servi/.e.'eac:tor 1455 pressuie heaters in service.
1500 Commenced PCIONR from 83% thermal power.
2020 Reactor thermal power at 94X, holding due to waste collector filter problems in radwasee and precoat of condensat;e demineralizers.
pr6ventfng'ackwash 2/03/81 0915 Commenced PCIO]<K from 94X thermal power.
2300 Reac,toi. thermal power, at 95%, holding due to waste collector filter problems in radwaste and precoat of condensat:e deminkraliderk.
pr&venting'ackwash 2356 Commenced PCIO~i,K from 95% thermal power. '/04/81 2/05/81 0100 Reactor. thexmal power, at 98%, VKLPD limited.
2/06/81 2130 Commenced reducing thermal power to withdraw rods afeer ST-191 which checks resphns'e dz con-'rol scram discharge header water level monitors.
2200 Reactor, tlhermal power ae 76%.
2210 Commenced power ascension from 76% therm<1 poacher.
2/07/81 0445 Connnenced PCIO'.IR from 95% thermal power.
0700 thermal power at 97%, O'K'LPD liml.eeIi. 'eactor
,2/08/81 0120 thermal power to 86% for turbine 'educed teses and SI's.
cokerlol'alve
Si nificant 0 erational Events Unit 2 Date Time Event 2/08/81 0245 Turbine control valve tests and SI's complete, commenced power ascension.
0330 Commenced PCIOMR from 95% thermal power.
0700 Reactor thermal power at 98%, CMFLPD limited.
2/10/81 -2300 Reactor thermal power at 97%, CMFLPD limited.
2/11/81 0910 Reactor thermal power at 96%, CMFLPD limited.
2300 Reactor thermal power at 97%, CMFLPD limited.
2/12/81 0700 Reactor thermal power at 95%, CMFLPD limited.
2300 Reactor thermal power at 96%, CMFLPD limited.
2/14/81 2217 Reduced thermal power to 64% for control rod pattern adjustment, turbine control valve tests and SI's.
2345 Control rod pattern adjustment, turbine control valve tests and SI's complete, commenced power ascension.
2/15/81 0050 Commenced PCIOMR from 87% thermal power.
1200 Reactor thermal power at 99%, maximum flow, rod limited.
2300 Reactor thermal power at 98%, maximum flow, rod limited.
2/16/81 0700 Reactor thermal power at 97%, maximum flow, rod limited.
2/17/81 1210 Commenced power ascension from 97% thermal power.
1500 Reactor thermal power at 99%, maximum flow, rod limited.
2/21181 0010 Reduced thermal power to 87% for turbine control valve tests and SI's.
0036 Turbine control valve tests and SI's complete, commenced power ascension.
0052 Commenced PCIOMR from 95% thermal power.
0630 Reactor thermal power at 99%, maximum flow, rod limited.
2/25/81 0100 Commenced reducing thermal power for shutdown to spare out 3A main transformer for maintenance.
0148 Reactor Scram (manual) No. 113 from 40% thermal power in order to spare out 3A main transformer for maintenance (there was a buildup of combust ble gases in 3A transformer).
4l 3.2 Si~nif icant, i0~era'tional Events, Unit 2 Date Time Event 2/25/81 1500 Commenced rod withdrawal fair .tartup.
1610 Eteactor Critical No. 126.
2/26/81 0115 Enrolled T/G.
0212 Synchr'onized generator, commenced power 2330 PCIOMR from 82X thermal power.
'asden'sion.'ommenced 2/27/81 0935 Reactor thermal power at 89X, holding de t:o computer problems.
1015 Cumputer problem.: resolved, holding at 89X po~er clue to "A" string high pressure heaters 'being'ut of,service.
2/28/81 1358 Reactor Scram No,. 114 'rom (1) 89X thermal power on EZRA's H3: while performing SI 4.1.Pi-15 (APBM gain).
1757 Commenced riod,withdrawal for .tartup.
2057 Reactor Critical No. 127.
2318 Rolled T/G.
2354 Synchronizeid generator, commenced power 'ascension.
2400 Power ascension in progress.
13 Si nificant 0 erational Events Unit 3 Date Time Event 2/01/81 0001- Commenced reducing thermal power from 74% due to high river dT.
0013 Reactor thermal power at 64%, holding due to high river AT.
0731 Commenced power ascension from 64% thermal power.
1130 Commenced PCIOMR from 95% thermal power.
1730 Reactor thermal power at 99%, maximum flow.
1822 Commenced reducing thermal power due to high river AT.
2300 Reactor thermal power at 77%, holding due to high river AT.
2/02/81 0300 Commenced power ascension from 77% therma'ower.
0330 Commenced PCIOMR from 87% thermal power.
1730 Reactor thermal power at 99%, maximum flow, rod limited.
2/03/81 0859 Reactor Scram No. 91 (2) from 99% thermal power, during the performance of SI 4.2.A-3 a spurious signal of unknown orgin momentarily caused a sudden increase in recirculation pump flow and APRM HI HI flux.
1805 Commenced rod withdrawal for startup.
2112 Reactor Critical No. 103.
2/04/81 0115 Rolled T/G.
0142 Synchronized generator, commenced power ascension.
1131 Commenced PCIOMR from 72% thermal power.
2/05/81 0130 Reactor thermal power at 82%, holding due to waste collector filter problems in radwaste preventing backwash and precoat of condensate demineralizers.
0605 Commenced power ascenison from 82% thermal power.
0700 Commenced PCIOMR from 89% thermal power.
1303 Reducing thermal power from 96% due to 1/4 isolation signal on "A" main steam line pressure.
1320 Reactor thermal power-at 93%, holding for SI 4.2.A-6 (main steam line lost pressure).
1435 SI 4.2.A-6 complete, replaced bad relay, commenced PCIOMR from 93% thermal power..
1800 Commenced reducing thermal power from 99% due to 1/4 isolation signal on "A" main steam line pressure.
2100 Reactor thermal power at 94% ("A" main steam line pressure, signal) instrument mechanics began trouble shooting low pressure switch.
2110 Commenced PCIOMR from 94% thermal power.
14 Signif icaht O~erational Events Unit 3 Date Time Event 2/06/81 0100 Reduced thermal power from 99% to 94% due to group I half isolations, ("A" main ~>>team line low pressure).
-0530 Commenced power ascension from 94% thermal power.
0700 Commenced PCIOMR from 96% thermal power.,
1030 Reactor thermal power at 98%, maximum flow.
2330 Commenced reducing thermal power for shutdown for maintenance, on MSIV's and drywell equipment, drain sum'p pump.
2/07/81 0051, Reactor Scram (manual) No. 92 from 38% thermal jpower for maintenance on MSIV's and drywell '-equip-ment drain sump pump.,
2/08/81 Maintenance complete on MSIV's and drywell equip-0815'829 ment drain sump pump, commenced rod withdrawal for
,startup.
- Reactor Critical No. 104.
2/09/81 2230'Rolled 0320 0359 T/G.,
Synchronized generator, commenced power asqepsiqn.,
Commenced PCIOMR from 70% 'thermal power<
2/10/81 0815 Reactor thermal power at 84%, holding for computer, outage.
1125 Computer back in service, commenced power ascension.
1330 Commenced E?CIOMR from 89% thermal powerl.
2/11/81 0630 Reactor thermal power at 98%, maximum flow, rod limited.
0955 Received spurious 1/2 scram, commenced reducing thermal power.
1800 Reactor thermal power at 97% due to 1/2 scram.
2029 Commenced power ascension from 97% thermal power.
4 2/12/81 0700 Reactor thermal power at 99%, maximum flow, rod limited.
2/15/81 0010 Commenced reducing thermal power to 87% for turbine control valve tests ans SI's.
0120 Turbine control valve tests and SI's complete, commenced power ascension.
0200 Commenced )PCIOMR from 97% thermal power.
0600 Reactor thermal power at 99%>> maximum flow, rod limited.
1017 Commenced reducing thermal power for RTI-'2 (Refueling Test,Instruction Pr;essure Regulator) .,
-1035 Reactor theaml power. at 95%>> RTI-22 irr progress. ~
15 Si nificant 0 erational Events Unit 3 Date Time Event 2/15/81 1300 RTI-22 complete, commenced power ascension.
1500 Reactor thermal power at 99%, maximum flow, rod limited.
2/16/81 1230 Reduced reactor thermal power to 71% due to loss of "D" main steam line flow indication.
1240 Commenced power ascension form'1% thermal power.
1330 Holding reactor power at 94% while performing main-tenance on "D" main steam line.
1435 Maintenance complete on "D" main steam line flow indicator, (square root converter changed out),
commenced power ascension.
1445 Commenced PCIOMR from 97% thermal power.
1730 Reactor thermal power at 99%, maximum flow, rod limited.
2/20/81 2340 Reduced thermal power to 87% for turbine control valve tests and SI's.
2/23.'/81 0001 Turbine control valve tests and SI's complete, com-menced power ascension.
0230 Commenced PCIOMR from 98% thermal power.
0430 Reactor thermal power at 99%, maximum flow, rod limited.
2/23/81 2100 Commenced reducing thermal power for shutdown to remove 3A transformer from service.
2201 Reactor Scram (manual) No. 93 from 39% thermal power to remove 3A 'transformer from service for maintenance (there was a buildup of combustible gases in this transformer).
2/26/81 0746 Commenced rod withdrawal for startup.
0920 Reactor Critical No. 105.
1310 Rolled T/G.
1404 Synchronized generator, commenced power ascension.
2/27/81 0130 Commenced PCIOMR from 75% thermal power.
2231 Reactor thermal power at 88%, maximum flow, rod limited.
2/28/81 2043 Reduced thermal power to 64% for control rod pattern adjustment.
2400 Reactor thermal power at 64%, control rod pattern adjust ent in progress.
(1) Personnel Error
"(2) Equipment Malfunction
0 16 AVERAGE DAlLYUNIT POWER LEVEL DOCKET iVO.
Browns Ferry 1 DATE 3-1-81 COiIPLETED GY TELEPHONE 205-729-6846 MONTH Febru<<y DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAlLYPOWER LEVEL (MWe-Net) (i>1We.>Net) 886 17 1004 2
986 1057 1003 20 1058 1030 21 49 1059 22 616
'>3 925 1039 24 1056 25 1055 1063'029 10 26 27 1054 1048'9 12 1058 2S 1044 13 1045 99 685 30 976 31 l6 liNSTRUCTIONS On this tortnat.!ist the average daily unit pi>wer Ie<<l tn lltVe Net t>>r each day iti the rep>>rrinc ini>nth. Ci>inpute to the nearest ivh>>le me aivat t.
Ii>I 7 71
AVERAGE lpAILY UNIT POWER L'EVEL'OCKET iVO UNIT DATE C<PiIPLETED IIY Teci Thorn TELEPHONE
<<$ 10<NTHFehlzUezv AVERAGE DAIL'YPOWER LEVEL DAY AVERAGE DAlLYPOWER LEVEL (MWe-iVet), thIWe-<Vet) 805 1060
<<'AY 7 17 IS 1072 1019 19 DQZ2-1025 ,20 1075 1063 1066 21
'22 1074 1046'050
'23.
1081 1054 '4 1078 1I050 25 59 10 lI059 76 5I05 lI046 9,50
~ ~
27 1I036 543 12 2S 1I035 '79 13 14 1I016 30 IS 1036 31 16 1040 liVSTRUCTIONS On this t'onnat.!ist the uvera<,e <Icily unit p<iwer lesel iri ~I<<Ye.<Vet for <<.aeh'<Iay in th>> report tn.i rni<nth. Ciitnp<ite to the nearest <whole rnc .<ivutt.
l<II g7)
18 AVERAGE DAILY'UNITPp'WER LEVEL DpCKET iVp 50-296 Browns Perry 3 3-1-81 COMPLETED IIY Ted Theta TELEPHONE 205-729-6846 iIOVTH February DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL
(~iI We-iVet) (MWe iVet I I 8 8 17 ao75 996 18 390 19 1077 632 20 1079
'74
'5 21 1072 1044 '22 1069
'23 975
-13 523 25 10 905 180 26 1049 884 27 1067 900 28 1075 13 a9 ao74 30 15 1062 31.
16 1062 INSTRUCTIOVS On tl>>s rbrrnat.!ist the avcrayc daily unit pi>iver level iii ~I'tVe iVct ter each dai',<<t th<<rcpnrttnc tnnnth. Cutnputc to 1
the nearest wlnilc m<<vivat t.
Ii)1771
.1'9 OPERATII4IG DATA REPOR1I'OCKET iVO.
DATE 3-1-81 CO<<IPL'ETED B'Y .Zgd T~onl ~
TELEPHONE .~~2~-%846 OPERATING STATUS
- l. Unit Name: Browns Ferry 1 .Notes,
'2. Reporting Period: February HFE
- 3. Licensed Thermal Piower (MfVt):
- 4. Nameplate Rating (Gro<s iaaf'IVe):
- 5. Design'Electrical Rating (Net <lf'lVe): 1065
- 6. hfaximu'm Deoendable Capacity (Gross 33ffVe):
- 7. Xfaximum Dependable Capacity (Net'ibfWe): 1065
- 82~1fiChan's;Occur,in
- Capdcity.'Ratings3(Items Numb3er:3 Througlhi73).Since,Last:Report.,Give<Reason<s:
-NA
- 9. Power Level To Which Restricted;If Any (I'Iet INWe):
- 10. Reasons For Restrictioris; If Any: I ~
This I3<fonth Yr.-t3o-Date Cttmulativ!e I. Hours In Reporting Perllod 672' 1416 57,698
- 12. 13Iumber Of Hours Reactor Vas Critical 655.58 1,399.58 36, 20M1M ~
>,.IT3~~
1!
- 13. Reactor Reserve Shutdown Hours. Z 292
- 14. Hours Generator On. Line 651. 95, 1.395. 95 35,,38,8. 77,
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (bf WH) 2 011,925 4,303.284. 97,. 59'5, 645
.17. Gross Electrical Energy Generated {31IWH) 664.:320 1440,110 32,203,1600
- 18. Net Electrical. Energy Generated (i~f WH) 649,'770, 1,406,541 31,270935o 19 Unit Service Factor 61,.3 .
,20. IJnit Availability Faictor 97.0 . '98.6 ,61,.3 I. Unit Capacity Factor I Using hlf)C Nct) 90. 7 93.3 50,. 9,
- 22. Unit Capacity Factor (Using DER Net) 90. 7 93.3 50,9
- 23. Unit Forced 0'utage Rate 3.0 1.' o. 9
- 24. Shutdowns Scheduled Over Ne3tt 6 Months I Type. Dati.. and D'urat'ion of Each'I:
Refuel ng April, 1981
.25. If Shut Ooiin At End-Of Report Periodl. Estiinated Date i)f Startup:
- 6. Units ln Test Status IPrior ro Cominercial Operation): 'ore'cast'chieved 31<it ITIA L<CRI'TIC'ALIT>Y INITIAL ELECTRICITY
'CO!31.'<IERCIAL OPEIRA1I ION
20 OPERATING DATA REPORT DOCKET lI'O.
50-260 DATE COMPLETED BY TELFPHONE ~~6846 OPERATING STATUS I Unit game Bro~s Ferry 2 Notes e ruary
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross LIIWe)::
aas2
- 5. Design Electrical Rating (Net INIWe):.
aos incumber
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. ilaxtmum D e p endable Ca P acit y(Net MWe: )
- 8. IfChanges Occur in Capacity Ratings (Items 3 Through 7) Since Last Report. Give Reasons:
.i%A NA
- 9. Power Level To which Restricted, If Any (Net IIIWe):
- 10. Reasons For Restrictions. If Any:
This hlonth Yr.-to.Date Cumulative
- 11. Hours In Reporting Period 672 1416 52 609
- 12. Number Of Hours Reactor Was Critical 664.61 1,391.78 32,135.39 13.. Reactor Reserve Shutdown Hours 7.39 24.22 12,477.70
- 14. Hours Generator On-Line 1.351.24 31,092.20 I'5. Unit'Reserve Shutdown Ilours 0 0 0
- 16. Gross Thermal Energy Generated (i~1IVH) 1,984,906 4,140,476 .. 97.711,119
- 17. Gross Electrical Energy Generated (IIIWH) 663,200 1,391,690 29,128,878
- 18. 'Bet Electrical Ener y Generated (MWH) 646.806 . 1 358.256 28.308.563
- 19. Unit Service Factor 94.9 95.4 59.1
- 0. Unit Avaiiability Factor 94.9 95.4 s9.a
- 21. 'Unit Capacity Factor (Using MDC Net) 90.4 90.1 50.5
- 22. Unit Capacity Factor (UEing DER Net) 90.4 90.1 50.5
- 23. Unit'Forced Outa e Rate 5.1 -4.6 31.9
- 4. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Eachl:
'Lfatwt>Pi BB . C O o
- 25. If Shut Uuwn At End Of Report Period. EBtimated Date uf Startup: I Eo-
- 6. Uniti ln Test Status {Prior to Commercial Operation): Forecast Achieved lNITIAL CRITlCA LITY IIBITIAL ELECTRICITY COiOIERCIAL OPERATION
OIPER ATING DATA,REPOR'T DOC)'ETNO. -50 296 DATE 3-1-81 Oi(PLETED SY ~~J2233..
I TEL EPHONE 20> "':68 OPERATING STATUS
- 1. Unit Nan>e: , 33rovn.: -Perr~-. 3 Notes
- 3. Licensed Thermal Power'(i1Wt): 3293
- 4. nameplate'Rating (Cross iiPVe):
DXG'> .
- 5. Design Electrical Ratirii! (Net M,We):
- 6. ilaximum Dependable >Capacity (Gross >i(We): :L098. 4' 7.,Max>mum Dependable ICapac>ty (Net >MWe): 06
.~8;.~lf)Changes'Occur>in>Capacity! Ratings (lltemis Number:3>>Th>'oug'h 7ijl'Sin'ce,'Last:Report.. Give'Reasons:
NA
- 9. Power Level To )Vhich '.Restricted, I'f Any (INet MWe):
IO..Reasons For Restrictio>ts;If Any:
This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 672 '1, 41'6 '5;7, 698
- 12. Number Of Huun Reactor Was Critical ~
558. f) 3, 916.43 '26,887., 70
- 13. Reactor Reserve Shutdown Hours 113.17 113.17 1,940;14
- 14. Hours Gener'ator On. Line 540.1 860.97 26,250,,97
- 15. Unit Reserve Shutdnwn Ilours 0 0
- 16. Gross Thermal Energy Generated (M)VH) ~1.61 .542 2,281,,603. 0'6,6'46'629 544,610 767,230 24,306,250 17 19.
Gross Electrical Energy Cenerated Unit Service Factor (MWH)'S.,Net Electrical Ene'rgy Gene!rated (>ilWH) 529,
- 80. 4 j90..., >,'43; 09,3
- 60. 8
- 20. Unit AvaiLability.Factnir 80.4 60'8 I. Unit Ca(iacity Factor (Usin >MDC Net) 65.8,
- 22. Unit Capaiity Factor (Using DER Nct) 74,. 01 :65.8, 23'. Unit Forced Out;ige'Rate 19.6 13.3 9,9
- 24. Shutdowns Scheduled Over Next 6 >il>>>>ths (Type. Date. arid Duration <>f Eachl:
, 25.. If Shut Di>wn At End Of Rep>>rt Perioill. Estimated Date uf Star!up:
- 6. 'niti I>> Test Status (Prii>r t'o Cum>nercial Operhti>>n t: ' '
'>>re'ca'~t A>.'hie ved
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DOCKET NO.
I UltITSl IUTDO'lUNS AND POWER RE DUCTIONS Brogans Ferr - 1 COMPLETI:D BY I
I
)>> )
) '. I REPORT MONTII Liccnscc i c Cause A ( orrcclivc l)atc Fvcnl 4l
~ << 'nV 0 Acl)ol) to Report ~
)
Prevent Rcc<<rrcoce p3
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165 2-1-81 Iligh river hT 166 2-7-81 Control rod pattern adjustment 167 2-7-81 Turbine control valve tests and SI's 168 2-13-81 "Bo recirculation HG set brush re-placement 169 2-2$ -.81 20.05 Reactor scram to place unit on 1B main transformer I
F: F<<)ced Reason: Method: Exhibit G - Inst roclions S: S.hcd<<lcd A E) luipment Failure (Explain) I-hfanual fof Prep)Ital)oo ol Data II hlaiotcimnce oi Test 2.Manual Scram. L)llr)'i)citslof I.)ccoscc C.Refueling 3-Auloolalic Scram.' Event 'Rcport (I.I)RI File (NUREG.
, I) Reg<<latory Restriction Other (Explaut) 0161)
I'. Ope)ator Trainiog 8: Liccnsc Examination
~ I"Adolioistrative
' Operational L'rror (Explain) Exhibit I - Saute Source (It/77) II Other (Explain I I
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DOCVET NO.
UNIT SIIUTI)OWNS AND POWER REDUCTIONS I
Itrowns Feri. - 3 February (.'Oh(PLL'Tl:I) It/
REPORT hlON'flI fl I.f.'PIIONf .205-729-'6846
~ r A<<J CJ~
c0 IA
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J Llecnscc 4l 4l Cause A Corrective No. Ihte CC Evert I 'n Action lr>
Vl Rcport > cn Cr O F ~ Prcvertt Recurrence
~C 58 2-1-81 D lligh river AT 59 2-3-81 16.72 During performance of SI 4.2.A-3, two leads shorted which. caused a sudden increase in recirculation flow
( ersonnel error 60 2-7-81 S 51.13 Maintenance o'n MSIV's and drywell e ui ment drain sum jr ~ 61 2-16-81 Loss of oDo main steam line flow indication 62 2-23-81 S 64. 05 Maintenance on 3A transformer start-
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up delayed as a result of cooling problems on HPCI MG sets g
I .~
sr F: Forced Reasoll: hlethod: Exhrbrt G - Instruct tons S: S;Ii'L.l<<lcrl A.(xluipmcnt Fai(ure (Explain). I-hlanu'al for Prctsaratron i)t DJta s
ll hlaintenance or Test 2 hlanual Scram. Fntry Slteels lor Lieerrsee
( Refoelutg 3-Autotnatic Scram.' Event Report (I.ill()I'ile INUREG-I) ltceplJlory Restriction', Otltcr (Lxplain) OIOI)
I ()pcrator TrainInhk, IJI:ense Examination I'.Arlrrdrristrative 5 G Opqratio>>al I:rror (lixqlain) Exltibit I Sante Source
~
(9177) II ()tlter (lixplai>>)
~ I
'I II
Ih l
BRO',i'HS FERRY NUCLEAl'LANT UNIT 1 ELECTRICAL HAIHTENANCE SUl'MRY Etiect on 'a e Action Taken Date System CcllIPOnent Nature of Operation of Cause of Results of To Preclude l la intenance Thc Reactor Nalfunction Malfunction R'currence 2/7/81 Control I!and Switch lland switch Hone Broken stop on Required care to be Replaced broken Rod Drive 85-48 repair lls 85-48 taken while operat- switch stop, switch ing switch to avoid operated properly rotating switch TR//188904 passed desired setting.
2/10/81 Control LA-85-085A Annunciator 'None Loose annuncia- Annunciator alarm Inspected and tight-Rod Drive alarm inoper- tor card. inoperabl'e. ened card, alarm able operated properly.
TR//203458 2/13/81 RCIC Relay 13A>>K43 Relay was None, the relay Broken coil Although relay was Replaced relay, found to have was operable, retainer. operable, corrective relay operated a broken coil action was required. properly.
retainer. TRII129355 2/15/81 Standby "1A" SLC Pump "1A" SLC pump None-repairs Suction line Suction line heater Replaced transfor-Liquid suction line were made befor heater trans- inoperable. mer, heaters operat-Control heater inop- temperature former bad. ed properly.
erable dropped below TR8203546 Tech Spec limit.
2/20/81 Annunica- Annunciator Annunciator. None Bad inverter. Annunciator Panels Replaced inverter, tor SysteI Panels on Panels on inoperative annunciator panels Panel 9-5 Panel 9-5 in- operated properly.
I operative. February 21, 1981, the inverter malfune.
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tioned causing a ground in the ann.
circuitry, the new inverter was replac-ed, ground cleared.
No further problems occurred. TR8203520 TR8204911
BRO!'HS FERRY NUCLEAR PLANT UNIT 1 ELECTRICAL ffAINTEHANCE SALARY For the !fonth of February 19 81 E rect on Sa e Action Taken Date System Component Nature of Operation of Cause Results of To Preclude tlaintenance The Reactor of'"falfunction Na 1 func t ion Recu".'rence 2/24/81 ~ R4'H .Fuse failure Fuse failure None Bad relay co'il. Received a false Replaced relay alarm on Pan alarm would fuse failure alarm. failure alarm.
"KKB'use 9-28 not clear, onerat ed" pronerlv.
TR8203498
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l t I BRO lVS FI'lRRY NUCLEAl'LANT,UNIT . 3 ELECTRICAL 'MAINTENANCE Sly! IARY ET!'ect on Sa e -Action Tat.es Results of lt Nature of Operation of. Cause:of To-Preclude Date. System Component
'.laintenance The Rc".ctor .'fn 1 func t ion', ~
Naif unc t ion R currence, It 2/2/81 i Rllll 3D RllR Ptttnp During the RllR heat ex-. The 4kV pump 3D Rl!R pump inoper- ,Changed- out I I norformanCe rltantTer 3R breaker rinnod nh1o t the the.'breaker,=
pump
'perated properly.
nut'f of SI4.5.8.16 service. free on -a close 3D RllR,pump signal, due to a'. TR920tt297 woULd not loose, trip link TRtI'190611'ERI/RPRO dtdVIl ~
QLllL ddd
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t) l ~ 5n 296/81 2/3/il Diesel 3C D'/G 3C D/G failed None No'thing was 3C .D/G, in'operable. Replaced 'the-'bad.
l l
Generator to trip from which woul 'ound relays,, completed
'll 2
Remvt.t tt.Jp IlaVe pl.evellt Jve dUJYUJJJallvc .l.nnt LcdLR during sur- -the diesel from 'iese1 generator veillance starting. Tlie'CR operated'- properly.
testing. and'TL01'elays TR8204281 i9 n 7 c a mR'Jt ltould not roi torl were'isrovorod ba'tj ., LER8BFRO-50-296/8109
-during investi-
'gation.
1 (
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'tl I Nt VL 1
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LVl~ ftnlt
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'\vv vtLvvn tn VVllLV nt 18 llVL RttM
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innndvdhl JllVQ% LVVJld
~
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~ l hl V nr VVlIr mnni tn ~~
R .RRM innnorab1 o Rinlar od tho bad.
Monitorinl , Monitor "B." return RBM 'switch was bad. , switch, rod: block I
"B" to servic monitor '-'B",operat-while it was ;,ed properlytl Jl Uytladd
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'RIl'7')1LA1 N tL status.
'l 2/6/81 9 t Diesel 3A D/G Receivdd a Hone Annunciator Received a false Tightened .car'd, Gci'iT raiors Aiiniiiicis to l. false over c Jrcuitry card alarm on 'pailel 9 23' alarm.- cleared Piincl speed alarm was loose 'in rRI/221316 on panel 9 annunciator panel.
1
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BROWNS FERRY NUCLEAR PLANT UNIT Common I
CSSC E UIPtiENT MECliANICAL MAINTENANCE SU>QIfARY a
EFFECT ON SAFE ACTION TAKEN COMPONENT NATURE OF ', OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE DATE SYSTEM 'I MAINTENANCE TilE REACTOR MALFUNCTION MALFUNCTION RECURRENCE
i HAIHTEHAHCE THE REACTOR HALFUNCTION, HALFUNCTION i
oil in tubes Unknown Cleaned cooler and 2/12/81 Controi 18 chiller Clean Hone Hud replaced heads Bay NVAC cooler TR 190880 Ii, relief 1-84-503 Leak None Faulty valve Leakage Installed new 2/27 CRD vs J.ve TR. 182505'
SROHNS FERRY NUCLEAR PLANT UNIT 2 CSSC E VIP 5KQiANICAL HAINTENANCE
SUMMARY
For the Month of February ]981 EFFECT ON SAFE ACTION TAKEN COHPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE SYSTEH MAINTENANCE TllE REACTOR MALFUNCTION MALFUNCTION RECURRENCE
~ /14 CRD CRD 42-31 Air leak None 0-ring worn Air leak Replaced 4 o-ring
<<<<l inside coil TR 221186
'g/20 '" CRD Pump D Leak None Loose pressure Pump leak Tighten regulator cap re ulator ca TR 103789
< <<;,g 25 -,-.-. CRD 2-85-229 Leakage None Horn valve stem Stem packing leak Replaced stay val i<< ~ D-stem packing TR 188939 V
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BROHNS PERRY NUCLEAR PLANT UNIT .
hlAINTENANCE SUlMARY'1-- 3'EQh8+Ah EFFECT ON AC TION TAKEN OPERATION OF SAPE'ATURE CAUSE OP RESULTS OF TO'RECLUDE.
DATE SYSTEM COMPONENT OF ls MAINTENANCE TllE REACTOR- MALFUNCTION .. MALFUNCTION RECURRENCE 2/1/81 Control Control Bay Hater found . None. Plug'ame out of Unknown- 'Plugged: tube and Bay liest Chillers in freon tube .cleaiied; Or w s
~
s~ s I sa'v sa hn Fika1 s nvs.
~ s vav TR 199142 2/3 D/G 3C D/G oil. Frozen float None Float stuck Inoperable , Removed: plate and frees I level switch, 'loat float. 'rK- tuff//ff 2/5 nvIInv nis ln On I v J'v tthl na.sx1 nvs.~v vaust
~ 0+v ssIJsas ss ussrsssnssss M a a sw s s wa wl a ~
Rl ntw I tjn sides of 40 rpm start'ing- system TR 2 19 224.
2 7 Hain 3-FCV-1-51 "D" Leakage None Blown'iston s'sa) Leaking air through .Changed 4-way valve-WD 1 A '0 '1 1 .1 Stc alia 4vJ/a@ 'aw 2/8 SeI Onilarv DrvWI 1 1 ner- Insnect door. None Unknown Unknown '-:
Cle'a'ned sealing. surface
~ I. Conta ir>me t sonnel access gaskets TR:190893 door Oil level
'orre l2 17 Hain None OK s TR .103183.
3-FCV-1-38
.3-FCV-1-52 a n ~ow set None Unkonwn Unknown Added lo oz ~, oil Ap MSIV anrl timed B'nd MlSIV-3-~7- Cs MSIV 3-1-51 TR .221315 2/ll High Pres 3-73-3 Leakage None Loose pa'cking nu Small leak on
-pacKing-
'Tightened packing TR 199026 sure Cool an t In ec Residual 3-74-73. Leakage None Loose packing Packing gland Ti'ghten packing nuts Heat R mox al nuts leakin TR 199027 2/26 Fire 3B fuelpool Leakage Loose plug Pump leaking ;Tighten plug Protectior coolin um TP, 19'9149 2/26 D/G D/G 3D Oil level too Unknown Drained..oil to-.pioper'ropei high I)" . . TR: 219230.
/26 Oil level too None ,Unknown Unknown Drainea oil to I
D/G filters'one 'R:219230 proper'evel 2/24 D/G 3C air bank 1 Clean None Unknown Unknown Cleaned, & replaced'. ai"r-yalve.
rn 91O99O, i ~,.- ~
t !
BRONNR FERRY NUCLEAR FIANT UNLT~3Ceneinued)
CSSC I UIPHENT HEClfANICAL MAINTENANCE SUM1ARY I I IFor the Honth of February 19 81 EFFECT ON SAFE ACTION TAKEN SYSTI.'H COl 1 PONENT -NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE RATE HAINTENANCE, TflE REACTOR lfALFUNCTION lfALFUNCTION RECURRENCE f/25 Fire 8 Fire Pump 'Bro'ken pin None Sheared pin at . Unknown Replaced pin Protectio> top of strainer TR 204863 1
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BRUUNB PURRY NUULUBR PIANT UNIT lt INSTRl&fENT MAINTENANCE SUlflfARY SSC E UIPfll'. FOg gfE HONTll OF February, j9 81 NATURE EFFECT OH'AFE CAUSE'F ACTION TAKEN SYSTEM COIifPOHEHT OF OPERATION OF OF TO PRECLUDE 1fAIHTENANCE TllE REACTOR MALFUNCTION'ESULTS MALFUNCTION RECURRENCE.
IJnit l L n "UL IIVIL nVVIllitaLQ Rfnnn 2-~ reeawarer r ri-46-48 Calibrate None T JIISIL RUIIIUIII IPLI I.I
~
f LOW nZW IJJU RI ll Vtl&
Cnntrn1 2-15 RHR Service PT-23-11'alibrate None Transmitter Froze Indicator Did-Not None Water Agree with RedUndanlt J-Tntlit ntnr 1
Unit 2 PnvA Qnv a7 wL% PilL Alt PT 75 21 Dnnn6
~ t%
v rQLL Ri Ann l1Vlll Mni at.ttvn in
~ lVAVLQ Al Vvana L Lv Tndinat ed Plow fJi th None mitter Pumps Off pt Uni.t B 2v3 Containment PIC-76-.94 Clean None Hoist'ure and Im- Co'uld Have Caused Le'ak in -Drywell Inerting purities in Flow Problems Even- 'epaired Rotometer tually Core Spray FT-75-21 Calibtate None Instrument Drift Indicated Flow With None PH-75-21 Pumps Off jt,:.
n- JL1 T 0 . 4 .. IY 1C T Rln 'n 2-5'I Hain Steam PS-1-72 Calibrate None IOSSJ.DJ.U ItUVUU apus.XVUV II4XL LnO= It VI
' Sensing Line lations GLED Clamp I'oiie 2-l6 Feedwater Replace None Faulty Flow Modi- Loss of 'Plow Indlca-Contro) fier t1 on I-16 RllR Service PI-23-93 Replace None . Sensing Line Gage Indicated Full None
'f ~
. Water Proze Scale r
R 2-17 Primary 'I'H-64-62 Calibrate None Instrument Drift Indicators Did Not None t':
2-,2)
Containment Primary TI-64-62 TR-80-1 Repair None I'U1L
'V ~
J.I 7 0LPUL VV Agree 61 1 UIJ 1 n6 VII 4 ~
~ Is T A4 nt'n ltltti.l Mnn nVLBn Motor Same Temperature.
37 OUTAGE
SUMMARY
February 1981 Preparations are in progress for the Unit 1 end-of-cycle 4 refueling outage and the Unit 2 short outage both of which are scheduled to begin in April.
The Unit 1 outage includes extensive torus modifications and internal reactor vessel work. Preliminary installations are underway for the Unit 2 station'ervice transformer, permanent connections to the main generator busses and 4kV boards will be made during the upcoming Unit 2 short outage. The major emphasis of outage preparation and other ongoing work includes:
- 1. Preparation for piping tie-ins to the two recently constructed condensate storage tanks are underway. Sandblasting is in pro-
-2.
gress on the tanks in preparation for coating.
-Fire- protection system installation at the pump intake structure.-
- 3. Refuel Floor
- a. Tool and equipment checkout and refurbishment.
- b. Removal of existing fuel racks in the Unit 1 spent fuel storage pool for replacement with high density fuel storage system modules.
- c. Repairs to the reactor building overhead crane cable cat-track.
- d. Receipt of new fuel.
~ f 1