ML20032D764
| ML20032D764 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/10/1981 |
| From: | Jones G TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20032D758 | List: |
| References | |
| NUDOCS 8111170459 | |
| Download: ML20032D764 (39) | |
Text
r TENNESSEE VALLEY AUTIIORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PL\\NT MONTHLY OPERATING REPORT October 1, 1981 - October 31, 1981 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
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Submitted By:
w Plar.
bpcrintendent- ----- --
glho O
R
TABLE OF CONTENTS 1
Operations Su::raary.
Refueling Information 3
Significant Operational Events.
5 15 Average Daily Unit Power Level.
Operating Data Reports..
18 Unit Shutdowns and Power Reductions.
21 Plant Maintenance 26 Outage Su= nary.
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1 Operations Summarv October 1981 The following summary describes the significant operations activities during the reporting period.
In support of this summary, a chronological log of significant events is included in this report.
There were 28 reportable occurrences and four revisions to previous reportable occurrences reported to the NRC during the month of October, s
Unit 1 There were four scrams on the unit during the month. On October 1, the reactor scrammed after receiving a MSIV's not fully open signal caused by main steam line low header pressure due to the opening of additional BPV'sforur$knownreasons. The reactor scrammed on October 3 when the turbine tripped on low condenser vacuum which was caused by an inleakage of air to a high pressure heater during an attempt to drain the heater for leak checking.
On October 5, the reactor scrammed from low reacter water level when a short cycle valve opened due to installation error and caused a condensate booster pump and a reactor feedwater pump to trip resulting in a partial loss of feedwater flow. The reactor was manually scrammed on October 12 in order to remove a loose weld backing plate which was used to align a horizontal weld on the "A" phase bus duct valves. The backing plate was apparently left in by mistake.
Unit 2 There were no scrams on the uni t during the month.
Unit 3 There was one scram on the unit during the month. On October 30, the reactor was manually scrammed to begin the unit's EOC-4 refueling outage.
- 5
2 Operations Summary (Continued)
October 1981 Fatigue Usage Evaluation The cumulative usage factors for the reactor v4ssel are as follows:
Location Usage Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00521 0.00422 0.00362 Feedwater nozzle 0.24937 0.18080 0.14108 Closure studs 0.20492 0.14260 0.10682 NOTE:
This accumulated monthly information satisfies technical specification section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 6.41E+05 gallons of waste liquid were disc'narged containing approxinntely 5.63E-01 curies of activities.
i l
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3 Cperations Summary (Continued)
October 1981 Refueling Information Utd d Unit 1 is Scheduled for its fifth refueling beginning on or about March 1, 1983, with a scheduled restart date of June 6, 1983.' This refueling will involve loading 8 X 8R (retrofit) fue,1 assemblies into the. core, finishing the torus modifications, turbine inspection, and' finishing TMI-2 modifi-cations. Unit 1 ended its EOC-4 refueling outage when it was synchronized to the system October 1, 1981.
There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool-presently contains 260 EOC-4 fuel assemblies,-232 EOC-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 168 EOC-1 fuel assemblies.
Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 1200 locations.
Uait 2 Unit 2 is scheduled frr its fourth refueling beginning on or about August _
1, 1982, with a scheduled restart date of December 30, 1982. This refueling outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, MG set installation for LPC1 modification,
[
and loading additional 8 X 8 fuel assemblies into the cere.
There are 764 fuel assemblies in the-reactor vessel.
At the end of the
. orth there were 352 EOC-3 fuel assemblics,-156 EOC-2 fuel assembliesi and-- - --
132 EOC-1 fuel assemblies in the spent storage pool. The present available atorage capucity 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 R
4 Operations Summary (Continued)
October 1981 Refueling Information Unit 2 (Continued) capability in the pool. However, 949 new high density storage locations have been installed and can be used after they are qualified.
Unit 3 Unit 3 began its fourth refueling on October 30, with a scheduled restart date of March 7, 1982. This refueling involves loading additional 8 X 8 R (retrofit) assemblies into the core, relief valve modification, turbine in-spection, generator breaker and unit station transformer tie-in, and torus modifications.
There are 764 fuel assemblies presently in the reactor vessel. There are 124 EOC-3 fuel assemblies, 144 EOC-2 fuel assenblies, 208 EOC-1 fuel assemblies, and 288 new fuel assemblies in the spent fuel storage pool. The present avail-able capacity of the spent fuel pool is 985 locations.
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Significant Operational Events Unit 1 Date Tirne Event 10/01/81 0017 Rolled T/C.
0316 Synchronized generator, conenenced power ascens!on.
0616 Reactor thermal pouer at l9%, holding for turbine overspeed trip test.
0622 Turbine overspeed tr1Qest complete.
0625 Reactor Scram No. 142 t rom 19% thermal pwer when MSIV's isolated on low presaure.
1205
,Cc=m' nce'd rod withdrawal for startup.
e 1230 Main turbine tripped - PMG burned up on EP con-trol.
1410 Reactor Critical No. 163.
1945 Reset main turbine.
10/02/81 0136 Rolled T/G.
0214 Synchronized generator, commenced power ascension.
0535 Opened ACL 214 - generator offline, reac tor :hcr=al 0556 _ _
power at 15 %..
Turbine overspeed trip test complete.
Ct,04 Synchronized generator, cora:er ced powe r c:cension.
0700 Reactor thermal power at 23':, holdin;; for startup RTI's.
2022 Commenced power ascencion f rom 23% thermal po.zer.
2130 Reactor thermal power at 28"',
hodling for startup RTI's.
10/03/31 Ou05 Comnenced power ascension from 28: thermal power.
0115 Reactor thermal power at 33;;, holding f or sc r.na testing control rods 14Wrem 38% thernal power f rom 1112 Reactor Scram No.
condenser low vacuum while attenpting to vent "L"
his;h pressure heater string into condenst r.
1622 Commenced rod withdrawal for startup.
1811 Stopped rod withdrawal CRD 14-15 will not wi t hd raw (repair in progress).
10/04/81 0322 Maintenance on CHD 14-15 complete, comnenced ruJ withdrawc'1 for startup.
~ ~ - ~
0437 Reactor Critical No. 104.
1100 Huldin:; due to instronuntation probleas en in
'.7-20 1150~ -
trobicar rexolved an "II 4~7-20.~
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1220
- iolled '1/G.
1238 Oil tripped turbine.
1248 Synchronized r,enerator, co..menced pe" r e n:: i c n.
13.'. 6 Turbine tripped due to high level in C-2
.o i n t we separator.
Reac t or t hermg1 power at 20i' 1425 Rolled T/G.
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6 Significant Operational Events Unit 1 Date Time Event 10/04/81 1439 Synchronized generator, commenced power ascension frem 28% thermal power.
2000 Reactor thermal power at 37% for scram testing control rods.
10/05/81 0700 Reactor thermal power at 35% holding tor scrar testing control rods.(2) 0816 Reactor Scram No. 144 from 35% thermal power, reactor scrammed on Icw reactor water level when FCV-2-29A (short-cycle. valve) cycled open as in-strument mechanics vere removing test gear.
This c_ sed a spike in condensate flow which cauced a trip of "C" condensate booster pump and "B""
RFUP.
10/06/81 0400 Commenced rod withdrawal for startup.
-0602 Reactor Critical No. 165.
0S10 Reset main turbine.
1050' Rolled T/G.
1246 Synchronized generator, commenced power a.scension.
1422 Reactor thermal power at 38%, holding for scram testing control rods.
1710 Scram testing.of centrol rods complete, concenced power ascension.
21-45 Reactor thermal power at 53%, holding for 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> soak.
10/07/.81 0700 Reactor thermal puwer at 50%, holding for 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> soak.
0945 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fuel soak complete, holding at 50% thercal 4
power for RTI's.
1110 Commenced power ascension f rom 50% thermal pcuer.
2100 Cormnenced PCIOMR f rom 67% thermal power (sequence "B").
5 10/08/81s0600
- Rea,ctor thermal power at 73%, holding; startup RTI's in progress.
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10/09/81 2040 Cocmienced reduc tna thermal power -for conc roi nm segiience e;d;bangg_trem "3".te.."A" 2 2143 Reactor thermal power'at 46%, liEntrol c6d'K"i U Fdc F ~
^
exchange in progress.
10/10/Si C037 Control _ rod _ sequence exchince comnleto. n wned power ascension.
N 0700 Commenced PCIOMR f rom 66% thermal power (sequence ff 11 A).
4 10/12/81 0035 Reactor thermal power at 99Z, maximum flow, rod e
limited.
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7 Significant Operational Events Unit 1 Date Time ivent 10/12/S1 1101 Commenced reducing thermal power for maintenance shutdown on generator ACB bus duct.
1203 Reactor Scram (manual) No. 145 from 40% thermal power to accommodate maintenance to generator bus duct.
10/14/81 2240 Commenced rod withdrawal for startup.
10/15/81 0102 R:cactor Critical No. 166.
0425 Stopped pulling rods due to settle bus timer malfunction.
0830 Settle bus timer repaired, commenced rod withcrawal for startup.
1301 Rolled T/G.
1326 Synchronized generator, cetaenced power ascension.
1440 Reactor thermal power at 35%, holding for turbine vibration check.
1600 --
- - Con =enced power ascenston from 35% therma 1 power.
10/16/S1 0600 Commenced PCIOMR fron 75% thermal power (sequence "A").
2113 Stopped PCIOMR for turbine vibration checks, reactor thermal power at 952.
10/17/81 0005 Commenced reducing thermal power for turbine con-trol valve tests and S1's.
0100 Reactor thermal power at 87%, holding for turbine control valve tests and Sl's.
0130 Turbine control valve tes ts and S1's con.pl e te, -
~
commenced PCIOMR (nequence "A").
1000 Reactor thern.al power at 93?f., maxinum flow, red limited.
1500 Reactor thernal power at 912, maximum flow, red limited.
10/18/81 0700 Reactor thermal power at 907, maximum flo. rcd linited.
1945 Reactor therual power'at 90%, holdin;f due to three-element ~icactor water level controller
~
being_out of service.
10/20/S1 0700 The th ree-e len en t reactor water level control'.tr has been repaired and returned to service,
- tor tl.ernal power a, 90%, holding for RII-13 a.
ii.
2030 Correnced reducir.; thermal power for cont rol rod pattern adjustnent.
70 4
8 Sienificant Operational Events Unit 1 Date Time Event 10/20/81 2130 Reactor thermal pouer at 707., control rod pattern adjustment in progress.
2255 Control rod pattern adjustment complete, co==enced power ascension.
10/21/81 0030 Co=menced PCIONR frca 75% thermal power (sequence "A").
0035 Co=menced reducing thercal power fron.76~ due to loss of C1 and C2 heaters.
0140 Reactor thermal power at 65%, hodling due to C1 and C2 heater isolation (=aintenance on steam valve 1-513).
0210 Comnenced power ascensicn fer 653 ther=.i power.
0500 Cc=menced PCIOMR f roc 79% thernal pcwer (n.;u._nce "A").
1645 Reactor thermal power at 90%, holding for "C" string high pressure heater maintenance.
10/22/81 0700 Commenced PCIOMR fron 90% thernal power (sequence "A").
Maintenance on C1 high pressure heater stcaa valve 1-513 continues.
2200 Reactor thermal power at 99%, maximum flow, rc d limited.
10/23/81 0100 Co==enced reducing thernal power due to problems with E-TIP cachine.
0600 Reactor therna] power at 963, holdine for n.: n-tenance on E-Tl? machine.
0605 "C1" high pressure heater steam valve repaired.
(
0315 Cc==enced pcuer ascension from 96% thertal peser.
1000 Reactor thermal power at 99%, naxicum fl:m, red limited.
10/24/S1 0001 Ceccenced reducing thermal power for turbine cen-l trol valve tests and SI's.
l 0100 Reactor thermal power at SSE, holding for turbine control valve tests and SI's.
0130 Turbine contro' o lvP~ test.
,a ar'.
t comenced-PGILM"-(-m penc PT_'). _- - _ _ _ _ _
0830 Reactor thermal poser at 99%, naximum f l e ':,
d 4
limited.
10/25/81 0504 Co==enced reducing ther~.,!
,_.;cr-
-J
. c e d- - ---
water control syste=) and RTI-32 (recirculat wn j
control systen).
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Reactor ther.ul power at -69Z,-hold inz-f or -M I-2 3 i
and 32.
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9 Significant Operational Events Unit 1
_D_a t e Time Event 10/25/81 1500 Reactor thermal power at 73%, holding for RT: 23.
2300 Reactor thermal power at 76%, holding for RTI 23.
10/26/81 0600 Reactor thermal power at 78%, holding due to problems with 1A, 13 and'1C RFWPs.
RTI 23 on hold.
1500 Reactor thermal power at 73%, holding for..ain-tenance on RFWP's.
10/27/S1 2015 Ell RFWP's back ig service, commenced potcer as-cension.
2050 Reactor thermal power at 92%, commenced PCIC"21 (sequence "A").
10/2S/81 0700 Reactor thermal power at 997., maximum flo.;, rod limited.
2200 Co*=enced reducing thermal power for RTI
.'3A 2235 Reactor thermal power at 74%, RTI-23A on "C" RFWP in porgress.
2335 "C" RFWP out of service for maintenance, reactor thermal power at 737_.
10/29/S1 1500 Reactor thermal power at 75%, holding fer ad-justments on "C" RFWP.
2300 Reactor thermal power at 77%, holding for ad-justments to "C" RFWP.
2345 1C RFUP in service for RTI-23A, reactor thermal pouer at 777.
10/30/81 0100 Commenced power ascension from 777 thernil power.
0230 Commenced PCIOMR from 971 thermal power (sequence "A").
0400 Reactor thermal power at 99%, maximum fit 1,
red limited.
09'40 Co=nenced reducing thermal power f rom 99 ' f or re-moval of "A" RFWP from service.
1035 Reactor thermal power at 73!:, holding for u! !n it-ments to "A" RFWP.
~~ ~
1230 "A"
RFWp _in nervice, holdin:, at 737 power.or id-justments t o "C" RE',,'P
_ _ - - - - - - - _ - - 1305 --
"G" RFWP -in se rv ic e, c om:en c ed - powe r-mn. o -4 *.- -
1615 Reactor thermal power at 77%, holdi.ng fet nl:
'3.
10/31/31 0700 Reactor therma l. ;'ower at 71%, hodling to'
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1430 RTI-23 complete, comenced power ascensi s 1920 Reactor thermal power at 7 5 7',, r,T I-3 2 in pre rt ss.
2100 RTI-32 complete, reactor ' power at 55%, co m enced power ascension.
2400 Commenced PC10MR from 85% thermal power (sequence "A").
O
10
-Significant Operational Events Unit 2 Date Time Event 10/01/81 0001 Reactor l thermal power at 99%, maximum flow, rod limited.
1 10/02/81 2333 Commenced reducing thermal power for turbine control valve tests and'SI's.
10/03/81 0001.
Reactor thermal power at 86%, holding for. turbine control valve-tests and SI's.
~
0030 Turbine control valve tests and SI's complete, commenced power ascension.
0500 F:Eactor therral power at 99%,'maxinum flos, rod linited.
10/06/81' 2300 Reactor thernal power at >992, naximea 13u9 nd' LLnited.
10/10/81 1920 Comnenced reducina thurnal pouer for contro!
i,c pattern adjustment.and scra.? tine testing.
2135 Reactor thermal power at 42%, holding for ejatrel rod pattern adjustcent and scran tlne teu in".
10/11/81 0340 Scran time testing complete, co==enced reser
..s-cension with red pattern adjustment in,rogred,.
10/12/81 0100 Commenced PCIOMR fron 7' L thertal po;;er. (sequence "B").
10/13/81 0500 Reactor thercal power at 982, naxinua fica, red limited.
0700 Reactor thermal power at 961, maxinun ficw, red limited.
1500 Reactor thermal power at 95%, maximum flow.. red limited.
2200 Co==enced reducing thermal power for cont rol red pattern adjustment.
2333 Reactor thermal power at 70%, control rod pattern adjustment in progress.
10/14/81 0030 Control rod pattern adjusteent conplete, comncnced i
PCIOMR (sequence."p'_') _. _
1830 Reactor th n d,.. e r - X ", ~.,.
1,...
t s
TI5 h,
10/17/5L 0246 Comnenced reducing tLermal pcwcr for turlhut u-valve tests and SI's.
0236 Reactor thernal :ot. r at S?%, holdina for ibc.ine
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' control valve'ti'sts'and 51'*..
0531 Turbine control valve tests and SI's cenplete, commenced power ascenstor 1630 Reactor thernal pouer at 'X, maximun flew, rod limited.
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11 Sicnificant Operational Esents Unit 2 Date Time E"ent 10/24/S1 1515 Reduced thermal pcuer to 91% thermal po..er <b.e to a heater leak.
1545 Commenced power ascension frou 91% thermal m.
r.
1630 Reactor thermal power at 99%, maximum f l( w, ro.!
limited.
231S Cotmacnced reducing thermal power for turbine con-trol valve tests and Sl's.
10/25/S1 0001 Reactor thermal pqeer at S27:, holding for turbine control valve tests and SI's.
0050 Turbine control valve tests and SI's complete, commenced pouer ascension.
0200 Commenced PCICMR from 92A thermal pouer (sequence "B').
1230 Reactor t.hermal power at 99%, maximum fits, rol limited.
10/29/81 2105 Commenced reducing thermal power to re r: eve string high presaure heaters from servict 115 Reacter thermal pcwbr at 22%, holding dut to "C" string high pressure heater isolation.
10/30/81 0730 Reactor thermal pc';er at 90J, holdim f or ' iin-tenance on "C"
- tring high pressure heater. (broken hangers on drain line Cl to Cl).
10/31/S1 1507 Commenced reducin:; thermal power to atici-op-eratin;; t equiru.ients for one full itrinp neatt rs out of service.
1545 Reactor thermal pewer at 88T,, holding fo. oper.itic requirements on feedwater heaters.
230 Cemmenced reduc in:: thermal power for een:rol rod pattern adjustment.
2255 Reacter thermal poaer at 67;., holdiny; for,;n.troi rod pattern adjustment.
2400 Reactor thermal pouer at 677, hodlin;; f or cont roi rod pattern adju;tment.
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.12' Sinnificant Operational Events Unit 3 Date Time Event l
10/01/81 0001 Reactor thermal power at 95%, maximum f1w, a::-4 coastdown.
10/03/81 0035 Commenced reducing thermal power for turbine con-trol valve tests and SI's.
0045 Reactor thermal power at 87%, holding for turitne control valve tests and SI's.
0100 Turbine control valve tests and SI's co6plete, commenced power ascension.
0200 Reactor thermal power at 95%, maximum flow, EOC-4 coastdown.
2300 Reactor thermal power at 94%,-maximum flou, ECC-4 coastdown.
10/06/81 0700 Reactor thermal power at 93%, maximum flew, EOC-4 coastdown.
10/09/81 0700 Reactor' thermal power at 92%, maximum'fleu, EGC-4 ' '~
~
coastdown.
10/12/31 0700 Reactor thermal power at 91%, maximum 11cu, ZOC-4 coastdown.
i 10/15/81.2300 Reactor thermal power at 90%. maximum flow, 20C-4 coastdown.
10/17/81 0125 Commenced reducing thermal power for turl.ine cen-valve tests and SI's.
0143 Reactor thermal power at 85%, holding for turbine control vlave tests and SI's.
0345 Turbine control valve tests and S1's comrlete.
commenced power ascension.
0500 Reactor thermal power at 90%, maximun flow, i:CC-4 coastdown.
2300 Reactor thermal power at S92, maximum flow, EOC-4 coastdown.
10/13/S1 0300 Reactor thermal power at_08%,, maximum _fIcy, D Q'.
coastdv u.
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10/24/81 0740 Reactor thermal power at 117%, maxinum fl6u', in:-4 coas td mm.
10/26/81 2300
' Reactor thermal' power 4 30 /., maxii:.uu Flid, ils-T "- ~-
~
coautdown.
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13 Significant Operational Events Unit 3 Date Time Event 10/27/81 2205 Commenced reducing thermal power for CRD testing.
2240 Reactor thermal power at 64%, holding for CLD testing.
10/2S/81 2335 CRD testing complete, commenced power ascension.
10/29/81 0200 Reactor thermal power at 92%, maxircum flow, EOC-4 coastdown.
0900 Reactor thermal pgwer.at 90%, maximum flow, EOC-4 coastdown.
1500 Reactor thermal pcuer at 89%, maximum flew, rod limited.
1700 Reactor thermal power at 88%, maximum flow, EOC-4 coastdown.
2000 Reactor thermal power at 87%, maximum flow, s0C-4 coastdown.
10/30/81 221'2 ~~ ~- - - - Commenced reducing thermal power for shutdown for EOC-4 refuel outage.
2345 Reactor Scram Manual No. 104 from 40% thermal power to accommodate EOC-4 refuel outage.
10/31/81 2400 ECC-4 refuel outage.
(1) Equipment aalfunction (2)Inntallation error 70
14 Significant Operational Events Unit 3 Date Time Event 10/27/81. 2205 Commenced reducing thernal power for CRD te.iting.
2240 Reactor thermal power at 64%, holding for CRD
~
testing.
10/2S/81 233; CRD testing complete, commenced power ascens.in.
10/29/81 0100 Reactor thermal power at 92%, maximun flow, i.uc-4 coastdown.
0900 Reactor thermal power at 902, maximum ficw, !.00- 4 coastdown.
1500 Reactor thermal power _at 89%, maximum flow, rmi limited.
1700 Reactor thermal power at 88%, naximum finw. '. 4,C-J.
coastdown.
2000 Reactor thermal power at 87%, maximum flow. ECC-4 coastdown.
. = - --
10/30/81 2212 Cemenced reducing thermal. power for shutdown for EOC-4 refuel outage.
2345 Reactor Scram Manual No. 104(Nom 40% thermal power to accommodate EOC-4 refuel outage.
~
10/31/31 2400 EOC-4 refuel outage.
(1) Equipment malfunction (2)Persennel error T
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15 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 M'IT Browns Ferry - 1
~
DATE.11-1-81 CONIPLETED BY Ted Thon s
205 729 6846 TELLPil0NE 510NTII October 1981 DAY AVERAGE DAILY POWER LEVEL DAY A\\'ER AGE DAILY P0hER LEVEL (5the-Net)
(SIWE-Net)
I 14 37 962 148 938 2
g3 127 3
39 943 105 910 4
20 5
95 21 874 161 6
22 992 558 1037 7
23 763 3
3 1043 711 833*
9 5
10 709 777 26 952 809 g,
,,s 513 1026 g3 73 771 13
-13 877 14 30 207 15 3;
733 853 16 2
^-
INSTRt*CIlONS On this format.!nt the aserage daily umt power leselin N1We Net for each dah m the reporting month. Gunpute in the nearest w hole meg.: wart.
- 0ctober 25 (25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />) CDST to CST
_ _ pi77 3 E
e.
.16 AVERAGE DAILY L* NIT POWER LEVEL DOCKET NO.
f UNIT Browns Ferry --2.
11-1-01 DATE COMPLETED 11Y _T_ed_Thom TELEPil0NE 205 729 6846 October 1981 MONTil
^
DAY AVER AGE DAILY POWER LEVEL--
DAY AVER AGE DAILY POWER I.EVEL -
-}
(MWe-Net I (MWe.Ne )
1076 1042
,7 2
1064 is 1066 1059-1066 3
39 4
1072 1069 20
~
1076
- 1069 _
_ 5_ _. _
_. __ _. _ _ _ y g_ _ _
1072 1066 6
y 7
1072 23 1068 8
1072 24 -
1071 I
1067 1035*
9 25 I
.{
984 1066 10 11 668
.27 1065 899 1059 g3 33 1000 1048
,3 29 14 971 952
~~
i to 1070 916 15 3
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10L4 16
- - ~
ins 1RUC110NS -
~ - ~ ~
~~
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On ilm format. Int the.ncrage.Ln!) unit power ledt in MWe Net f or each da) m it.e icp unn. mienth. (~.it.,,a the nearot winile mepwitt.
.. _ - ~. _ _ _. - _. - -. ~,
~~
7.'
~ '-'
I
? -- - -
i'
- 0ctober 25 (25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />) CDST to CST
,,c 7,
s t
e b
17 AVERAGE D \\lLY UNIT 8%SER LEVE'.
50-296 DOCKET NO.
UNIT 3rewns_ Ferry.- 3 DATE 11-1-81 I
COMPLETED BY Te d _Iha-'
l l
TELEPIIONE 205 729 6846 i
MONTil DAY AVERAGE DAILY POWER LEVEL'-
DAY AVER AGE D \\lLY POWER LEVEL t M b e-Net )
( Mb e-Net i 1
1007 g7 938 i
1001 18 941 3
1000 19 938 1000 20 935 j
4
(
5 997 930 I
988 923 o
983 919 7
33 979 92'+
3
,7 9
975 25 916*
10 976
'6 913 972 896 l
i,
{
967 668 12 3
i 962 940
,3 y
965 866 la w
958
-10 i3 3,
953 i,
z
.._=_==.= =-::. = = - - = = = --
,g g gggg33 On t!ns t.u:nat. !nt the.ner ege dai!) unit p. mci les el ni Mw e-Net I, r each de ai & rep.. tui; ni >n:l.. F.,
il:e i.e.n est w la.le me::i a a'i.
,^'L--.-
- 0ctober 25 (25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />) CDST to CST
'" 75 P
l
18
~
OPERATING DATA REPORT
~
' DOCKET NO.
50-259 DATE 11-1-81 CO5tPLETED BY m ch,n1 Chapman TELEPilONE 205 729 6846 OPERATING STATUS Browns Ferry - 1 Notes
- 1. Unit Name:
Odober 1981
- 2. Reporting Period:
3293
- 3. Licensed Thermal Power (31Wt):
1152
- 4. Nameplate Rating (Gross 51We):
1065 S. Design Electrical Rating (Net htWe):
1098.4 6
- 6. hiaximum Dependable Capac;:) (Gross StWe):
1065 7 hiaximum Dependable Capacity (Net 5twe):
- 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 (Net atWe)r NA NA
_.____ _10.._ Reasons For Restrictions. If_Any;__
4 This hionth Yr.-to.Da t e Cumularise 745 7,296 63,578 5
I
- 11. Ilours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 637.08 3044.23 37,850.80 98.74 116.33 5,215.20
- 13. Resetor Reserve Shutdown lic>urs
- 14. Hours Generator On-Line 592.58' 2.973.35 36.966.17
- 15. Unit Reserve Shutdown llours 0
0 0
~
- 16. Gross Thermal Energy Generated (htWil) 1,427,-186 8,852,681 102.145.042 I*
- 17. Gross Electrical Energy Generated (SIWil) 478,070 2,952,270 33,715,560-
- 18. Net Electrical Energy Generated (atWil) 462,672 2,870,521 32,734,338
. fi.,.,.
- 19. Unit Sersice Factor 79.5
-40.8 58.1 i'
~
79.5 40.8 58.1
- 20. Unit Availability Factor 58.3 36.9 48.3
- 21. Unit Capacity Factor (Using SIDC Net) 58.3 36.9 48.3
- 22. Unit Capacity Factor (U>ing DER Net) 20.0 5.4 27.9
- 23. Unit Forced Outage Rate
--.. -.24 Shutdowns Scheduled Over Next 6 htonths (Type _, Date.and Duration of Each)' - - --- - - - - - _ _. _. - - - - - - - -
m.
~
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
_.26. Units in Test Status (Prior to Commercial Operationi: -
11-Force'ast -
- - - Achicied ~ - ~ ~ ~
- ' ~
z - - ::-_ :- _:--.=. : -..
._----- -- --- =
: -- : =.- ~.:.
INITIA L CRITICALITY INITI A L ELECTRICITY
~
CO%t%IERCIAL OPER ATION
~
~
(9/77)!
~
g
19 OPERATING DATA REPORT DOCKET NO.
50-260 DATE 11-1-81 COMPLETED BY
.M.
Chapman TELEP}l0NE 9n%.774 6846 OPERATING STATUS
- 1. Unit Name:
Browns Ferry - 2 Notes October 1981
- 2. Reporting Period:
34-
- 3. Licensed Thermal Power (MWt):
1152
- 4. Nameplate Rating (Gross MWe): _
1065
- 5. Design Electrical Rating (Net MWe):
1098.4
- 6. htaximur.) Dependable Capacity (Gross MWe):
1065
- 7. Maximum Dependable Capacity (Net MWe):
S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
4 NA e
- 9. Power Level To Which Restricted.If Any(Net MWe)f NA A
- 10. Reasons For Restrictions.If Any:
This Month Yr.-to-Date Cumulative
~^
745 7,296 58,519
- 11. liours In Reporting Period 745 6,302.05 37,045.66
- 12. Number Of Ilours Reactor Was Critical
- 13. Reactor Resene Shutdown }!ours 0
965.58 13.419.06
- 14. Ilours Cencrator On-Line 745 6,054.83 35,795.79 0
0 0
- 15. Unit Reserve Shutdown !!ours
- 16. Gross Thermal Energy Generated (MWil) 2,374,466 18,645,073 102,215,721 4
i
- 17. Gross Electrical Energy Cencrated (MWil) 788,350 _,
6,200,410 33,937,598
- 18. Net Electrical Energy Generated (MWil) 767,800 6,017,303 32,967,610 100.0 83.0 61.2 -
- 19. Unit Service Factor 100.0 83.0 61.2
- 20. Unit Availability Factor 96.8 77.4 52.9
- 21. Unit Capacity Factor (U>ing MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 96.8 77.4 52.9
- 23. Unit Forced Outage Rate 0
10.8 29.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):
~
Refuel outane August 1982
'~
-^
^
- ~
=_
W-~~~'-_-
.Q
.n-Q __:4 4
- U
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
~
~
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved '-
i INITIA L CRITICALITY INITIA L ELECTRICITY COMM ERCI AL OPER ATION
~ ~ ~ - -~
~ ~ ~ - ~ ~ ~
- - --~-~ - ~ ~~ ~~~, _ _. _ _ _
(9/77)
- es =
.4-
20
$r OPERATING DATA REPORT l
DOCKET No 50-29_6 DATE 11-1-81__.
6 f6846 EL P 10 E i
OPERATING STATUS l
I Browns Ferry - 3 No!"
- 1. Unit Name:
b
- 2. Reporting Period: October 1981 3293
- 3. Licensed Thennal Power (5th ):
1152
- 4. Nameplate Rating (Gross MWe):
f
- 5. Design Electrical Rating (Net MWe):
1965_
1098.4 i
- 6. Stasimum Defendable Capacity (Gross MWe):
1065 I
- 7. Masi;num Dependable Capacity (Net 31We):
S. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Give Reasons:
NA i
- 9. Power Lnel To Which Restricted. lf any(Net MWe): "
NA
- 10. Reasons For Restrictions. If Any:
NA i
This Month Yr..to.Date Cumula n e II. Ilours in Reporting Period 745 7.296 40,944 j
- 12. Number Of Ilours Reactor Was Critical 720.75 6,495.71 32,466.98
- 13. Reactor Rewne Shutdown llours 10.50 330.64 2,141.53 i
- 14. Ilours Generatur 0n.Line 720.75 6,360.78 31,750.78
- 15. Unit Resene Shutdown llours 0
0 0
l
- 16. Gross Thermal Energy Generated (MWil) 2,106,382 19,493,592 93,858,620' _
- 17. Grow Electrical Energy Generated (Mwil) 701,320 6.459,160 30,998,190 l
- 15. Net Electrical Energy Generated (Mwil) 680,071 6,264,623 30,088,946
- 19. Unit Senice Factor 96.7 87.2 77.5 96.7 87.2 77.5
- 20. Unit Asailability Factor 85.7 80.6 69.0
- 21. Unit Capacity Factor (Using MDC Net) 85.7 80.6 69.0 Umt Capacit,s Factor (Using 1)ER Net) 22 0
7.1 9.2
- 23. Unit Forced Outage Rate 24 Shutdowns Scheduled Oser Nest 6 Months IType. Date.and Duration of Each t'_
^
g
- 25. If Shut I)own At Lnd of Report Period. Estimated Date of Startup:
.26. Units ir Test Status iPrior to Commercial Operation):
Force:nt -
A cluen.1
- -_.=.:-
INill \\ L CRI TICAll1Y INITIAL ELEClRICITY CO\\l\\ll.RCI \\ L OPI R AllON k,
L
.I 4
,'-l i
i' i'
- .. L l
,l!
l 50-259
' ~
,,i i-DOCKET NO.
UNITSilUTDOWNS AND POWER REDUCTIONS Browns Ferry - 1 i
UNIT N AM E -
DA*IE Il-1-81 COMPLETED BY _ Icd Thom October i
REPORT MONTII (El.f.Pil0NE. ?M 794 6R46._
I
- ,i it i
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u i
f
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.5 ?
3 41i Licensee
[cg
{~1, Cause & Corrective 8
No.
, Date i
r,
- E 4
EE5 Event t; '?
o>
Action to Report #
di0
!0 Prevent Recurrence I
3d:!
i!
i 4
j@
E V
e i
s' i
}q I
4 (1
173 10/01/81I!
Fi 6.08 A
3 Reactor scram when MSIV's isolated
{
on low pressure during turbine over-1 i
if I-speed trip test.
174 10/01/81.
F.
13.73 A
3 Unit remained down - EllC control sys-tem permanent magnet generator burned i
up.
t 175 10/02/81; S,
0.48 B
Generator'offline for turbine over-H I
speed trip test - no reactor scram Reactor scram from condenser low 176 10/03/81 F
6.98 A
3, i
i vacuum while attempting to vent "B" r!
'I high. pressure heater string into condenser.
e 177 10/03/81l F,
16.82 A
Unit remained down - CRD 14-15 would i
not withdraw.
178 10/0,4/81'.
F 1.63 A
Unit remained down due to instrumenta-tion prob 1' ems ort TR 47-20.
179 10/04/81 S,
0.17 B
Oil tripped turbine test.
i.
I i
i i!,
2 I
3 11 4
F: Forced '
Reason:
Method:
Exhibit G -Instructions N
S: Schedule'd 'g A Equipment Failure (Explain) 1-Manual for Preparati.m of Data l'
B-Maintenance or Test 2-Manual Scram.
. Eni y Sheets for Liernsee 3 Automatic Scram.
ihent Itepost (l.l RI File (NUREG-i(
C-Refueling p
p',
D Regulatory Restriction 4-Other ( Explain)
'0161!.
L-Operator Training & License Examination 1
F-Administrative 5
G-Operational Er ror (Explain) '
Exhibit I-Same Source (9/77)
!; p, Il Other (E xplain)
I l
J h.
a i
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~
4 DOCKET NO. 50-259 t
UNITSilUTDOWNS AND POWER REDUCTIONS
}
UNIT NAME Browns Ferry - 1 (Con't) l DATE 11-1-81 COMPLETED BY Tml Tbnm i
October TELEPilONE 205-729-6846 REPORT MONTil i~
i l
1 2
.o.?
=
n l'.
kE
? '5 d Liyensee 5't Cause & Currective I
No.
Date h*# "'
l?
d Adion to 4
d' s2 0
-5 5 *:
g US Rcport #
to V O
Prevent Recurrence O. ~~-
ce
{
d 180 1 /04/81 F
1.22 A
Turbine tripped due to high 1.evel in 0
C2 moisture separator - no reactor scram 181 10/09/81 lF 28.50 A
3 Reactor scram onlow water level due
}
l to condensate short cycle valve open-ing as test instrumentation was dis-connected.
"1C" coMensate booster l
t' w
t i'
pump tripped which caused "1B" reacto
+
d feedpump to trip.
11 Derated for, control rod sequence.
182 ;
10/09/81 lj S 6
l o
change.
l' 4
Reactor scram to accommodate mainte -
t 183 10/12/81 E
64.37 A
2
,6 nance on generator bus duct.
i I
184[
10/15/81
'II, '
9.02 A
Unit remained down due to settle bus timer malfunction.
j 11 Derated for control rod pattern ad-1 185' 10/20/81 q S' g
justment.
j 186g 10/25/81 jS,
B Derated for RTI-23 and RTI-32.
p il r I
ii MI f
3 4
]t!R ason:
Method;
- Exhibit G. Instructions i
F: Forced i
ilA Equipment Failure (Explain)
- 1. Manual for Preparation of Data S: Scheduled '
" 11 Maintenance of Test 2 Manual Scram.
Entry Sheets for 1.icensee i
!?
' C Refueling 3 Automatic Scram.
Event Report (l.ERI File (NUREG-i"
,/jD Regulatory Restriction 4.Other ( Explain) 0161) t p
i C !E Operator Training & License Examination 1
.d (-
P fF Adnunistrative l
5 i
t i
? G Operational Error (Explain)
E.shibit 1 Same Source
!s
(')/77) [p l
q
'i.11 O. ther (Explain) o F
.,4, I
i S
y ti.
p p.
- ).
- i i1 4
lI 1
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50-259 DOCKET NO.-
- I UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME Browns Ferry - 1(Con L tj DATE 11 1-R1
'i I I October COMPLETED BY Ted Thom l
REPORT MON fil TELEPilONE 205 729 (,846 lj j'
E E
5?
'h j jf 2 Licensee
,E s j
jn Cause & Corrective i
'o Date l
3 3=
4 js5 Event y
9-8 Action to No.
j' Prevent Recurrence f-5 j ;p, g Report e mt*
i H
I 6
I Derated for RTI-23A.
187 10/28/31 S
B 188 10/30/81 F
B i
Dcrated for maintenance on "A" and l
"C" reactor feedwater pump.
i 189 10/31/81 S
B i
Derated for RTI-32.,
4
'r i
g 4
i u
Li f:
i i
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=
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i
, s l
L J t
I l;
l l
t t
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t-j n
I 2l r'
3 4
F: Forced Reason:
Method:
Exhibit G -Instructions
' S: Scheduled '
- A Equipment Failure (Explain) 1-Manual for Preparation of Data Bataintenance of Test 2 Manual Scram.
Entry Sheets for Licensee.
l
['
, C-Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG.
I
- D Regulatory Restriction 4 Other (Explain) 0161) i
! E-Operator Training & License Examination li s'
I F-Administrative 5
G. Ope' ratio...it Error (Explain)
Eshibit I Same Source l
r i
(9/77)
J' il Other (E xpuin) 0 3.
I l'
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.t
UNIT SilUlpOwNS ANI) POWElt REDUCTIONS DOCKEINO. 50-260 UNil NDtt Browns Ferry - 2 DAIE.11-1-81 COMPl.F TED !!y Ted_Jhom RI:pOR I slON ill October I El.i PilONE 205.729_.6846___
='2
.; u. i e,
8
=
s2 1.icensee g -t,,
gg cause & Correctise I
=
No.
Date 5E 4
jj$
E.eni s7 57 Action to E
U 5 f =E Report =
- iu E'
Prevent Recurrence 2
v 6
.l 210 10/10/81
!S H
Derated for control rod pattern ad-l justment and scram time testing.
i 211 10/13/81 l
S H
Derated for control rod pattern I
adjustment 212 10/31/81 lS H
Derated for control rod pattern i
adjustment, s.
l I
i 1
i i
i J
I i
! l, '.i -
i
\\,
I
.i i!
l I
l'
. ] 'i l 3
4 j'. !A I quipnient Failure (Explain)
F: F6 reed R.ason:
Metheal:
Exliibit G Instruetions S' S hedufeo '
! Manual f or Picpaution of Dai.,
[3 p} Il staintenance or Test 2 Manual Scrain.
Entry Sheets l'or I.ieensee g
i p.C Refueling
- 3. Antoin.itic Strain.
laent Report ti 1:R) File iNIiRI G-ji
'[y Operator Training & l.itense F xamin.ition D Regulatory Restriction 4-Ot her (lixplani) 0161) f i'.-
i l'
i iyCF \\Jnunistrative 5
J
', ;G Operational I rror il:splai.o 1.slatut i. S nne Source ps/77 ) il 411 Ot her ( Explain) i t
i il.
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6
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~~~ -- --- -~- ~
' ~ ~ ~ ' * -
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50-296 i
UNir sitin downs AND POWLit itLI)UCI10NS i
{BrownsFerry-3 nur 11-1-81 i
i co\\tri.I: II:1> 11Y led _Ihom RI'POR I' MON ill October
,,.II.PIIO N E 20'i 721 6846_.
l l
i I
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]
9
(_iCellSee
- (
Can5C k CilIIClliVe iE 4
i E3 I:sent 3
e?
Action t.
N...
Daic i
A j$
j, Repor t E0
}'
Present Reentrence i
i i
5 l
T-92 10/27/81
.is B
Derated for control rod drive test.
93 10/30/81 E
23.25 C
2 Reactor scram to accommodate EOC-4 I
refuel outage.
l l
i l
l ra l
V3 I
i l
I p
i o
I I
t i
i i.'
u l
1 I
3 4
F: Fhrced
' 'R. asdn :
Method; I:xhibit G. Instrussions S S hedn'e.1'
{ {A 1.quipment Failure (Explain)
! -M.in ual for Preparation of Data g
j j li.\\1.iintenance or Test 2-Mannal Scra nt.
1.ntr> Sheets for 1.ieensee e C Refueling 1 Autorn.itic Strain, laent Report (l.I~Iti File iNilRI G-D Regulatory Restriction
+0t her ( E xplain )
0161)
, il :)perator Training A litense i.sainination h '
l' \\denumtrative 5
' jG Operational I tror iINplaial l'sliibit I Sanie Soince 19/77) j 11 Other ilhplain)
- i i
,i e
i-i.
m,
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-.--~-.,.,*mn=
men -
~
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' * * ^
' ' " * * * * * ^ ~ ~
't.
I
. <,l! - : }
l EROWNS FERRY NUCLEAR, PLANT UNIT 1 lt :
CSSC EQUIPME T ELECTRICAL MAINTENANCE.
SUMMARY
f0R TIIE MONTil 0F October 19 81 l' -ll ll
+
ll Action Taken Mttect on Salc lj
', Celnlponent!!ature of Operation of lCauseof
., Results of To Preclude U.- B e S ys t cc; '
ll
.,' i
!!aintenance The Reactor
' Malfunction Malfunction Recurrence l
j Coil for relay 1RM will not retract Replaced coil.;
t
+
i
- 10/2/81 Neutron;,
"F" IRM IRM will not None
.d Monitoring retract from 7 K 7K burned from core Tested OK.
u[ !
f TR #224958 II core
,l!
S XS 39-2J, Intermittent None D &ector opera-Intermittent alarm Replaced detector.
1I
.?l ting on inter-tested per SI 10/3/81 Fire llllj TR #182969 alarm mi tent basis 4.11.C.1 65.
1 Protection f
I ji l!
f f
.I '
i:
i 11 0 ' sample Motor failed None Mgtor fan came Sample return pump Replaced complete lI 4,
10/4/81 11 0 j-2 loose causing inoperable pump and motor 22 assembly.
return pump motor,. inding TR #241750; y
w 1Ali l
f ll damage j'
LER BFRO-50-259/
i ll q>'l l
8157 i
il v
I !
{;
o g
,ee j'
e CRD ll IISh5-48 Stop plate None Stop plate Spitch not operat-Replaced stop ij l 10/5/81 i-l' broken broken.
~ing properly '
plate. Switch i
I fi operated OK.
TR #224764 I
i l(
lli TR #224816 i.
I u
(
0
,t J
J pg il
!; l 1
i' t
' 10/8/81 Diesel!
D/G(1 &12A Relay would None Bad time delay Relay did not oper-Replaced and i;
ll i
Generator Rel'ay ESTD.
La time relay ate properly. Ilow-timed relay per ever, this did not SI 4.9./. 1.d.
f correctly
'effect D/G opera-TR #250779
,g j;
jj during annual bility.
I inspection l!
t '_
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~
BROWNS FERRY NUCLEAR, PLANT UNIT 1 F '
i i
t l
i
't ELECTRICAL MAINTENANCE SUmiARY CSSC EQUIPMENT' I
October 19 81
.I i
t FOR THE MONTil 0F i
a i i a i e
Action Taken r
Eftect on Saic
!!ature of Operation of Cause of
,Results of To Preclude D..e c Systce' Cc aponent
!!aintenance The Reactot-Malfunction Malfunction Recurrence i
l10/9/81 i
l HPCl Vibrat. ion Cable damaged None Damaged cable Vibration recorder Replaced cable.
recorder inoperable TR #2507t,.1 i
+
' 10/10/8 Nhapparent D/G shutdown prior Investigated but
, Die'sel j, D/C 1 & 2C D/G stopped None Generator from idle for cause found to completion of no cause deter-i.
I no apparent shutdown sequence.
mined.
reason Did not effect TR,#203612 l
j.
[
D/G operability LER BFRO-50-259/
I i
l f
,1 8161 t
u u
'l l
i 10/11/81 PCIS F
FC064 '41 Damper show-None Limit swite.h Unable to determine Adjusted limit
^
f I
ing red and out of adjust-actual damper switches. Tested s
l' green light,"
ment position by use cf OK.
w
)
indicating lights TR #227001 l
lii i
i i
!l I
s10 RBCCW [t Damper 70-65 Damper posi-None Limit switch Position indica-Adjusted limit
~
l/13/81 j
[
{i tion-not out of adjust-tion incorrect switch. Tested
.i
,')
indicating ment OK.
TR #226918
(,,
full open j
/
}
t i
i l'.
p{
l 110/16/81 11 0 H0 sample Pump and
.None Undetermined Pum'p was operable Replaced pump and 22 2g when removed from motor assembly..
3,
[
return pump motor assembly 1B l l;
noisy service TR #241486
'l*
i i
LER BFRO-50-259/
l
- i 8162
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i l,
I l
(,
3 t
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d i!
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o 3'
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~
l' BROWNS FERRY NUCLEAR PLANT UNIT ELECTRICAL MAINTENANCE SLWiARY' i
4 CSSC EQUIPMENT.
FOR Tile MONTil 0F' October 19 81 t
Effect on Satc Action Taken l
Date Systce Cce'ponent Usture of Operation of Cause of
,Results of
'To Preclude i
Itaintenance The Reactor Malfunctio'n Malfunction Recurrence
'i i
l' i[10/18/81 None Bad relay on
' Alarm would not Replaced relay.
t Diesel
D/G 1 & 2C.
D/G C running 1
Generat'or alarm will poinc card clear Tested OK not cicar l
TR #279764 jl, t
a l
.' l h
l "510/20/81 Reactor Relay Coil bad None Bad coil Relay 3A-K42 failed Replaced coil.
't Tested OK.
3A-K42 t
8 r
i Manual TR #203986
+j.
Control' i
,i System !
f Il r
I 1A) reactor I
Solenoid coil None Bad coil Damper inoperable.
Replaced coil.
'l10/22/81 Reactor,'
TR-#267611 Building building' bad' 4
l Ventila-exhaust-fan g
4 tion damper
- l i
3
- I f
j Il0/25/81 PCIS
[
Relky '16A-Bad relay None Bad. coil Fuse failure alarm Replaced coil.
(.
K40; coil I
received Tested OK.
TR #224772-i i
j l 2
i-j j i
.a
! 10/26/81 FuelPodl,-lFuelpool Bad bearing None Bearing bad Removed from ser-Replaced bearing.
s W
'l coditing pump
.vice prior to motor Checked OK.
- i C'oolingl '
,' mot lor 1A fallure' TRL#250442
. i System
~'
iI
\\
(L i
i i;l10/26/81CRD IIS 55 48 Stop broken.
None Broken stop.
Switch not opera-Replaced stop.
ting properly Tested OK
[
f f
TR #280336 i
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1 :
i BR0hrNS FERRY NUCLEAR PLANT UNIT 1 ELECTRICAL MAINTENANCE
SUMMARY
CSSC EQU'TPMENT-i 81 ctober 19 FOR Tile MONTil 0F i
i Action Taken Ettect on Safc lCauseof Results of To Preclude i
flature of Operation of i
i Itaintenance The Reactor Malfunction dalfunction Recurrence D..e e Systen~
Ce ponent l
l
.10/27/81 RPS 1B RPS MG K1 relay bad None K1 relay bad Tripped 1B RPS MG Replaced relay.
set causing s-scram Tested OK I
seti l
TR #226828 i
10/29/81 Control' 1A[ control Breaker will None W re loose on IA control bay Replaced wire.
Bay Heat-bay. chiller not close in c ose circuit of chiller inoperable Tested OK i
ing, Vent-lj norma] opera-480 volt feeder TR #250610 be'eaker i
ilation i
tion or test l
and A.C.
j System I
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f 1 & 2C Annunciator None Bad inverter Loss of annuncia-Repaired inverter.
D/G,dciator tion for D/G 162C Tested OK 10/30/81 Diesel
~
annu panel inoper-i Generator l
in control room TR #239291 l
pan'el on.
able 1
Pni,9-23-8 l
l i l 10/31/81 Annuncia-XA-55-8B and Annunciator None Bad inverter Loss'of annunciator Replaced inverter
, i panel XA-55-8B and card. Returned panels inop-I, tor 8C.
erable 8C annunciator panels i
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BROWNS FERRY NUCLEAR PLANT UNIT 2
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ELECTRICAL MAINTENANCE
SUMMARY
CSSC EQUIPMENT '
81 October i9 FOR Tile MONTH OF Action Taken Effect on Sale D.. e c S)stce Cer$p onent llature of Operation of Cause of
, Results of To Preclude l
ltaintenance The Reactor Italfunction Malfunction Recurrence
!.10/10/81 11 0 2B 11,0 Pump tripping None Undetermined Pump tripping Investigated 22 2
trouble., Adjusted sample intermittent-
- I therrnal overloads i
return pump lv problem cleared.
l TR #279841 i
LER BFRO-50-260/
815'.
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l 10 / M '81 Fire Smok'e Alarming None Detector Intermittent alarm Replaced detector t
Protec-detector intermittently alarming and tested per tion XS-39-87WD intermittently SI 4.11.C.1 & 5 TR #239286 I
TR #239287 1
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BROWNS FERRY NUCLEAR, PLANT UNIT 3
ELECTRICAL MAINTENANCE SUFDIARY i
CSSC EQUIPMENT f
I FOR Tile MONTil 0F October 19 81 i
Action Taken Etic t on Salc 0 eration of Cause of
. Ecsults of To Preclude e
f l DMc Syster~
' Component
!!ature of P
,talfunction Recurrence l
ltaintenance The Reactor blalfunction l /8/81 1
10 Diesel D/G 3E D/G started None Defective diodes Spurious start of Replaced diodes.
Generator when alarm on annunciator D/G Tested OK l
reset button rdlay TR #235980 LER BFRO-50-296/
i was reset 8158 l
l Tim le l delayTimer out of None Tfmerappears Timer out of toler-Replaced timer 10/9/81 Diesel ance and tested per I
Cenerator relay PFD1 tolerance tg be dritting l
SI 4.9.A.l.d.
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TR #235971 L
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LER BFRO-50-296/
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8162 I
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!10/11/81 flPCI HS-7$-30A lland switch None nad hand switch Unable to open Replaced switch will not open valve from control per EMI-23.
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valve room
.TR #227747
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i i l i10/12/81 RCIC FCV-71-34 Valve will not None Arc shield bind-Valve not closing Freed contactor g
close electri-in'g contactor electrically cycled valve
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I several times.
8 li cally TR #203663 i
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ij LER BFRO-50-296/
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I p) i kO/14/81 RPS 5A-K14C l Relay not None Coil smoking and Scram relay failed Replaced coil.
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TR #280267
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3 BROWNS FERRY NUCLEAR PLANT. UNIT I
ELECTRICAL. MAINTENANCE
SUMMARY
CSSC EQUIPMENT i
FOR Tile MONTl! 0F October 19 81 Action Taken-Ef tect on Sate l
Nature of Operation of Cause of
, Result's.of To Preclude
)
,.Date S)stcr i Cecipca. nt l
ltaintenance The Reactor Malfunction Malfunction Recurrence I
t
'10/16/81 RPS l
5A-K14C Relay will None Coil and iron Relay would not This relates to j
not pick up dataaged energize all the the problem of time 10/14/81 above.
f everytime The iron and coil
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vere replaced and
'i no additional prob 1 cms have.been I
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experienced.
TIi #227788
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, 10/19/81 Ventila-Shutdown lbd.
Fan won't None Motor and over-Exhaust fan inop-Repla'ce'd motor.
tion room exhaust start locally loads bad crable and overloads.
i Tested'OK
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fan 3A TR #280265-
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,i Bacelf in Battery power not
.. Changed out f-I ll10/25/81 Fire 2
d 4
Pn1!25287
- cell dead in None Protection-3 battery battery avai'labicforpanel} battery.
i ll Ik) wever, panel was TR #250765; U,
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operabic.
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,l 3Aiontrol Suction and None Expansion valve Suct; ion an'd dis.
Adjusted expan-
'!10/28/81 Control l
Bay IIea t-bay l chiller discharge out of adjust-charge pressure sion valve..
ing <Veni-il pressure ment
. swinging
.TR #227792 ilation fl, swinging ll a!'
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BROWNS FERRY NUCLEAR PLANT UNIT ' Common l
q CSSC EQUIP!ENT dl MEC!MIICAL MAINTEIGIICE SUKtARY l
FohtheMonthof Octo er 19 81 I
il
. ll yp EFFECT ON SAFE ll ACTION TAKEN DATE SYSTEM
.COMPO!;ENT j NATURE OF OPERATION OF CAUSE OF RESULTS OF ID PRECLUDE I'
'I M\\INTENANCE Tile REACTOR MAliFUNCTION MALFUNCTION RECURRENCE t0-8-81 Secondary Door 2iB
'l Air Escaping None Air d'eal bent, Air leaking from Rx Replaced air seal Containmnt receiving plate Bld. to Turb. Bldg.
&' receiving plate, torn off, foot' foot bolt l
f l! l.
t TR# 230248 l
boltgstripped out i
Door lfailing to-Sending an open alarm Adjusted closure.
'6 c
Door Malfunc-None lLO-16-8:
Secondary Door,721
Containant tion close properly while door is closed Inspected lock &
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l loose screws f,'
t TR# 230308 l
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su MECilANICAL MAINTE!N1CE SUElARY CSSC EOUIP!fE'!T For the Month of October 19 81
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ACTION TAKEN EFFECT CN SAFE DA7E SYSTEFI COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF 10 PRECLUDE Ft'sINTENANCE IllE REACTOR MALFUNCTION MAT. FUNCTION RECURRENCE 9-21-81 CRD CRD Punp 2A Water Leak None Nipple broken on Leak Changed nipple flange TR# 279919 10-15-81 CRD 2-85-590 Valve Handles None Unknown Unknown Replaced Valve T
handles.
ij, missing N-TR# 279822j
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"W" Valve Water Leak None Faulty Valve Leakage Replaced W Valve 9-23-81 Cond Detin.
TR#'279725 L
"J"-Vedael
.h 9-30-81 Secondary; Door 220 Broken door None Unknown Foot bolt, retaining Drilled 1/4" holes plate, hinges & air indoor & installed Containment seals broken pins. Welded, ll l
straigtened hinges
& reworked air seam
,lf f'
I TRt' 190097 h)
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e Bad pressure.
Broken pressure gauge Replace pressure CRD Pu y I'A" Faulty press.
None 3
9-26-81 CRD gauge gauge gauge it TR# 279801
'h ' :
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.Sampl ! return Noisey Pump.
None Bad ' bearings Pump running noisey Installed new
. 9-17-81 Primary bearings pumpjif
'l TRf 239259 Containmnt i
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10-26-81 CRDl 370 Sgrm Pilot Air Leak None Cap' nuts losse Air leaking around Tighten to 100 in.
1 I
Valvde; l$
on all valves cap o' rings lbs., on all 370 vlvs i
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,;l TR# 182334 e
i 10-28-81 Rx Bld i
- 2B Refu21 Exh Damper Not None Damper not closinr0perator working Installed nev Venf IFan FJoar Closing all.the way imprbperly operator TR# 235048 tl
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CssCEcuIrrtkNT.
,IIECilANICAL MAINTENiNCE SUM:fARY Oc;tober 19 81 For the Month of l
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ACTIOII TAKE:3 l
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EFFECT CN SAFE l
C011PC:iEUT MATURE OF OPEPATION OF lCAUSE OF RESULTS OF 70 PRECLUDE I
1 MAINTENANCE Tile REACTOR MALFUNCTION ffAT. rut:CTION RECURRENCE l
'DATE SYSTEI!
i I
Installed new bearing:.
R0-4-81 RilR LPCI 3EA MG' Worn Bearings Mene Badibcarings Unknown TR# 235012 Set i
30-3-81 RilR '
LPCI 3EA MG Gen. out of None Bad bearings liigh vibra; ion Align coupling &
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grease bearing l
Set i
alignment TR# 2F3655 l
l (coupling) h l
- 9-29-81 Fire Prot. 26-11]3 1
Faulty Valve None Val 7e needed Valve binding I: lean valve seat &
I lubricated servicing f
l TR# 203714 t
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!10-13-81 Secondary Door 721 i !
Door will not None Morn parts Door dragging on Shimmed hinges to
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l close threshold adjust door to frame I
Adjust closure & lub.
l Containment 8
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"C"-lljG' Air Casing Leaking None A Faulty Valve Air Icak, Replaced check valve t !
p TR# 280224 10-23-81 11/G,
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EROWNS ITRRY UUCLEAR PLANT UNIT 1,2&3 INSTRUMENT MAINTENANCE
SUMMARY
CSSC EQUIPMENT F0lt Tile MONTil OF _0ctober 19 81 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN
'1 ATE SYSTEM CG1PONENI 0F OPERATION OF OF RESULTS OF TO PRECLUDE RECURRENCE MAINTEN/.NCE Tile REACTOR 1%LFUNCTION MALFUNCTION Unit i 10-2 75 PDIS-75-28 Replace None Faulty Switch Switch Did Not Reset None at Proper Pressure I
10-9 68 PDT-68-21 Replace None Transmitter Faile(
Instrument Indicated None I
Upscale 10-11 46 FT-46-4 4 Replace None Transmitter Erratic' Indication None Erratic
's lUnit
?
10-6 76 R/PR-76 14 Repair None Amplifior Failed Loss of Itidication None i
.c 10-12 90 l
RM-90-25;l Calibrate None Instrument Drift Incorrect Indication None i
o Unit 3
'l l
.. b, Calibrate None Instrument Drift Incorrect Indication None 10-8 67 FT-67-6A' i
]
dl,i 10-9 1
il PS-1-81A', '
Replace None Instrument Drift Incorrect Setpoint None
]
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TRS-85-7Ii Repair None Stepping Switch Loss of Indication None 10-;1 85 Failed i
i
'V Repair None Meter and DC
. Loss of Indication None 10-27, 92
- RM"F"i[
Amplifier Failed q
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37 FIELD SERVICES
SUMMARY
I October 1981
~
-- ~ The unit 1 EOC-4 refueling outage was completed October 1 at 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br />.
Preparat.i_ons,for the unit 3 EOC-4 refueling outage continued through the re-mainder of-the month. Major prefabrication efforts included torus modifications (principally shopwork), mechanical / structural preparations for generator breakers and unit station service transformer, setup of C-zone and maintenance areas as well as refuel floor and turbine floor arrangements and laydown areas.
Final planning efforts and preparation of procedures and revisions con-tinued during the month. The list of modifications to be performed this outage was being finalized at the close of this report period. A major work activity that has been deleted from the schedule is replacement of the jet pump hold down beams (at present this work is deferred.to the unit 3 EOC-5 refueling outage).
Unit 3 EOC-4 refueling / torus outage started October 30 at 2345 hours0.0271 days <br />0.651 hours <br />0.00388 weeks <br />8.922725e-4 months <br /> for a scheduled 127 day duration. Return to service date is currently projected for March 7, 1981.
Quadrex personnel for torus scrap steel decontamination returned onsite October 13.
Work on the turbine building decontamination room was finished on October 19 and Quadrex began preparations for setting up the electropolishing equipment. The duct work for the exhaust fumes has been routed to the SJAE room
~
of unit 3.
Final equipment setup and decontamination of unit 1 scrap torus steel is expected to start the first week in November.
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