ML20126M620
| ML20126M620 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/01/1981 |
| From: | Thom T TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20126M617 | List: |
| References | |
| NUDOCS 8106190299 | |
| Download: ML20126M620 (35) | |
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.g s TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT May 1, 1981 - May 31, 1981 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68
/ l rY Submttted By: / ? // W $ $ $ h !'4 % s Plant' Superintendent ~
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TABLE OF CONTENTS Operations Summary . . . . . . . . . . . . . . . . . . . . . . 1 Refueling Information . . . . . . . . . . . . . . . . . . . . 3 Significant Operational Events . . . . . . . . . . . . . . . . 5 Average Daily Unit Power Level . . . . . . . . . . . . . . . . 12 Operating Data Reports . . . . . . . . . . . . . . . . . . . . 15 Unit ~ . Shutdowns and Power Reductions. . . . . . . . . . . . . . 18
- Plant Maintenance . . . . . . . . . . . . . . . . . . . . . . 21 Outage Summary . . . . . . . . . . . . . . . . . . . . . . . . 33 l
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1 Operations Summary
'May 1981 1
l The following summary describes the significant operational activities during the reporting period. In support of this summary, a chronological 1
log'of significant events is included in this report. l There were 23 reportable occurrences and one revision to a previous
.repartable occurrence reported to the NRC during the month of May.
Unit 1 Unit 1 was in its E0C-4 refueling outage the entire month.
Unit 2' There were three scrams on the unit during the month. On May 6, the reactor scrammed when the main turbine and feedpump turbines tripped from a false high water level signal generated during maintenance en Unit 2 shutdown boards. The reactor scrammed on May 11 when the main turbine and feedpump
. turbines tripped from high water level from a feedpump MGU lockout on loss of control signal and a recirculation runback caused by a loss of plant pre-4 ferred power during maintenance on Unit 2 shutdown board. On May 27 the reactor i
I was manually scrammed to begin a short outage in conjunction with Unit 1 E0C-4 refueling outage to accommodate modifications to unit station serv 1ce trans-l formers.
Unit 3 There were two scrams on the unit during the month. On May 6, the reactor scrammed when the generator field ground relay operated due to a slow transfer of the plant preferred power to its alternate source following a Unit 2 scram which loaded the start bus relay.. The reactor was manually scrammed on May 22 _
to identify and correct leakage (packir g on FCV 68-79) in the dryvell.
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Operations Summary (Continued)
May 1981 Fatigue-Usage Evaluation d
The cumulative usage factors for the reactor vessel are as follows:
Location Usage Factor i
Unit 1 Unit 2 Unit 3
' -Shell at water line 0.00503 0.00403 0.00344 Feedwater nozzle 0.24411 0.17387 0.13295 Closure studs 0.19865 0.13859 0.10383 NOTE: This accumualted monthly information satisfies technical
- 7. .
specification section 6.6.A.17.B(3) reporting requirements.
Common System Approximately 1.10E+06 gallons of waste 11guld were discharged containing approximately 1.84E+00 curies of activities.
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l Operations Summary (Continued)
May 1981 Unit 1 Unit 1 began its EOC-4 refueling outage on April 11, with a scheduled restart date of August 13, 1981. This refueling will involve loading additional 8 X 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modtf-1 cation, power supply on LPCI modification, generator breaker and unit station transformer tie-in (requires Unit 2 to be shutdown), and torus modifi-cations.
There are O fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 764 EOC-4 fuel assemblies, 550 spent 7X7 fuel assemblies, five 8 X 8 spent fuel assemblies, 260 new 8 X 8 R fuel assemblies, and one spent 8 X 8 R fuel assembly. Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 384 locations.
Unit 2 Unic 2 is scheduled for its fourth refueling beginning on or about ' arch 26, 1982, with a scheduled restart date of August 13, 1982. This refueling outage will involve completing relief valve modifications, torus modifications, "A" low pressure turbine inspection, MG set installation for LPCI modificaeion, and loading additional 8 X.8 R fuel assemblies into the core.
There are 764 fuel assemblies in the reactor vessel. At the end of the month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent fuel O
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Operations Summary (Continued)
May 1981 Unit 2 (Continued) storage pool. The present available capacity of the spent fuel pool is 160 storage locations. With present capacity, the 1979 refueling was the last refueling that could be discharged to the spent fuel pool without exceeding thst capacity and maintaining full core discharge capability in the pool.
However, 949 new high density storage locations have been installed, but cannot be used until Special Test 161 is completed.
Unit 3 Unit 3 is scheduled for its fourth refueling beginning on or about September 25, 1981, with a scheduled restart date of February 7, 1982. This 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.
There are 764 fuel assemblies presently in the reactor vessel. There are 124 discharged cycle 3 fuel assemblies, 144 discharged cycle 2 fuel assemblies, and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool. The present available storage capacity of the spent fuel pool is 1052 locations.
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5 Significant Onerational Eveats Unit 1 Date Tite Even:
5/01/81 0001 End-of-cy'cle 4 refuel outage con:inues.
1333 Core unicad completed.
5/26/81 0345 Started fuel sipping.
5/31/81 2400~ End-of-cycle 4. refuel outcge continues.
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Significant Ocarational Events i
Unit 2 D_ ate Time Event 5/01/81 2340 Commenced reducing thermal power from 99% for turbine control valve tests and SI's.
5/02/81 0010 Reactor thermal pcuer at 77%, holding for turbine control valve tests and SI's.
.0030 Turbine contro'l valve tests and SI's conplete, commenced power ascension.
0500 Reactor thermal power at 99%, maximum flow, rod limited.
'2126 Commenced reducing thermal power for MSIV tests.
2140 Reactor thermal power at 82%, MSIV tests in progress.
2144 MSIV tests cumplete, ccmmenced power ascensien.
I 2200 Commanced PCICMR from 93% thermal power (sequence "B").
2330 Reactor thermal power at 99%, maximum flow, rod limited.
1 5/06/81 1843 Reactor Scram No. 118(IT from 99% thermal power when '
outage people were working en "3" 4-E7 shutdoan board.
It appears that undervoltage relay 27TSB momentar11v j
made-up causing normal f eeder breaker 1o16 to "B" 4-L j j shutdown board to trip and immediately reclose. This '
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interrupted power to "2A" 430V shutdoun board. I6C bus "A" feeds off "2A" idO" shutdetm Loard. The his water trips for the main turbina and reactor fceu punn 1
turbines - on2 channel feedo from an inverter uff of th, 2507 unit battery; one channel off vf anit preferred I one channel off of "A" I & C bus. Battery discharge test was being performed on uait 2. The procedure gave operations the optica to jumper the inverter j supply "A" I & C bus. Operations elected to run on one singic element control with one channel de-energized.
This interruption of I & C bus feed on 430V shutdown board "A" caused another channel to drop out unich tripped the main turbine and feedpump on false high water.
5/07/81 0342 Commenced rod withdrawal for startup.
0638 Reactor Critical No. 131 (sequence "B"). )
0925 Rolled T/C. )
0952 Synchroni ed generator, commenced power ascension. l 1350 Reduced thermal power frem 53% to 39% for removal of "B" recirculation pump from service for recirculation pump MG set brush replacement.
1415 A blown fuse in feedwater inverter "A" caused "A" re-circulation pump to runback, reduced thermal power to 36".
1800 "B" recirculation pump MC set brush replacement com- -
plete, increased thermal power to 40%, holding for maintenance un "A" feedwater inverter.
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Significant Operational Events Unit 2 Date Time Event 5/07/81 2020 "A" feedwater inverter replaced, commenced power ascension from 4C% thermal pcwer.
5/08/S1 0015 Commenced reducing thermal pcuer from 63% for re-moval of "A" recirculation pump from service for MG set brush replacement.
0040 "A" recirculation pump out of service, reactor
- o. pcwer at 42%, holding for MG set brush replacement.
0233 "A" recirculation pump back in service, commenced power ascension.
1000 Commenced PCIOMR from 78% thermal power (sequence "3").
5/09/81 0700 Reduced thermal power from 85% to 81% due to pro-blems with condensate demineralizers. (Radwaste at full capacity, condensate demineralizer on hold).
1730 Commenced power ascension from 81% thermal power.
2300 Reactor thermal pcwer at S4%, holding (radwaste pro-bicas continued).
5/10/81 1205 Reduced thermal power to 75% for a control rod pattern adjustment.
1500 Control rod pattern adjustment complete, commenced PCIOMR (sequence "B").
5/11/S1 1000 Reactor thermal power at ,9%, maximum flow, rod limited. g 2123 Reactor Scram No. 119 from 99% thermal power on reactor high water level. Tha trip was initiated when an undervoltage relay operated to cransfer 4-K" shutdown bus. This transfer resulted in a nomentary loss of voltage to the "D" 4-KV shutdcun board which in turn resulted in a momentary interruptian to the unit preferred power supply and the I & C Bus. This power interruption caused a lockout of reactor feed water l pucips and a runback of the reactor recirculation pumps.
l This resulted in a reactor high water level which tripped the turbine and caused a reactor scram. Work was being performed in the shutdown board roon "C" c,t the time of the scram.
5/12/31 0700 The unit remained down to replace a level switch on the scram discharge volume.
5/13/81 1122 Commenced rod withdrawal for startup.
1324 Reactor Critical No. 132 (sequence "B"). ~
1728 Rolled T/G.
1807 Synch onized generator, commenced power ascension.
8 Significant Operational Cvents Unit 2 Date Tfme Event 5/14/81 1400 Commenced PCICMR frca 73% therw.a1 power (',equence "B").
3/15/81 2300 Reactor thermal power at 90%, holdlag, .omputer out of service. ,,
5/16/81 2205 Commenced reducing thermal power for a control rod pattern adjustment.
2300 Reactor thermal power at 70%, control rod pattern adjustment in progress.
5/17/81 0045 Control rod pattern adjustment complate, ccmmenced power ascension.
0700 Reactor thermal pcuer at 99%, maximum flow, rod limited.
5/20/ 1 2147 Co=menced reducing charmal power for MSI'/ tests.
2206 Reactor thermal power at 80%, holding for MS!V tests.
2212 MSIV tests complete, co'menced m power ascen.sion.
2300 Reactor thermal power at 99%, maximun flow, rod limited.
5/23/31 2233 Commencad reducing thermal power for MSIV teacs.
22a5 Reactor thermaA pcuer at 52%, holdin; for MSIV tests.
2250 MSIV tests complete, ccer.cnced power aucunsion.
2300 Reactor chermal power at 91%, holding for turbite control valve :ests and SI's.
5/24/81 0130 Tutbine control valve tests and SI's cenplace, com-menced power ascension.
0133 Commenced PCIOMR f rom 95*' thereal power (sequence "B").
0330 Reactor thermal power at 99%, maximum flow, roo limited.
5/27/81 1945 Commenced reducing thermal power for shutdcun for a planned modification outage.
2215 Reactor Scram (manual) No. 120 from 36% thermal power.
to accommodate modifications to unit stacion service transformers.
5/ 1/81 2400 The unit remained down for modifications to unit station service transforners.
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_Stgnif! cant Operationel Events Unit 3 Dato Tinte Event 5/02/31 0040 C:=mencad reducing ther:ml power for turbine con-trol valve testa.
0055 Reactor thermal power at 88%, nolding for turbine control valve, tests.
0100 Turbine control valve tests completed, commenced power ascension.
0113 Reactor thermal power at 973, holding for SI 4.1.A-10 main steam line high radiaticn monitoring and SI 4.3.A-2 control rod exercise.
0310 SI's complete, commenced power ascension.
0340 Reactor thermal power at 99%, maximum flow, red limited.
3/06/31 1851 Reactor Scram No. 97('" from 997; thermal pcuer when unit 2 tripped at 1S48 hourc and the shutdown bus 2 transferred to start bus supply voltage. Apparently the transfer locded the start bus cauning a dip in voltage to be reflected throegh the common boards, lighting boards, plant preferred and non-preferred systems. Theplant preferred attempted to transfer to the alternate scurce and was slev in transferring.
Uhen the plant preferred and non-prefarred returned, the generater field ground relay en unit 3 operated resulting in turbine-generator locd nbalance :nd e;n-trol valve fast ciorare 2350 Commenced rod withdrawal ter startup.
5/07/31 043'd Reactor Critical No. 109 (control cell core).
0815 Rolled T/G.
0344 Synchronized generctor, commenced power asceasian.
1505 Commenced reducing thermai power frem 67"; for temoval of "3" recirculation pump MG set frem service for maintenance on control system (Bailey governer).
1535 "B" recirculatica pump out of service, reacect thermal power at 453, hciding for maintenance en MG set control system (Sailey tovernor) .
1555 "3" recirculation pumo back in service, ccanenced pcuer ascension.
1330 Reactor thermal power at 512, holdira; f or maintenance l
on "B" recirculation pump MG set contr:1 system (Bailey governor).
2:30 "B" recirculation "G set maintenance complete, c;m-menced power ascension.
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- j. 5/08/81 0300 Commenced PCIOX2 from 74 thermal power (control cell core). -
1500 Commenced reducing thermal power from 321 <iue to pro-blems with demineraliaers (radwaste at full capacity condensate domineralizer backwash on hold).
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Significant Ocorational Events Unit 3 Date Time Event 3/08/81 2300 Reactor thermal power at 78%, holding radwaste problems continued.
5/09/81 1930 Commenced power ascension from 73% thermal power.
2200 Commenced PCICMR from 907. thermal power (control cell core).
5/10/81
0320- Reduced thermal powe- 'com.94% to 89% thermal power due to continued radwastu problems (full).
0450 Commenced power ascension from 89% thermal power.
1500 Commenced power ascension from 37% thermal power, (control cell core).
2100 Reactor thermal power at 99%, maximum flow, rod limited.
5/12/31 2350 Commenced reducing thermal power for removul of "3" string high pressure heaters for maintenance on down stream isclation vlave (3-76).
5/13/81 0105 Reactor thermal power at 39%. holding for mainte-nanace on "3" string high pressure heaters down stream isolation val"a.
1057 "B" string high pressure heaters in service, cam-menced power ascension.
1130 Cenmenced PC EMR from 9c2 chernal pever, : c ent r. .
cell core).
1430 Reaet:r thtraal pcwer at 99%. maximum flov. rod limited.
5/15/S1 2250 Commenced reducing thermal porer fer turbice een-trol valve tests and SI's.
5/16/81 0001 Reactor thermal power at 932, halding for turbine control valve tests and SI's.
0130 Turbine control valve testa and SI's complete, com-menced power ascension.
0200 Reactor thermal power at 99%, maximum flow, rod limited.
5/21/61 2345 Began experiencing rapid increase in drywell pressure.
5/22/81 0035 Commenced reducing thermal power for shutduwn to investigateexcessivi2Y#7""lL1**k"E*'
0123 Reactor Scram :lo. 98 from 40.! thermal power to investigate excessive drywell 12aktge. Remainee -
down to repair Slown packing on FCV-68-79 (Loop "3" recirculation pump discharge valve).
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11 Significant Operational Events Unit-3 l
Date Time Event 5/25/81 0320 Commenced rod withdrawal for startup.
0445 P.enctor Critical No. 110. ;
0455 Reactor brought suberitical, problems with '
icvel instr.umentation LI-3-53 and LI-3-206.
0728 LI-3-53 and LI-3-206 res:ored to normal, commenced rod withdrawal for startup.
0342 Stopped pulling rods due to a head gasket back on HPCI gland seal condenser.
~1335 HPCI maintenance complete, commenced rod with-drawal for startup.
1937 Reactor Critical No. Ill.
5/26/81 0344 Rolled T/G.
0410 Synchronized generator, commenced pcwer ascension.
. 1730 Commenced Pr10MR from 82% thermal power, (Centrol cell core).
5/27/81 0530 Reactor thermal power at 867;, maximum flow, rod limited.
0917 Commenced reducing thermal power for a control rod pattern adjuotmant.
1000 Reactor thermal power at 77%, holding for con-trol red pattern adjustment.
1300 Control rod pattern adjustment complete, com-menced PCICMR (control cell core). I 1700 Reactor thermal power at 99%, maximum flow, rod ,
limited. l 5/30/81 0030 Commenced reducing thermal power for turbine con-trol valve tests and SI's. !
0130 Reactor thermal power at 84%, holding for turbine control valve tests and SI's.
0205 Turbine control valve tests and SI's cocplete, commenced power ascension.
0330 Commenced PCIOMR from 97% thermal power (centrol )
call core).
0530 Reactor thermal power at 99%, maximum flow, rod limited.
5/31/81 2400 Reactor thermal power at 9 9 f' , maximum flow, red limited.
(1)Maintenanco error.
(2) Equipment malt' unction.
12 OPERATING DATA REPORT 50-259
?OC r.F.T NO 1,.\ 1 E UNI t.0MPLETEu by T"d .". i a TELE! HONE .. 'J5n.U.2 _D C 4 3 OPERATING ST ATt'S ---- -,
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4 Brotms Ferry - 1 .s o t,.s '
- l. l;mt.ame: ,
- 2. Reporting Period: IE17 1901 i
- 3. Licensed Themial Power IMbtt 3293
- 4. Nameplate Ratiny (Gross Mwer 1152 DD'
- 5. Desn Electrie:I Rarmy per MWer i
- 6. Mas.imum Depend.ible Cal'aeity (Gron MWe): 1098.4 f 7 Masinium Dependable Capacity INet MWeg l@5 ' ,
s if C! range Occur ia Capacity Ratinp titet'n Numner 31hroug!i 7) Since I.ast itepor: Gire Rea,ons NA _.
- o. Power Lesel To which Restrie:cd. if Any (Se: MWee 'A 10, Reason, For Retrietions. lf Any: NA TH: .%nt h 's - e line , c . a u ,: n i.
I 1. Ilocrs In Reporting l'eriod N' 3U - ', ..
I2 Number of Hours Re ictor ba, Untie-d 3 3 *. ** 2 U ' ' '
l .i Rea -ior Reserve Shutdown Hour.
14 lio ir3 Generator Un-l.ine O N 7 i3 3*
n 3 ,)
14 Lui Resene shutJuan floors
i t.. Grow 1hermal Energy Generat::d iMWH 0 7 ' " O ' ,#' O_.._ I '_.N Grim Electrical Energy Generated (*.thH) 0 3
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!5 Net Ele,.incal Energy Genrrated iMb Hi ..
19 Umi senice Factor 0 'C 5 . 7 d . 7 20 Umt Anulability Factor 0 N UU' 21 Unit Capacity Factor f Using stDC Net) 0 6 2. L _ 5 0 ,,h_ _,
2 .' Umt Cap-icity Factor < Usmg DFR Net) 0 0- . .i 50.6 , , , , , _
23 L mt forced Out.nte Rate 0 0.8 29.0 24 snuidou n, Schednin! O.cr Ne . e Morths Ty pe. I)ste. and Ut.ratum el En h t 25 11 %ut Down At Fnd O! Report Period. E3tunated !! ate of Startup- A ' * ' '
l 2n L.nas in T est Status (Prior to Commercul Operationi. Forceast i.huw' INill A L CHillC \LITY -
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OPERATING DATA REPORT 50-260 flOCKET NO.
DATE 6-1-61_,,_
00\lPLETED DY Ted Th:'n TELEPliONE 7) R i-1 846 OPERATING STATUS f 1 Browns Ferry - 2 N"t'"
- 1. Unit Name: ! l' I
- 2. r(eporting Penod: Ity 1981 4 Licemed Thermal Pou er (Mht)- . ' 3293 '
- t. Nameplate Rating (Grots Mhe)[ I l
- 5. Desian Electrical Ratmg tNet Mhe): 1065 i
- o. '.LiNn~ura hapendable Capacih (Grou \lbe **
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- Mnimum Dependable Capacity INet MWe): N '
5 If CLantes Oci,ur in Capacity Ra;inp titems Number .i Throug:i7) .since La t R: port.Gite Reasoas.
NA . - - .
- 9. Power L t! fu WSieh Re>:rkted. lf Any (Ne: MWej: '%
- 10. Heasons For Restrictium. lf Any- 'A~
This Month Yr. to D.ae Cu:nuk tiu 11 llours in Reporting hnod Iai 3, k 3 _
54.,316
- 12. Namiser Of Hours Reactor has Critica! 394 40 3,@ Ol 30f I5'.22 13 Heactor Hesene Shutdowr Hours 121.23 136.02 12,639 3
- 14. tlours Generator On Line 5<36. 4 5 3346.'54 3 3,03~ . 4 0 15 Umt Rewne Shutdown Hours 0 0 0 l e> Gioss Thermal Ener;y Generated L'th!!) 1,803,11') 10,317,798 94,368.441 17 Gross Electrie:.1 Energy Generated (Mull) 52.0.13y0 2,447,620 31_,13 4 d_05; 1%. Net Elcetneal Energy Generated G,1WH) 377,197 3,DL,6;9 30,001,926
- 19. Unit Senice Fr.ctor 78 8 92.A 6 0 . --
20 Umi Ami!ahihty Factor 72.S 92.4 60.4 21 Umt Capacia Factor (Limg MDC N10 72.S 8 6. C# 5 L. 9 2' l'mt Capacity Factor (U>ing DER Net) 72.8 86.9 3L 9 2.1 Una f orted Outge Rate 93 51 30 -
24 Shutdow ns Seheduled ther Nes t $ stonths t Tvpe. Date, ant: Duration of Fas h e 25 11 %ut llown' \ t End Of Henort l't riod. Estimated Date of Startup: 3Fu 13, !981 26 Unos in I est Status iPrior io Commercial Operation L I ore m i \ s : ii u d 1S1114 L CRillCALITY INITI \l. Ell CIRICITY ___
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OPERATING DATA REPORT 00rxt:T30 50-296 DATE N-2~
COS1F TED BY led._Ih01 TELFPilONL .2 6 222_6846 OPER A TING STATUS
.3 Browns Ferry - 3 S"th !
- 1. Unit Name: l
- 2. Reporting Periodi
.May 1981 .
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- 3. Licensed Thennal Power (StWrij 3293 ;
1152- 1
-1. Nameplate Rating (Gross \lWe):
- 5. Design Electrical Rating tNet .StWe):
1065 l 6; .\taEtium Dependable Capacity (Gross 51We): 1098.4 7: .\tasimum ()ependable Capacity (Net SIWE): 1065
- 3. If Changes Oecur in Capacity Ratings titems Number 3 Thrut.gh 7) Since i.ast Report, Gise Reasong NA _
f
- u. Power Lesel To hhich Restricted,if AnvINet SIWE): NA N* A 10 Renoni For Restrictions, if Any-f-
lhis Af ont h Yr ro Date 4 a no.' >:
II Hours in Reportmp Period 744 3,623 32,271
. l .' No.ntwr Ot flours Re.s tor has Critie.;l 654.15 2.973.61 _ J8j94'. 88' l .1 Hsactor Reserve Shut town lloars 23.35 103.49 2,004. h
.. 14 llours Cenerator un-Line 631.33 2 483.65 23,273.65 15 Umt Ressne Shutdown flours 0 0 0 I ti . Grow t hermal Energy Generaied ($1 bill 2.005J 21 3.649.207 83.014 M I? thow Electrical Energy Generated (\1hII) 654 81 8 0_, , 2,S83,110 27&Q2,,14,0_ 0 15 Net Electrical Energ) Generated ISih H) .
634,377 2,795.42.L 25.619,744
- 19. Unit Senice Factnr '34.9 _
79.6 75.9 U ' Unit Aoilability Factor 84.9 79.6 75.9 21 Unit Capacity Factor iUsing StDC Net 80.1 72.4 6M
' O .' ' t'nii Capacits Factor iUsing i)ER Net) 80.1 72.4 67.1 _
23J Unit 1 orced Outage Rate 15.1 9.9 9.8 24 Shutdowns Scheduled User Nest 6 \lonths (T> pe, Date.and Duration of Fach r Maintenance Septe:nber 1981 25 If shut )own At End Of Report Period. Estimated Date of Startup-On t' mis in is t Status (l'rior to Commercial Operation): Forecasi h hi, u d INITI \ L CRillC.\ LITY INIIIA L El. ECTR! CITY -
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15 TVEIMGE D \lLY UNil PCMLH LEVEL 1)OCK ET NO. 50-259 L: NIT Browns Ferry - 1 D A1E _i-J.-81 CO\1PLETEI) IlY Ted Thon _
TELf ? HONE '205-729-6846 FIay 1981 st0NTil D O(* AVER AGE DAILY PO%Eit LEVEL i)AY AVER AGE D\lLY POMER LEVEL IM%e Net) i stwe. Net )
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t t Btf>LE T1. i) !;Y _ I.e.d_.U.tl ._ j TEL:7tlONii __dC3-U9 :0316 stO.N111 May 1981 DAY ~
O'ER AGE DAILY PONCit LEVEL !>.\ f WEi! IGE D AILY Pub:M: !.E'. i L inhe Neu i '.t W e.% o 1
1951 1009 I. _ ___ .
LQid l . _ . _ . L O M_ . _ . . _
- 1031 ;9 1950 4 1012' , 20 ___ 1q16 1008 1N'1
- ( . . _ _ _ . - - _ _ _ _ _
,, 816 ,, 1061 774 2.1 _
10 E-s P.16 ;; l,0,j 6
.., 855 25 1033 10 . _ _ -
010
.6 -
In So - <
11 903 ,, 934 g, -8 -8 3
Lt 123 -I
'9 la 799 ~0 to _ _.
15 978 ;; -6 to 078 IN5 TRl'( llON i t in t!. s ., , 3; the4.c.nc . .k : a p. .n s : m e! .i '.W,'e . % : 1.i c ... h : i s ' h. t $. .o c .
".c tie.n I a m te mens : ?
i l
1 l
I l
4
, - - - , , . . . , , , , , ,e - - - , - - . , - - . ~ . . - - n , , - - , , - - , . - , . , - , - . - , ,
,,..-.-,,,..w, . . , , . , -.----w,,-. . , , -,, ,-.
17
.'.VER AGE DAILY L'.N1 T POWER LEVEL.
l DOCKET No. 50-296 _
. .s; m ; T,tovas re r" - 3 in 1.. 6-1-J1 CO'.!f'LETEll 0Y Ind Tho .
TEl.EPHO V 20 f- 7 29 t i> '.6 s10NT!! M3Y 1981 D \( , \VER AGE D \lLY POWER LEVEL D.i'r AVEk IGE D.\lLY P0w CF, l.EY!:t.
I %1Me Neu !the Net, j 1063 i. 1069
, 1053 i3 10 0
- 1059 19 _ _1053 4 1068 yg 105a
- 1054
- : __, 105?
,, 323 ;, 13 330 i -11
, 816 -13 3
,, 833 ,< -13 I rj _ . _
1026 ,, ; 3';___
It 1010 -. 966 ___
i, 1052 ,3 1063 13 ____
100S ,9 1066 ra 1061 :g 10'46 _ _ ,
i; 1062 ,g i 10~2 in inso INS I R L:CTIONS tln i!as t .o i int the . net.ip a !is oe o.m ,:r.:n.\l%c Neitit,a,h..n ..!>!n >.n.. , d - m1 -
'! e ns .nes 4 hoh inty.nv o t
., y , y ,.v--',e-- * *'"'"" ' -**- "
o 11NII *,ltt'ItechNS 1ND POWElt Ill. DUCTIONS gu n 6,l No, 50.- MS___
UNil N A%tt Er nrm Frrrv - 1 '
i t%'II: 6-1-ul Hi tult I \10 Nill f fi:V /
CDP.tPL1 Tl D tty Ted Tliom 1 L1.1 PilONE 205-729-6dM ___
_ E F.
+
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step.it : iE L-j' P.esent iteturrria c 172 S-1-81 S 74'. C 2 EOC-4 Itefuel Outage e
00
[_..__.___...._.._____ .. t__.___________. _ . _ . L. . __ _ _ _ _ _ _ _ _ _ _ _ _ _
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UNil SiluIDOhN$ \ND POWI R RI11t'r1 ONS DOGE 1 NO. 50-260 UNil N AME 11rowns Ferry - 2 D A TI- 6-1-81 RI i'OR I MONill May [
COMPill fli l1Y Ted Thom
. I ELEl-ilONE 205-729-6846 E
-, =g
- - J, =u.4 1. it e r r.ce g-r, E
g <t Cause A Corsetine No Dak
. i }{ % _E 5 5 I s ei.t 3? h3 Atnotiin A 5 $ 3 .j g licport r viL 5' l'. event itet on en. c
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i 188 5-1-81 S B Turbine Control valve Tests and SI's 189 5-6-81 E 15.07 3 11 Main turbine and reactor feed pumps tripped due to false hi;;h water level (maintenance-workind on 4 KV shutdown board roon). [
190 5-11-81 F 44.73 3 11 Reactor high water level (personnel working in "C" shutdoun board roc:a)
Unit remained.down to replace a level switch on the scram discharge valume Begar. 0700 on 5/12/81.
191 5-16-81 S B Control rod pat tern ad j ustiaent.
__192 5-27-81 S E 2 .
To accommodate moditications to unit 4 statian service c ransf ormers
__ _k ___._
l ?
1 I I . .. . - 1 itca .in Melnul I sinb;i G .lintiu. ao.n
'. S. helil. .I \ 1.pt pui.ni 1.ntin s i l . , .i . ira ! Mr.o.el io. h.pm ate n u. I b: .i 11 M auiici.niu ..: Iot ' Marnul S.;t.ini.
I nin Steces 1." I i enm
( Ret..e!a,; Autonuin is nn. i woi R i...r il i 1 6 i ic (Nt.Ri G
- 1) R. ent..tes . IL t t . r. .n 3 4 )t hs i t I sp!.nn i dieti i tqei.n. I . u. .. A I i. . n v ! s ci..i. .on i i inmn it ut. '
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M*eia.il ,. inns i
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f UNI 1 SitUll) OWNS .\ND POWER RIDLICTIONS DOCKET NO. 50-296 i - Ufill NAME Browns Fv-rrv - 3 i DATE 6-1-10 j
R1 PORI MONill gY / COMPLETED 11Y Ted Thoisi TEll.PilONE 205-729-6846 . =
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& 3p 4 3 ~l 5 Lvenii -
- 7. ? M_ Atinu:t sie i
f5 $ 3i5 Rep..si = Jib 5' Pret.ent Rbcurrence .
., c v-d l 75 5-6-31 F 13. 8ts 11 3 l
control l valve _ fact closure.due to '
generator unbalance uhen unit 2 j'
t sc rarr.med .
l i 76 5-22-81 F _98.78 _A 3 Packingleak on FCV-68-79. .Startup f delayed due to reactor water ' level j
indicator probleais and IIPCI gland l
3 seal condenser problems.
4 4
9 1
1 !
I l
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! Mamul in: h e;. iut u . .s? Data j li-M date: .:Lr.. l es 2 Mana.tl .9tain. 6in4. '.heci s t o- 1iceenee
! t R s ue' ., .. Aui.+tnatic Si am. I un. In u i s I i'_ t I ile int Rt t. i i in , train.
I e t; o.l a.
1-Ott:en ii spl.iin 6 Olnii I L 8;'/5 tii.I ll *? . . r e .\ l t s ' I t .s I ..t!. tue.t 1. ti l 1 \ han:nt i in s -
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1
, BROWNS FER!d NUCLEAR PLANT ' UNIT 1, 2, & 3 .-.
~
INSTRUMENT MAINTEllANCE SUFEIARY CSSC EQUIPMENT FOI? Ti!E MONTil OF. May 19 81 i
4 NATURE EFFECT ON SAFE' CAUSE i ACTION TAKEN DATE SYSTEM COLIPONENT OF OPERATION OF OF , RESULTS OF- TO PRECLUDE MAINTENANCE Tile REACTOR MALFUNCTION !!ALFUNCTION RECURRENCE
! Unit 1 Reactor LIS-3-58A Repair N one Replaced Suitches N/A N/A Feedwater LITS-3-58B- With New Improved LIS-3-58C Type LITS-3-58D '
LIS-3-56A LIS-3-56B LIS-3-56C
, LIS-3-56D LITS-3-52 LITS-3-62 LIS-3-184
! LIS-3-185 - -
Neutron A,B,C & E Repair None Nortnal. Fnd of . Loss of Power Displa o None U l Menitoring ifiO! Poser Life of Power on panel 9-5 j Meters (panel Meter l
9-5) -
, APRM-A Repair None Faulty Power Erratic Test Output None
! Test Potentio-
! meter j C ont a in- LI-84-2B Calibration None Instruacnt Loop N/A None ment Air Found in Toler-Dilution ance Ii lUn E React or 3AK27 Rcplace None Faulty Relay No Rod Block from None
^
Protection 25 gal. switch on t System SDVT Repair None Faulty Meter Sloppy Switch None-
! Unit _J Meutron APlet-D Monitoring Function Switch' Action l
I.Pic t- D Repair None i
s a
$ I l 4
+_ _ _ . - - . _ _ . _ - . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ , _=__ _=__- - _ _ _ _ . . _
UllOUllS FEIUtY NUCLEAR PildlT UNIT 1,26 3
~
INSTRUMEllT !!AINTEtJANCE SUMt!ARY CSSC EQIIIP IEllT FOlt 'nlE MOIiTll OF MaY 19 81 NATURE EFFECT ON SAFE CAUSE / ACTION TAKEN DATE SYSTEM COMPONENT OF OPERATION OF OF , RESULTS OF TO PRECLUDE MAINTENA!!CE Tile REACTOlt MALFUNCTION MALFUNCTION RECURRENCE Unit 3 Main Steam PDIS-1-36C Replace None Instrument Drift Setpoint Exceeded N/A a
(Cont) Tech Spec Core Spray FI-75-21 Calibrate None Inst rument Drift Indicated Iligh None
- 9 e
O t
e
a.
I 4 ,
!c LRO'.GS FERRY iUCLEAR PLiGT' UNIT 1 and Common ,,
b CSSC- EOtil1%1::tT ELECTRICAL liAltiTENIJ CE SUICl^.RY .
For the L uth fif M3Y 1981 ,
)
ll! * !Mie Syste2 Cceponent tlature of F.Fec t on Sale Operation 6f _
Caum af.
j
. Results'of Action.Taken To Preclude l! 212in renance The Reactor Ital fur:e tion Malfunction K ?currence - '
5/1/61 i Fire Fire pump During post- None, manual uiring wtti re- Fire puiap auto-start neplaced permanent l ) Protection auto-start < modification. start capability moved from term- logic Inoperable. ulring immediately.
logic tests on a neu was operable. Inal poluts in! . Precautions verc
/g main relay. panel added to the work
' sprinkler sys-
![ I tem, the fire 52, interruptinn pian rcquiring the pump'at3t o- power to. fire- -electrictans to con-i" -l*
atart logic pump auto-start sult with the cogni-
-zant engineer prion l'j il was found inoperable circuit, possi--
~bly shile per- to removing any
- - foruIng a modi-existing ufring.
- i ,
fLention in.the LER#BFRO-50-259/81h I panel.
i 1~
- fj'5/1/81 RBCCW FSV-70-32 FCV-70-32 None Ead calenoid: FCV-70-32 inoperable Ecplaced solenoid coil, valve operatt i inoperable coll ou FSV 'U
' 32 properly._ -
l , TR #166304 1
), __
_._ g During per- None, unit in liclay uas slight .-Timer relay tuok too :The relay was cali-
, i 5/4/31 , m in steam: Automatic brotcd to'and sucac depressuriza- foruance of cold shutJ.ma ly out of accep- long to operate l
jl; tion system S14.2.B-44 table calibra- ofully tested.
Icgic tim.:r relay 2E-K35 tion TR #219347 relay. operated in LEit#BFRO-50-259/81:
i .
j ; 126.25 secotuis __
i5/7/81 Core spray Auta-sequenc~ Scheduled None, reacter Thae delay rclay Relay (14A-Kl9B) took Adjuured timer to uithin. limits and
- l cooling ing timer 14A- maintenance vessel uns (14A-K19B) was too long to operate.
K19B and relay SI4.2.u-39D unloaded. slightly out of Time delay on high replaced. relay M A-l '
i 14 A-K 122A calibrattun. dP spray header to K122A. Core spray j
- Tica delay on core plate annuncia- system, logic relay-operated properly.
high dP spray tor inoperable.
l ,
j i header to core TR #219350 -
l 1
plate annuncia- ! ERF BFRO-50-259/ ell. ,
tor relay (14A-K122A) was tcund l to be bad.
l l
- t ;
i i
? i
Eno'. MS FEnRY HUCLEld' PLANT U!1lT 1 and Common CSSC EQtIIPill:NT ELECTRICAL nTIITEil;CCE Sl!IftARY For the Month of M"Y . , 19 81 j
~
itiect on Safe Action Taken !
!! Dcte System Ccmpenent fliture of Operation of Cause-of . Resultc of To Preclude
! Itaintena::ce The lam e tor !!al f uric t ion dial func tion nccurrence 4 5/10/81 Fire pro- Cable tray Received Mone 1)uring refuel- False alarm receiv- Replaced heat detec-'
,tection heat detector false alarm ing while pull- ed in control room tor, applicable-J TE-39-44C in contcol ing cables the : parts of SI4.5.ll.C.
room. cable tray heat I run, heat detector detector was operated properly.
, damaged. TR #236764
! LERfBFRO-50-259/8122
' I 5/13/81 Air coa- "18" cont ro l Chiller would Mc,ne 011 puup motor Chiller inoperable Replaced oil pump ditioning bay chiller nat start shatt broken motor, chiller ope:
ated properly. The l
notor shaft broke g S/14/81, it ocs #-
j determined that the l broken shafts was a i result of a sticki q
] ! oil relief valve.
! Hech. maint. repine-8 ed relief valve, t h.
9 motor was replaced, i oil added and the i i
- ; chiller operated
- properly.
I TR #236/91 i ! TR 6208746 i !
, i
, iS/14/31 Care "lL" core Breaker uould None, reactor Jack nat tread Breaker would not Replaced jack nut.,
Spray spray pump not rack fully vessel was vere bad rad rack in properly. strai;;htened uount-Cooling breaker in unloaded. mounting plate ing plate, the brea beat er racked in proper-
.TR #203586 E
I
' e I g i
a lino'G;S FEiti'Y NUCLEAL' PL! GIT UNIT 1 and Connon -
EII.CTRICAL 11AltiTENtdiCE SUFIMAKY CSSC 13111 till.NT
- For the Montli of MAY 19 81
. 1'.i f e c t on Saic j Action Takea I Nature of 0)cration I of- Canse'of . Results of To Preclude
- Systect Lenponent .,ac u r reac e
'tr ' e -
- aintenance The l< eac t o r Aalluriction Malfunction r I
- 5/14/81 :liesel "B" Diesci Pal 9-23-7 None Switch and con- Covenor control Replaced bolt, ran Lenerator generator governor con- trol block re- switcli vould not , D/G and govenor con :-
~
panel 9-23-7 trol vould taIner bolt inake proper contact trol _ switch operat-governor not work in missing. uitti control block. ed properly.
control lower direc- TR #203590 1 tion in l cianual I a
l t.n 6
i l
I
?
l i
i i
! , k I i
3..
2 I L P.C'.%S FlIi Y ? UCLEE ! *.!WT UNIT j ELECTR1 CAL :lAl;:TEstc;CE SLRIM/J:Y QC i Qtt1 P"ENT For the '40:tth of NY 19 01
' i l
~
Eticct un '; ate Action Taket
, Ita t e Syster. Cccponent Uature of Operation.of Cause,of Resultc of To Preclude
,' I ,
- la i r,t ena nce The Ranctor Malfunction Malfunction Recurrence Relay 23AK51 During per- Ucne Bad relay- CSCS suppression Relay 23AK51 was 5/5/81 l IIPCI chamber high level replaced and tested i
i formance of (23AK51) f SI4.2.B.27 annunciator and successfully.
relay 23AK51 relays were inoper- TR #180927 1
l failed to pick able LER&BFRO-50-260/8120 4
up l
LCV 73-8 Bad solenoid llot well LCV 73-8 Replaced ceil'and f5/6/81 IIPCI Level control None, IIPCI was coil, blown fuse inoperable blown fuse, level 1' value inoper- operable able control valve operat-ed properly.
4 TR #225565 a h
- h. i 5/7/81 Reactor Feedwater Inverter was !!une Bad invert.er Automatic control Replaced inverter,*
l inoperabic, manual automatic feedwater
, Feedwater inverter. not operating Control properly feedwater control control operated was required properly.
l
. TR #205837 e
2 i '
s- -
t;one llS-85-48 broken lland switch inoper- Replaced switch per f5/9/81 !Cantrol lland switch lland switch inoperable EMI 23, new switch
. rod drive 85-48 able
= operated properly.
!' TR #205842 I
,' !' 5/14/81 Armuncia- 4kV shutdoun Received a None Bad alaru relay 4kV shutdown baard Replaced the alarm tor system board battery abnormal alarm battery charger relay, the alarm
- charger alaru at panel 9-3 nlarm circuitry cleared and operated inoperable properly.
- l circuitry TR fi205605 3
e k
l
. i i i I
_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ e , - ' -
3
. 2 i".C':5 :-T.; ;Y ::UCLEAR l'I. ANT USIT .
( ESC Ftst:1 ;?i; ::T LLEC TRICAL :nINTEMAI CE SDDU.RY -
Fo r t he :-lont h o f #7 19 I
' Action Ta'r.en ~
~
lEfe.;t on 5.ite ,
I !Mte Syster Ccepenent Nature of v:> eta tion o f Cause of Results of To Preclude
! Maintenance The hactor Mal funct ic n Nalfunction Recurrence t
l Relay lS/14/81l. Primary
! contain- (16A64A)
Re"uel zone ventilation None, relay coil failed the Bad relay coil Refuel zone ventila-tion isolated Natural end of coll life. Replaced '
ment inboard and relay and logic relay coII, relay l outboard circuitry in operated properly.
l isolated the safe direc- TR #204427 1 tion ,
'}l 5/17/81RUCU Relay 16AK26 RUC isolated None, the logic circuitry is Ead relay coil Relay coil opened and dropped out Natural end of coil life. Replaced designed such relay 16AK26 relay coll, relay that when this operated properly
! relay coil fail. TR #204432- N ed FCV 69-1 l
, ; closed auto-i natically.
I.
I l i
i 1
I I
t i
i 5
l -
l i :
- a L!:C'.T; ' i:; '.Y .UCLEAi: PL: Tf l'!;II 3 (N' C r w it:1!JIT h Lf r.Tn1 C.'.L :nII;TL;;" E St.q2tU:(
For ti.e '+' n t h o f May 19 81
- - - - - - - - ---t ,
. - - , t r e.c t n ' .i c i Action Takea j! Pne S y ;. t c r. ' cr.p unent I:ature of 0;w ration cf Camie, o f
- Res.:l te o f Malfunction To Freclude
'
- Miintentuce d- T actor m lfunction Recurrcnce i/1/81 iI ilPCI FCV 73-35 FCV 73-35 None, v alve Valve motor FCV 73-35 inoperable Replaced valve motor
! inoperable failed in the grounded- performed EMI 71'6 (closed) safe EMI 18.1, valve position. The operated properly llPCI remained- TR #221357 ope ral:1 :. -
',j 5/5/8L RPS Automatic Uhen perforu- Ilone, the 1.:al- Auxiliary con- The actuator would Freed contact, the scram actua- ing SI4.1.A.5 function of the tact 9-10 somatimes de-ener- contactor then oper-
. tor 5A-1(14C on channel A, auto scram (scram contac- gi: e ngain af ter the ated properly.
l in panel 9-15 had problem actuator was in tor) was bind- scrc:a reset signal 'IR #221352-4 ,; uith switch tha safe direc- ing cleared w
,I when rcsetting tion o3
'; half scram
,i
- ,I S/7/81 l!PCI Inlet drain Grounded cir- None 11oisture in LS-71-5 was11naper- Cleared ground, leve 2
line stea.a cuit on 250V LS-71-5 caused able switch returned to g
l pot level Rx MOV board short circuit service l TR #205913
, suiteit at terminal luy 5/8/81 Ventila- 3E3 battery Fan "b" was Noa I:n.1 'i he t ca l Fan periodically Replaced overload, tion icou fan "h" periodically av erl . ,a;l
. rcipped fan operated proper 1 1, circuitry tripping TR #205286 TR #205287 4
t -.
4 '
4 I
e
! 1.
- i 6
l i
I
! 1
F.RC'."M Fi:: ;Y ::UCLi':J 1*LAN1' UNil 3 LSSC l'qP i lii"T:T El.i:CTRICAL 21\lGTEi:ANCE SriMG ,
May For the 'bnth of _ 19 81 LTiect on'S.i f t i Action Taken
- ~
IIature of Operation of Caum,of Results of To ?reclude hy;ter Ccepanent l ltne ';aintcnance The Renctor .% 1 f unc tion Malfunction Recurrcnce 5/11/8llutR FCV 74-57 Valve ther- R11R , 1 cop 1 The bolts which FCV 74-57 inoper- The motor bolts and-l malled out on suppression hold the valve able bearings were re-opening and pool cooling motor together placed, the-motor j closing inoperable broke. This reinstalled, the-allowed the valve operated pro-l bell to come perly.
i lot.se and the TR #223360 l rotor to rest _ LER$BFRO-50-296'/812<
.i cn the stator preventing the i motor from j
3 running y i
- 5/14/El iiPCI ECR circuitry During per-y ll?CI inoperable Loore cable llPCi tripped during Lcose connector traa l formance of connector frou fast start test t.ightened and SI
' S14.5.E.1.d & EG?! box at the 4.5.E.1.d 5 e I
successfully comp 1.--
, e the IIPCI ECR actuuror tripped on preventing prcp- ted.
I l l overshoot er EGR opera- TR 6205340 l i during fast tiou LER0LFRO-50-295/812.a
' start test
. 5/17/81 itPCI ' LCV 73-8 Valve had an None, !!PPI was Solenoid coil llotwell level con- Replaced call, valv; j intermittent operable burned trol valve had operated properly.
operation intermittent TR #205528
- . operation I
e -, ,
f5/22/81' Primary l Relay 16AK65A Purge valves None Bad relay coil Purge' valves 64-17, Replaced relay coil.
contala- 64-17, 30, 33 30, 32 und 76-24 cleaned contacts ant.
ment and 76-24 Inoperable iron, relay operated I
wculd not properly.
open TR #22513/
I !, .
i l
p *
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~ I uw
.i .; l 30 -
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' t ') u W 1 Q r 4 f3 Cf; W .J w
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'4 ."4 M ,1 W
-A w :.s Gk U 6 CW
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U :. - "y 2 *a f* y ec O /A r1 W ~) M
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. =01 M O JMC M ** ' . * (1 Q c m e, Q .~e ' Jr: J 4*
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s CSSC l'OUII't1FNT 11ECllANICAL 11AII;TEtRNCE SUt@iltkY
- For the lionth ot' M3Y 19 81 _ ,
EFFECT ON SAFE ACTION TAKE!!
1 ATE SYSTD1 C C 1FON EI T MATURE OF OPi2ATION OF CAUSE Ob _j RESULTS OF 'ID PRECLUDE IMIHTENANCE Tile REACTOR IMI FIII CTIO.': 11ALFtR:CTION RECURRENCE 5-1-81 RBCCW Drywell Air l'it t ing broke None B rol:en Fitting Leakage on outlet Replaced flair fittiu compressor B 6 1/2 copper tubing 18" long ,-
TR 225573
'4-2 /- 31 CRD 2-85-55'. Valve Leaking None kust on seat Leaking through Cleaned valve seat E stern TR 208448
'6-27-81 CRD Module 42-55 Broken ?!one Unknown llaknown Replaced handuheel Valve 2-85-588 liandwheel TR 225522 i-7-81 IIPC I Cland Seal Bad gasket None Worn Casket Unknowa Replaced gasket-Condenser TR 182072 u
H
's-21-31 Fuel Pool 2A Fuel Pool Pump noisey None Bad Out bosrd Noisy puap Installed new bearlin Cooling Cooling Puu:p bearing & adj. packing' TR 204548 i-26-81 CRD Discharge :irty Filter Nco-e Dirty Filter Dirty Filter Installed new filter Filter Due to Service TR 205367 i-30-8] RCIC FCV-71-3 Packing Leak tione Leaking Due to In Service 1acking Replaced packing Service Le.sk TR 148048 -
4
MEclLuiICAL HAINYE!; MICE SUti!-It.RY CrSC EnUII'tif::T For the liont h of M3Y 19 8I EFFECT Ott SAFE lCTION TIJEN K\Tt:RE OF OPELA flOIl CF CAUSE OF LESULTS OF l>NIE SYSTEli COtiPct:Lt;T
- til;rl12'A!
- ::E Ti!E REACTOR 11ALFUt:CTIO!!
j ~10 PRECLUDE
. It'.LI USCTION RFCUPREUCE 15-6-81 ttX Feedwat e ; tJone Unlnoun' tad equalizer Valve Meplaced Valve l Lad Valve LIS-203ti TR 240851 I
5-6-81 IIPC I cland Seal blown Caskets tion e Unit Scram Gaskets pushed out of Changed Gdskets 4 Condenser E1519 position TR 182046 5-7-81 ilPCI Gland Seal Blown Gaskets I one Unit Scram Caskets pushed out of Changed Caskets Condenser E1519 position TR 182045 i
- $-15-81 IIPCI isall & Tappet Overspeed Trip !!one Testlug fuspection, o.k. Remove ball 6 Assembly tappet-inspected o.
TR 234907
- 5-23-81 Rx Water FCV-66-79 Bloun Packing rione Scored Eloun packing-Unit 3 Repacked valv,2 vit.
Re-Cir I;oun grafoil packing u TR 198860 N iS-10-81 D/G 3C D/G South Replace St arte - Hone Sticking Vane St icking Vane : Due to Replaced starter c.
Side Starter ilotor being . dirty Cleaned Valve TR 205289
'-25-81 !!PCI Cland Seal Top ilead !!ane Over-Pressured Casket pushed out of Changed Gasket Condenner Gasket Llown Condenser Position TR 205553 5-22-81 CRD Ace tacul at o r Valve Stem tiene lini.n own Valve Stem separated keplaced Valva Ue3, 3Q-07 Charping Separated Fram Hedge "R 205546 i
11 0 Va l ve fron Uedge i
l5-29-81 ilPCI FCV-73-5 Pc e king ::aae Survice 6 Valve racking 1.eaking l<epacked Valve
!.eak in s Pressure
.i-29-31 IIPC I 3-73-20t Pack init I -ah L .n e Horn Packing, Packing Leakins due Repacked Yalve i
t (- Service ik 221338 1-14-8) IIPL1 FCV- 1 1-3 5 Proken Stem !!cac Unknown St a !!n t B r o!-. e n O t' i %placed stem nut i
l ::ut At Flange Ta 1S2090 i i
f s
[
33 i
OUTAGE SUM?tARY May 1961 i ,
! l
'The Unit 1 cycle 4 refueling / :rus outago continued through the month of 1"
>by eith major emphasis on the following:
- 1. Torus internal and external modifications.
- 2. LPRM changeouts (completad May 3, 1981).
-1. In-vessel inspections. l l 4. i;P turbine disassembly and sandblast for non-destructive 1
l tests.
5., CRD changeout.
l
). 6. Generator breaker modification (P0214) - Initial preparations.
1 j 7. iB reactor feed pump disassembly.
[ E. Reactor vessel feedwater spargar changeout - S tarted May 13, 1981.
- 9. Local leak rate testing on selected valves.
- 10. 'tain steam isolation valve maintenance.
- 11. Main steam relief valve testing - done off site.
- 12. CCW tunnel inspection and repairs to inlet tunnel joints.
- 13. Fuel sipping.
In conjunction with the Unit 1 outage activities, preparations for the Unir 2 station service transformer modification (P0275) outage continued through may. Unit 2 was chutdown May 27, at 2217 hours0.0257 days <br />0.616 hours <br />0.00367 weeks <br />8.435685e-4 months <br /> to begin a scheduled 21 day outage. The principal efEhrts during this outage will be completion of the unit station transformer electrical and fire protection work, change-out of the 11 and 0 SamPlc 2
r turn Pumps (EC:1 P0313), 161 kV capacitor bank modifications (ECN PO403) and reactor feed pump disassemblies (B and C).
.