ML20071F347

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jan 1983
ML20071F347
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 02/01/1983
From: Swindill J, Thom T
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20071F322 List:
References
NUDOCS 8303150496
Download: ML20071F347 (40)
v • d • e


Text

{{#Wiki_filter:%e;n, w .. ; ~a ~ w ~ m m.m n~ w n -e m v ms.mn m > w w e w n-w.- ~ - g y;c, s.,. (y v14. ~ -;sa e. 4 4 +, n +./.e q,.7. <. u se.v,, gg i,.: s ~ o i TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT t MONTHLY OPERATING REPORT January 1, 1983 - January 31, 1983 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by: [ /$M// [en Plant Superintendent 8303150496 830209 PDR ADO::K 05000259 R PDR

-, _ -,,, n -

-+ -, ; +w-; ~. =w-me-.w.~s.xmn ymn c m.. -m-wc.- ,.r-~~~ 'ca C e a ya., + d .,. -6.u w;m . c :._,, .-a, t TABLE OF CONTENTS Operations Summary...................... 1 Refueling Information. 3 Significant Operational Instructions. 5 Averge Daily Unit Power Leve 13 Operating Data Reports.................... 16 Unit Shutdowns and Power Reductions. 19 Plant Maintenance..... 22 Field Services Summary.................... 34 l l i I O

.., n. - n.- a.,sm mmmm vwsmms~v yw -a. -m.. ~=+r, . = ~ - - n e,r,. , s c.e,

3..

.c. 1 Operations Summary January 1983 The following summary describes the significant operation activities during the reporting period. In support of this summary, a chronological log of significant events is included in this report. There were 12 reportable occurrences and three revisions to previous t reportable occurrences reported to the NRC during the month of January. Unit 1 There were three scrams on the unit during the month. On January 23, the reactor scrammed on MSIV closure from main steamline high temperature when a steam line blew out in the steam tunnel. The reactor was manually scrammed on January 25 when a recirculation pump tripped and could not be restarted and the unit entered a 24 hour limiting condition for operation (LCO). On January 28, the reactor scrammed when the turbine tripped on a false high reactor water level indication which was caused by a loss of unit preferred power. s Unit 2 The unit was in its EOC-4 refueling outage the entire month. Unit 9 There was one scram on the unit during the month. On January 12, the reactor scrammed on reactor low water level when two reactor feedwater pumps tripped from a false high vibration indication caused by maintenance on the out of service reactor feedwater pump. 6

,,n -m - - a-c._ n +.vrww we,;w~m m www~v~~nwnn,e --?u ~ir-t v < -l<y -:f eb v.E. < e 7 -:s ;f',e 3 L G-s G r.,. ~ 2 v,i m y ,a ,a a ~,: ~ , < +- Operations Su=marv (Continued) January 1983 Fatinue Usane Evaluation The cumulative usage factors for the reactor vessel are as follows: Location t Usane Factor Unit 1 Unit 2 Unit 3 Shell at water line 0.00577 0.00448 0.00391 Feedwater nozzle 0.28078 0.19544 0.14871 Closure studs 0.21955 0.15641 0.12705 NOTE: This accumulated monthly information satisfies Technical Specification Section 6.6.A.17.B(3) reporting requirements. Common System Approximately 8.72E+05 gallons of waste liquids were discharged containing approximately 2.70E+00 curies of activities. 4

+.w.vm. -,z- ,p - -.[ w e". t , c;- g m n- .n, m... n 7.,,... aw.wm ew-e*,, v-rew.+ w.c. 3- ,7 u, ,.,; 94. s .,n

m.,

n ~ 3 ODerations Summary (Continued) January 1983 Refueling Information Unit 1 Unit 1 is scheduled for its fif th refueling beginning on or about April 15, 1983 withaschedugedrestartdateofAugust 15, 1983 This refueling will involve loading 8 X 8 R (retrofit) fuel assemblies into the core; finishing the torus modification; turbine inspection; finishing TMI-2 modifications; post-accident sampling facility tie-ins; core spray changeout; and changeout of jet pump hold-down beams. There are 764 fuel assemblies in the reactor vessel. The spent fuel storage pool presently contains 52 new fuel assemblies, 260 EOC-4 fuel assemblies, 232 E0c-3 fuel assemblies,156 EOC-2 fuel assemblies, and 168 EOC-1 fuel assemblies. The present capacity is 1,148 locations. Modification work and testing are in progress to increase the spent fuel pool capacity to 3,471 assemblies. Unit 2 Unit 2 began its fourth refueling on July 30, 1982 with a scheduled restart date of March 7, 1983 This refueling outage will involve completing relief valve modifications, torus modifications, "A" low-pressure turbine inspection, generator inspection, MG set installation for LPCI modification, loading additional 8 X 8 R fuel assemblies into the core, TMI-2 modifications, post-accident sampling facility tie-ins, and changeout of jet pump hold-down beams. i l --,m1i

.c- ,., _.== mnwrsm c=wn.a ownw.m mn.~r-r -:.~m-- -~ rw ; r. 1-:.n n - t m%,. 7 - - -.. ni um::,. . - v u a..,,: 4.;.,.e m.;; i.; ;

y..,...g1; e ;.,n,,,

.+.,,r. n ~~ 4 Operations Su===rv (Continued) January 198: Refueling Information Unit 2 (Continued) There are 325 fuel assemblies in the reactor vessel. At the end of the month there were 248 new fuel assemblies, 439 E0C-4 fuel assemblies, 3 353 EOC-3 fuel assemblies, 156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 422 locations. Unit ~4 Unit 3 is scheduled for its fifth refueling on or about October 1, 1983, with a scheduled restart date of January 31, 1984. This refueling will involve loading 8 X 8 R (retrofit) assemblies into the core, finishing the torus modifications, post-accident sampling facility tie-in, core spray chani aout, finishing TMI-2 modifications, turbine inspection, and changeout i of je,t pump hold-down beams. There are 764 fuel assemblies presently in the reactor vessel. There l are 280 E0C-4 fuel assemblies, 124 EOC-3 fuel assemblies, 144 EOC-2 fuel assemblies, and 208 E0C-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 993 locations. t l l

.. - - - m, - s c.ww.enom wem +.v*-wrew.,..w.wm..~ m~~ ynm3< m c4 3 4W:% %,y v:..s g -a,f y. :waus, v.,,... n ,c.6 g, a.: 5 Significant Operational Event Unit 1 Date Time Event 01/01 0001 Reactor thermal power at 99 percent, maximum flow, rod limited. 01/09 0030 Commenced reducing thermal power for turbine i control valve test and Surveillance Instructions (SI's). 0100 Reactor thermal power at 92 percent for turbine control valve test and SI's. 0105 Turbine control valve test and SI's complete, com-menced power ascension. 0400 Reactor thermal power at 99 percent, maximum flow, rod limited. 0900 Reactor thermal power at 98 percent, maximum flow, rod limited. 01/11 0700 Reactor thermal power at 97 percent, maximum flow, rod limited. 01/13 2300 Reactor thermal power at 96 percent, maximum flow, rod limited. 01/14 2220 Commenced reducing thermal power for SI 4.6. A.6&7 (Thermal and Pressurization Limitation Startup of Recirculation Pump or Idle Loop). 2354 Reactor power at 56 percent for SI 4.6. A.6&7. "A" MG set out of service. t 01/15 0100 Reactor power at 46 percent. SI 4.6. A.6&7 complete on "A" recirculation loop. l 0133 "B" recirculation MG set out of service for SI j 4.6.A.6&7. Reactor power at 46 percent. i 0200 Reactor power at 48 percent. SI 4.6.A.6&7 in progress on "B" recirculation loop. 0300 Reactor thermal power at 44 percent. SI 4.6. A.6&7 in progress. l 0315 All rods out, rod pattern attained. 0320 "B" MG set back in service, commenced power ascension. 0345 Reactor thermal power at 73 percent; holding for r turbine control valve test and SI's. 0513 Turbine control valve test and SI's complete; com-menced power ascension. 0830 Commenced PCIOMR from 77 percent thercal power. 01/15 0300 Reactor thermal power at 99 percent, maximum flow, rod limited. i

w - (, y s~memw qy .- - v=,,,.x:,- mwsr-mm n ~.r-nmw.- n --:nc .,r c1 -

g, 9 7. - ~ w; u

..o ,m.e ..,,s,..._>< m, ,jy, ~ 6 i 1 Sinnificant Operational Event Unit 1 Date Time Event 01/ 17 1230 Commenced reducing thermal power to scram control rod 10-39 1315 Control rod 10-39 scrammed to "00" for maintenance. Reactor power at 88 percent. 1643 naintenance complete on control rod 10-39, reducing thermal power to withdraw control rod. 1700 Reactor thermal power at 85% for withdrawal of control rod 10-39. 1710 Control rod 10-39 withdrawn to "48" and timed. 1712 Commenced power ascension from 85 percent thermal power. 2100 Reactor thermal power at. 99 percent maximum flow, rod limited. 01/20 2300 Reactor thermal ibower at 99 percent maximum flow, rod limited. 0 1/ 23 0043 Reactor Scram No. 164 from 99 percent thermal power on MSIV closure from main steam line tunnel high temperature. The cause of the high tempera-ture was a steam leak which developed when the B1 moisture separator drain pump discharge line blew out due to erosion between LCV-6-73A and B2 high-pressure heater. 0945 Commenced rod withdrawal for startup. 1345 Stopped pulling rods for maintenance on steam leaks. 1635 Commenced rod withdrawal for startup. 1700 Reactor Critical No. 184. 1805 EHC problems on turbine reset, No. 2 stop valve opens, holding up startup. 01/24 0111 Rolled turbine generator. 0152 Synchronized generator, commenced power ascension. 0544 "A" recirculation pump overspeed manually tripped pump and performed SI 4.6.E 6&7. Reactor thermal power at 27 parcent. 0551 SI 4.6 E.6&7 complete. 0600 Placed "A" recirculation pump in service, pump tripped, received overcurrent alarm, Increasing thermal power, "A" recirculation pump remains out of service for maintenance (speed control problems). 1200 Reactor thermal power at 43 percent. "A" recirou-lation pump limited. e m.- y _, +

V.. vu.. .. f. m 7 7, "..m.o"=w..e"wa - e ~** m V m v ~ ~ e "- %e em" ~ t s.,, eu.we; -e w

m.. o w_m a w _., su

,w , ~, 7 Sinnificant Operational Event Unit 1 Dalg_ Time Event 01/24 1500 Reactor thermal power at 42 percent, "A" recircu-lation pump limited. 2040 Tried to start "A" recirculation pump again, prmp tripped, reactor power at 40 percent. t 01/25 0300 Manual Scram No.165, from 40 percent thermal power, for maintenance en "A" recirculation pump MG set. (Pump failed due to a broken "Heim" rod end within the fluid drive which allowed full coupling of the motor and generator). 2003 Maintenance complete on "A" recirculation pump MG set, commenced rod withdrawal for start-up. 2146 Reactor Critical No. 185. 0 1/ 26 0040 Rolled turbine generator. 0057 Synchronized generator, commenced power ascension. 1300 Commenced PCIOMR from 77 percent thermal power. 01/27 0235 Stopped PCI0HR at 90 percent thermal power due to inoperable trend recorder 47-20. 0400 Recorder back in service, commenced PCIOMR from 90 percent thermal power. 1300 Reactor thermal power at 95 percent, stopped PCIOMR, "B" t ecirculation pump upper guide bearing high high temperature. 1400 Decreasing thermal power due to "B" recirculation pump upper guide betring high temperature. 2300 Reactor power at 89 percent, holding due to "B" recirculation pump upper guide bearing high tem-perature. 01/28 0130 Commenced PCICMR from 89 percent thermal power. 0205 Reactor thermal power at 91 percent, maximum flow, rod limited. 1353 Reactor Scram No.166 from 90 percent thermal power on loss of unit preferred power. 1925 Commenced rod withdrawal for startup. 2231 Stopped rod withdrawal due to problems with sequential events typer. 2310 Sequential events typer in service, commenced rod withdrawal. 01/29 0018 Reactor Critical No. 186. 0305 Rolled turbine generator. 0325 Synchronized generat or, commenced power ascension. 2030 Commenced PCIOMR from 94 percent thermal power.

. -.&=.z,, a, =emnn a c.7,n,wnc,:.,. ~, m. :. ....-g,~~,...- g

m...... w v

,, v. ~~,c v.~. 8 Significant Operational Event Unit 1 Date Time Event 01/30 0400 Reactor thermal power at 96 percent, maximum flow, rod limited. 0700 Reactor thermal power at 95 percent, maximum flow, rod limited. 0900 Reactor thermal power at 94 percent, maximum flow, rod limited. 1100 Reactor thermal power at 93 percent, maximum flow, rod limited. 1155 Commenced reducing thermal power for control rod pattern adjustment to pull all rods out. 1230 Reactor thermal power at 84 percent, control rod pattern adjustment in progress. 1300 Control rod pattern adjustment complete, all rods are full out, reactor power at 88 percent. 1440 Reactor power at 87 percent, reducing for PCIOMR envelope. 1700 Reactor thermal power at 83 percent for PCIOMR envelope. 1730 Commenced PCIOMR from 83 percent thermal power. 01/31 0530 Reactor thermal power at 99 percent, maximum flow, rod limited. 1010 Commenced reducing thermal power for maintenance on bus duct fan damper. 1130 Reactor thermal power at 52 percent, holding for maintenance on bus duct fan damper. 1540 Reducing thermal power to trip main turbine for maintenance on bus duct fan damper. 2005 Manually tripped main turbine for maintenance on bus duct fan damper, reactor power at 25 percent. 2100 Reactor power at 28 percent, generator off line, holding for maintenance on bus duct fan. damper. l 2320 Rolled turbine generator-. 2400 Rolled turbine generator for startup. l l l l i l

w -. _ _ -., s,. 4.ew - m ~,.v.:r_- 7 _ -ww,,,,. ~,,w.m ~ ..- c. -.,,, y.. gl u d ' A %. a,. # : f., ' a t//. .s. _,, tu cvsm.. -3, ,<+. s ..a 4. ja,- j

  1. +

yg. il 9 1 Sinnificant Operational Event Unit 2 Date Time Event 01/01/83 0001 End-or-cycle 4, refuel outage continues. 01/31/83 2400 End-or-cycle 4, refuel outage continues. i l l 9 e I -'MP"'--" -- Ww w-v v='r-"wT w8w'-= e'

vw-www'v-

'-"*w- P -.-ae. e g- -.m-,_m-- y w-m -- --y...-tN re+-- evw e-

sw y-7 y.. .. n,rwmm-w.vmmm.ew2.em-w-m. n s n .v. u. j w., %m e sw - o xy.c -, rs.w._ ~ e mrum.mn +. s, >... ; w ~,n

. y.

^ 10 s i Sinnificant Operational Event Unit 3 Date Time Event 01/01/83 0001 Reactor thermal power at 96 percent, holding for change out of oil filter on "A" reactor feedwater pump and turbine control valve test and SI's. 0200 Change out of oil filter on "A" reactor feedwater pump and turbine control valve test and SI's com-plete, commenced PCIOMR from 96 percent thermal power (control cell core). 0630 Reactor thermal power at 99 percent, maximum flow, rod limited. 2325 Reduced thermal power to 95 percent for turbine control valve test and SI's. 2355 Turbine control valve test and SI's complete, com-menced power ascension. 2400 Reactor thermal power at 99 percent, maximum flow, rod limited. 01/09/83 2123 Commenced reducing thermal power for removal of "B" reactor feedwater pump from service for main-tenance. 2400 Reactor thermal power at 78 percent for maintenance on "B" reactor feedwater pump. 1 01/10/83 0700 Reactor thermal power at 79 percent for maintenance on "B" reactor feedwater pump. 1100 Reactor thermal power at 80 percent for mainte-nance on "B" reactor feedwater pump. 01/11/83 2300 Reactor thermal power at 79 percent for mainte-nance of "B" reactor feedwater pump. 01/12/83 0256 Reactor Scram No.109 from 78 percent thermal power, when 3A and 3C reactor feedwater pumps tripped on indicated high vibration. The water level dropped to the low-low level setpoint, and the MSIV's closed. Three "B" reactor feedwater pump had been removed from service for mainte-nance. The vibration probes had been disconnected from the cables. The cables for the six Indikons (two per reactor feedwater pump) run together in a common raceway from the turbine building to the control room. Due to the small signal generated by the probes high impedence, low capacitance co-axial cable (RG62/U) are required in order to eliminate electronic noise. A different type of 4

my-am -., y.--w.;smym,.vwa-e m:n.wm,lw m.,v,egw - , r.m m. ~ - g .- O m s -. y;- q.a< ;., g y.. n.. n n.; ra.; w + +; w w

s. w,

4,x. 3., u 11 Significant Ooerational Event Unit 3 Date Time Event (Continued) 01/12/83 0256 cable was used when the system was installed (unit 3 only). The disconnected cable grounded on con-tact with water in the feedpump room which gene-t rated an electromagnetic field in the grounded cable and in turn generated noise in the other five cables resulting in indicated high vibration and reactor feedwater pump trips. Unit remains down for maintenance on turbine steam leaks. 2325 Reactor in cold shutdown for maintenance on tur-bine steam leaks. Maintenance also continues on reactor feedwater pump Indikon system. 01/13/83 1830 FCV 74-53 tagged for maintenance. 01/14/83 2150 Work on reactor feedpump Indikon system complete. 01/16/83 0010 Leak in "D" residual heat remover (RHR) heat exchanger. 0014 "D" RHR heat exchanger out of service for main-tenance. 01/20/83 1700 Maintenance complete on FCV-74-53. Maintenance continues on "D" RHR heat exchanger leak. 01/29/83 2240 "D" RHR heat exchanger repairs complete, holding unit offline because of inoperable "C" RHR torus suction valve FCV-74-12, and inoperable HPCI valve 73-5. 01/30/83 0420 RPCI valve 73-5 operable, holding unit offline for repairs to FCV-74-12. 1230 RHR valve 74-12 repaired, RHR Loop I operable. 1145 Commenced rod withdrawal for startup. 1438 Reactor Critical No. 123. 1820 Ultrasonic test (UT) west header monitor equipment malfunction alarm received, stopped rod with-drawal. 2015 Commenced rod withdrawal. 01/31/83 0100 Holding up on rod withdrawal due to problems with EHC and computer. 0445 EHC problems resolved, turbine in chest warming, holding due to proolems with computer. i

~ .wwwmsnmwwwAe-r, em e m.< m,- l.Iv,.- m,8 , m., > = - -- , g.7 , r-t .~ .. ~.. ; ,.x. ~ 12 i Significant Operational Event Unit 3 Date Time Event 01/31/83 1441 Rolled turbine generator. 1630 Synchronized generator, commenced power ascension. 1800 Reactor thermal power at 32 percent, holding due to turbine vibration. 2400

Reactor thermal power at 32 percent, holding due to turbine vibration.

4 r

4 op y yr . m,q =s==<y nenwapm:.,ms py r ,,.r.4A, y @ p n g w p o,n n-w e m y w sy m y r y p 3.,. 3, p p{..p e...p. .,-. p,.. , y S v;s..-asse.. , g.p;, 7 4,# < < 3,q,$gm.g pz $.. j 1:

7.-

13 , y-:,..p-g AVERAGE DAJLY UNIT POWER LEVEL .h-....,,.-. DOCKET NO. 50-259 UNIT B ret-. e verry 1 DATE _2-1-83 COMPLETED BY Ted Thom 205/729-0834 TELEPHONE MONTH Januan i DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe-Nc ) i 1078 17 1027 2 1065 1066 g3 1065 1066 3 39 4 1067 20 .1065 5 1064 21 1069 1063 6 22 1051 1056 21 7 23 8 1054 24 301 9 1046 25 33 10 1044 654 26 1042 gg 929 1039 543 I _,

s

~ g3 1031 709 1010 g4 9t,1 is 820 31 634 I t, 1071 INSTIRTIIONS Oie t hn f ornut. h u tin.n cr. ige.j.nn .a..t a..a c. > v; n, M V.. Ni i t.g,, h.: 2. .i. ,..neti. ?!.e tierest ula A en ca.. o t. l (0.'77i 1

{f]']"p<mee.'-Nme-g pgppyygrg,. hhu E]!:.M, i.((( '?;Uy.[;j.;[ ._n. g t .v. .3..g.g _.; p s-14

s

{ e AVERAGE D.ulY UNIT POWER LEVEL i,i DOCKET NO. 50-260 r 'l UNIT Browns Ferry - 2 2-1-83 DATE COMPLETED BY Ted Thom TELEPHONE 205/729-0834 MONTH January i DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) i MWe-Neu -6 -7 I 17 2 -7 18 -8 -7 -8 3 39 -7 -8 4 20 5 -8 21 -7 6 -7 22 -7 -7 -8 7 23 ~7 -g 8 -6 -8 9 25 10 -7 -8 26 -12 -7

g

-11 -7 l, 3 -13 -7 13 -12 -i 14 10 -8 -g 15 16 -8 On thn I iriiut,!st ti... i m., t..j r.,,,,,. ,.,.,t.

..g,

~ ' I " I,' ' ' S 'lIlll ' '"t t h. I ' * :llpul c t e, i I IC IICJfCst %l pile tia, 4,g g e -~, a e. 4 I

hhN d)M,P I D $ N h h h h.h.. [ 7 ' 'I2~"7'"((j[EyMf?[$;I!I4 l i ' 1 15 ?, { 3 .WERAGE DAJLY UNIT POWER LEVEL DOCKET NO. 50-296 UNIT B: owns Ferry - 3 2-1-83 DATE C0\\tPLETED BY TELEPHONE 205/729-0834 MONTli January DAY AVER AGE DAILY POWER LEVEd DAY AVER AGE DAILY POWER LEVEL (Mhe-Net) iywe.Neti 1 1062 -12 37 1065 2 ,3 -13 3 1062 19 -14 4 1068 20 . -13 5 1061 -13 3; 1065 -13 6 22 -13 7 23 1063 3 24 -12 1041 -11 9 25 826 -11 10 26 g 822 -11 7 86 -11 y; 5 13 -14 y -I; 14 -12

g

-1? -11 65 15 ti ~II 14, INSIRUCIIONS On tins t.it uat. h.t s he er.re,, - e. n : +,.. a '. u l n '.:','.;.% i,.i c.i. l; a n i,; 1 ...e .n,,, c. ,.n.i., t h1 tic.irest w ht >lc n 2.tw so '77 > I i 1 I

W- 'Mi'f,7,My m... w r"8L hn-w w.T**,w*'i*Wy&m'7D*H'l""TWMfRT*n'y"**: m., om., t g p,, 9lal'y t' ~T ' ph,0.M,. H e, q. k. m.. ysp y n p ip,... 4.g... h Im... -..,.. t. 4 m u...i y, s.. @r,io. t*r,4N q+A. 3 s

g 3,

g 1 '. I J [- d e:.i Q', d % e L .b -> 7 -o.. .s. l OPERATING DATA REPORT DOCKET NO. 50-259 DATE 2-1-83 COMPLETED BY Ted Them TELEPflONE 2n5/729 n834 OPERATING STATUS s

1. Unit Name: Browns Ferry - 1 Notes
2. Reporting Period: January 1983 3293
3. Licensed Thermal Power (MWt): 1152
4. Nameplate Rating (Gross Mv ):

e

5. Design Electrical Rating (Net MWe): 10652 1098.4
6. Maximum Dependable Capacity (Gross MWe):

1065

7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacitv Ratings (Items Number 3 Through 7) Since Last Report, Gise Reasons:

N/A

9. Power Lesel To Which Restricted,If Any(Net MWe): N/A
10. Reasons For Restrictions,if Any:

N/A This M'inth Yr.-to.Date Cumulatise

11. Hours in Reporting Period 744 9504 74,546
12. Number 0f ilours Reictor Was Critical 698.55 E.773.29 48,088.09
13. Reactor Reserve Shutdown liour, 45.45 567.56 5,782.76
14. Ilours Generate r On-Line 679.45 8.t>49.40 47.079.57
15. Unit Resene Shutdown llaurs O

C 0

16. Gross Thermal Energy Generated l\\1% H t 2.0%, E30 26, W,927 133,839,834 17 Grow Liectrical Encrev Gener:ited t Mulb 033.740 F,792,C+.a 44,084.510 15 Nct i lectrical Encrey Gem r.ited iMhIh 0g2'>'

r 6 1' 6 3.' 915 * "' )6 e o 19 Unit Senice im f or 01 3 9' .i l. hadahihty Factor 91.3 63.3 9 ,.0 mt

21. Unit C.ipacits Factor (li ina MDC Net I
    • . 0 W4

{3.9 s _h'

  • U" 2.'

ll nit Can.iory I actor (L'sme D1 R Net e 8,/ E.> +.i

23. (! nit I orced Out et !Lif e 24 si.utdowns Sch<dnica Our Seu f \\louth. t I s pe. liite ":d ihnai m i of i.ul.'

~ 23 II Shui llow n \\ t I nd Of R.*pos t i'erned I sismated li ste of virinp 2h I ints li. I of ht itns I hiur to t nunn is i. l ()peration ) 1 nre a. \\ s.nch d IN!!! \\ l. ( Ril R' \\1 ll % INf il \\l. l~l.1 C I Rit Ili LO\\l\\fl lit I \\l. Opl R \\ llON g a t~,

-*m. 9 ~: %. syr=r+ w p =+= - g p mynin.,2 n s.hu, 4a.n.. e ud;Qn,9 5 p, ; >y;p *m.mywwym y myl ',;;yy ;; ym. ~,. g yn am . 6 g g.cp. 4 y a ; p p g g g v ~ 17

l-t OPERATING DATA REPORT DOCKET NO. 50-260 DATE 2-1-83 COMPLETED BY Tod Thrm TELEPIIO.NE 205/729-0834 OPERATING STATUS Brom kny - 2 Notes
1. Unit Name:

.. Reportmg Pen. d, January 1983 o

3. Licensed Thermal Power (51% t): 3293 1152
4. Nameplate Rating (Gross MWe):
5. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Grow MWe): 1098.4 1065
7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

N/A

9. Power Level To Which Restricted. If Any (Net MWe):

N/A

10. Reasons For Restrictions,if Any:

N/A This Month Yr.-to.Date Cumulative 744 9,504 69,487

11. Ilours in Reporting Period
12. Number Of Ilours Reactor h adritic:.I O

4,846.51 43,293.47 O 203.00 13,064.82

13. Reactor Reserve Shutdown llaurs O

4./ia.30 41,'Ji).43

14. liours Generator On-Liae O

O u

15. Unit Reserve Shutdown llours P

13.827,550 120.480.340

16. Gross Thermal Enerey Generated (5thil; 17 Grow Electrical Enerev Generated f \\ luth 4.592.20')

4C,024.00M U 0 4. 4 3 0. ".'" 3S.873.D75

15. Net Elettrical 1.ncrgs Generated I'.*Wil.

C 5l 3 60.4 19 Unit herwe I act r U 50 3.: DO*^

20. Unit Aui!.ibility Factor O

4+. 0 E,2, 2

21. Unit Capacity I actor (LNing MDC NeO la.O

'i2. 5 22 Unnt Cap.ia!) l' actor IU.ing DElt Net) U i

23. Unit Fment out. nee R:ae 0
5. 5 27.I
24. Shutdowns Schedul.d ther Neu 6 Momin : i s pe. D.ne.and Durati..a of I.i.h i 25,11 Shne D.mn \\t I nd 01 Htport Perin I I stunated D dr of Startup 3/7AC
26. l'mh in leg Status (l'rior to rununeraal O tration!

I nicc.iq \\cioned i INIl l \\l. ( Mil lf Al. ll Y INill \\l.1 I I CIRR fIY f O\\1\\11 RCI \\l. Op!'R \\ IlON top 7)

c y,a+. ..we.,,&%., - 7.r w moym.m ms.q,s $ g yk % p%a*k)rd.Qgse[ gI se ift.II@S4htMJ4@yd*C/pdtijgkl icy: f f 10' L 4'N ljj f-;f Nptlh4j.4 g f m d.. F . m i t y 9.n. :l y n. . a : 0.. y 9 pyp.-. yi 7l 18; s' q v .s 4 = .4, OPERATLNG DATA REPORT 1 DOCKET NO. 50-296 DATE 2-1-83 COMPLETED BY Ted Thom TELEPHONE 20s/729 0834 OPERATING STATUS Browns Ferry - 3 Notes

1. Unit Name:

January 1983 o .. Reportmg Pen. d: 3293

3. Licensed Thermal Power (MWt):
4. Nameplate Rating (Gross MWe):

1152

5. Design Electrical Rating (Net MWe): 1069 1098.4
6. Maximum 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: N/A

9. Power Lesel To Which Restricted,if Any (Net MWe):

N/A

10. Reasons For Restrictions,1f Any:

N/A This Month Yr.-to-Date Cumulative 744 9,504 51,912 i1. Ilours In Reporting Period

12. Number Of Ilours Resctor Was Critical 300.30 5,445.60 37,912.58
13. Reactor Reserve Shutdown llours 443.7 1,674.32 3,815,85
14. linurs Generator On.Line 274.43 5.297.71 37,048.49
15. Unit Rewne Shutdown floun 0

0 0

16. Grow Thermal Energy Generated (Yh }i; 793.830 16,27's,322 110,134,942 17 Grow Electrical 1:nerev Generased f tl%fl>

279,800 5,321,400 %,319,590 11 Net Electrie.it 1.nern Gentrated iMbil, 2 t> 7, Ps 4 5, m,';2 7 D, si, W l's. Umt $crsite I actor

20. Unit Asailahihtv i actoi M9

->i./ /1.4

21. Unit C.yacitt I actnr iUsm; \\iDC Nc0 33.7 5!.0 63.8 22 Unit Cap.icirv i actor e thine lil:R NeI, 33.7 5I.0 63.8
23. Unit l'orced out.c.c Itate li.L '

2 '._W .l_1 1

24. Shutilow w schedul t's her Nest I, %nths i i s ne liite.and iler itnio ut l.1hi

~

25. If %m ib w n \\t I nil Ol' Report Ptrio.. latimated ll.ite of startup.

2h. l nie, In i est St.ilus tl'rtur to ( onnnerti.il tlperati mi I ut i.i s \\ s lucsi d INill \\ L Cl!IllC.\\ t 11 Y INIIIAI I'll CiHlClIY CO\\l\\ll IRI \\ L Ol'l:R \\ lif;N (.). g g q

... n :, I 9 5 73 s.4 -m DOCKET NO. 50-259 [_q UNIT SilU1 DOWNS AND FOWER REDUCTIONS UNIT NAME Browns Ferry - 1 , __g DATE 2-1-83 , W, COMPLETED BY Ted Thom REPORT MONTil Januarv g , g t' i.t .U -.7 E M4

i, 5 i.icensee

,E -t, E9., Cause A Corrective 3 i-r L I b'" i 5? 4 Is$ Event G? $ ~$ Action to 2d 3E jig Report r (A 0 y' Present Recurrence ~ 6 --5-5 253 1/14/83 S B Derated for 81 on 1hermal and Pres-surization Limitation Startup of f.) ________. 1/23/83 __.11 3 Recirculation Pump on Idle Loop M 254 F 25.15 Reactor, scram due to main steam '"j tunnel high temperature fi 255 1/2 /83 l-21.95 B 7. Reactor scram for maintenance on DJ recirculation pump M-C set. 'I[ 256 1/28/S3 F 13.53 11 3 Reactor scram due to loss of unit 1s ~ o geferred power e 4 257 1/31/83 F B Derated for maintenance on bus duct %j p fan damper. Turbine manually tripped for mainte-258 L/31/8i F 1.92 H + nance on bus duct fan damper. No M reactor scram. 4 , 7.) ".e y . cy,

~ a e!.

n' g __L_ 3 4 . q f I."s J .R ea u.n Method: Exhibit G Instructisms -r$IQ 5 5 he t J J .\\ !.rnement !.n! ne t ! sp un) I. Manual for Preparation of Data 8 .32Q l' il.nnten m.:e or i en 2-Manual Seram. Ents) Sheets for Licensee i ' l i>i,,,g ( Rel ocl.n g 3-Automatic Scram. Event Report (LER) File (NUREG-J3 h Repa!ito 3 Res n i.n., i 4-Ot her I Explain) 0161) iQ l Opeun. lumn v 1 ta r nse I samination '.U$ I thnmntut r.e ' 5 (, Opeunonal 1 i n. t I spl.ca n Exhibit ! - Same Source

i l'*/ 77 )

It Otha 11 splamt g 25 9 ,.ab g

_ rt a 49 -y 'i UNIT SilUIDOWNS AND POWER REDUCTIONS DOCKET NO. 50-260 UNIT NAME Erowns Ferry -2 + DATE 2-1-83 RLPORT MON'!Il January COMPLETED BY Ted Thom .Q TELEPl!ONE ?ns/7?o-nau J:- Ji.F. ..dk:h -.: a ~l. Y% u 5->2 5

?)

y T g"3 y" p " ', 36 5 75y t.icensee 5% L Cause & Corrective -n 2.f j -@ 5 - [? 0-Action to 3e I^ct'l a Report a mU sL Prevent Recurrence -..tid 2:

s e

u C ,,' ;;;g jQE WE .. $ 1 a 243 1/1/83 r, 744 li 2 EOC-4 Refuel Outage Continues

k' a

a;r, l4 !-t .3 w,. Q* d'. ~

]

64 . L$ ,a ?.4 ____..____[

'f f 3

4 '*:. h+s y I i-. It. n Method: Eshibit G-Instructions - p'; y 3

5. '- ' u 1

\\ l pupat nt !.ul or t i

  • rhin) 1-Manual for Preparation of Data

..- :q It it. net caince i,r ic t 2%nual Scram. Entr> Sheets for Licensee ( n tochne 3-Autorn:itic S ram. Event Report (Lf Ril:ile INtlRI:G- ,7~2]

1) IN m!a:ory P.c stricua 1 Otiict (Explain)

O!611 ~L ! Opelator Tr.iimnc i t t. cose i xainination Tj f h!nunntrati.e 5 (s I)[h'laflofiaI i t rol t lI A j81. lid ) Exhibit I - SJine Source 1 17/l ll-fi her (i splain) ( t 4 9 .e -=e e e 4e =%

, ;+ n ' N] A UNIT NAME Browns Ferry - 3 . I. 50-296 UNITSilUlDOWNS AND POWER REDUCTIONS DOCKET NO. '[. DATE 2-1-83 _; j REPORT MONTil January COMPLETED BY Ted Thnm J TELEPilONE 205/729-0834 ,g a.n 'I. 4 !t k. ,a5 i =_ 5M i.scensee gg c Cause & Corrective ie r N' I '." 7 5? 4 is5 Event a '1 $.E Action to ill -5 E 5 55: Report e N0 5V Prevent Recurrence q' j u C q.g {~~a R 122 1/9/83 F 11 Derated for maintenance on B reactor y3 feedpump tj 123 1/12/83 F 469.57 A Reactor, scram due to false high vibra- >j tion indication on 3"A" and 3"C" i reactor feedpump. Unit remains down for maintenance on 3"B" RFWP Indikon ] system, turbine system leaks, FCV p '.$ ' 53, "D" RHR heat exchanger, m? ,ip. ..y i ? .____________[ l N -4 I 3 4 'l I I n. - I l i r....o. Method: Exhibit G. Instructions 'N N 5.In !u!M i !.pipment !.nla,e i r sp!iin)

1. Manual for Preparation of Daia 3.

1: \\ taint: :unce i,r Ic.t 2-Manual Scram. Entr> Sheets for Licensee -3 ( R.,f, H n e 3 Autom:itic Stram. Event Report (LER) File (NUREG-. 7 IL Frcola Ju) l'est imo.n 4-Ot her i E xplain ) 0161) i Opeutor luining & I o "use i samination j i.%Jin nnerati.e 5 j G Operational I iror iI spf.n.ti Exhibis 1 - Same Source t'o 77 11 otherti spl.nn) += g6 4

1 a ouvwa e una nvwwu, a m..a w.. T~ CSSC EOUll"4ENT MECHANICAL MAINTENANCE

SUMMARY

Rf '[ For the Month of January 19 83 g g ~ ~- EFFECT ON SAFE ACTION TAKEN DATE .SYSTD1 COMPONENT . NATURE OF OPERATION OF CAUSE OF RESULTS OF 'IO PRECLUDE i,j ~ PAINTENANCE THE RFACTOR-MALFUNCTION MALFL'NCTION RECURRENCE ' o -4 12-30 ' Radiation ~ cam,90-256 air Icak none faulty o' ring & charcoal holder Installed o' rings og, Monitoring front cover out leaking air holder 6 straighten:' of adjustment front cover ,,( TR# 216800

1 C

1-17 CRD directional module non-none faulty direc-module would not replaced directions; control valve functional tional control move control valve. id FSV-85-40A on valve TR# 291786 I 1-module 10-39 t,; 1-21 RHR valve 74-67 slow leak none slightly loose slow water leakage tighten packing h TR# 340047 F l >.5 fr.1 1-21 D/G B air compress air compressor none faulty high air compressor repaired head $1 D/G 1C malfunction pressure unloade blowing air pressure unloaderig r j & head gasket replaced head gaske; high pressure w 7,1 TR# 310160 N FT gy .i 1-21 RHR FCV-74-52 valve bolts none bolt under valves not set at tightened & torqued FCV-74-53 out of adjust-torque setting proper torque to 680 ft.-lbs. j I FCV-74-66' ment TR# 242302 -s FCV;74-67 j 7-4 1-20 D/G air. compressor air leak none blown head leaking head gasket replaced head N

  1. 2 D/G 3D gasket on 2nd stage gasket

"- { m TR# 313350 3 -; v. 1-261 RHR FCV-74-77 bolts not none unknown valve bolts out of torqued per,MMI Sif FPC. pumps properly specified torque TR# 297005 3 ]. :. '. torqued value j m. 1-25 RCIC & FCV-71-37, 38 bolts not none unknown loose valve bolts torqued 71-8, 37, 3 l' LFCI & 39 & 8 properly out of torque specs. & 39'to 245 ft.-lbs FCV-74-47 torqued 74-47 to 846.70 ft. Ibs. ~ TR# 297281 l B

7

.M ... m c.:

  • j f a'

.,m n ~- ~A n

1 a,,wmw, a.m. .o.... e- .....~ . '. 'HECHANICAL MAINTENANCE

SUMMARY

O CSSC EQUIPMENT T.Z ~ N. '.

a..,.

. C.IC,. .. _..Ti.',D ~ * . [For the Month of. F January 19 83 yz v- - . ~.m y -.. W.. n-.

e. m. _

1 u. EFFECT ON SAFE ACTION TAKfD . y f.. 4 ySYSTEM COMPONENT NATURE OF. OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE ' iMTF, ?1 HAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PECURRENCE zy. valve-3noper-none* keyway on shaft valve not functioning repaired drive pin 1'09" Core Spray HCV-75-29 Qq 'j, J- =.g. able was -found to be properly & keyway j 5 4'*W. worn & drive pin TR# 31113'. 4 7 r broken E.;a. i t T.y.. h r

a. ;.

+4 o .*.-y. .j %... g; w plC3! L j&. . n r#.. ~ sea wf) %.dC.T.* .{

  • s 4

p 4 r.u ' ?. ~. (f +. DC. T.E..:. w.e,..-

  • gr

.u..* % g e. .e q dy - x. E.

    • '4'

.;. * + 7. N,},*;3 *

.rf N

i

  • [.=,,'-

g%. p '.~4 g. W e, g,r i i .i - V -* f~

~n.m.

s(

  • p Fav yu f.ir:-.1,. -

.4't* [ *_?l e'.*,..un-r., ,: a T.'**"- ~

  • k. M-W5 L;. ;T.

. 4,e. -,, -

n t-~ ~

.M~ %';.J'*: ~.w*.\\h ': M t K * ' r.. .A-e.m vb. 7 ~ b.:

  1. e.-.A 4

f*h ,,.w" t-* x,. +7,yg .. 7,'?

  • .*'7

._.,..a-- i, ~4- . c. 4 - y> p**.,.t t.* 1 ,.oe.~.. s _, L

_.6

,.G . & si . py ~- t..w g .y, s. gg>, g i,:w.h. ;y- +, u., F ,~...-~,.-;e' , v. :%,..,,.,

v. n.~, r. : --

p-~.a.1 (.. i a*h s 4 1.ad 1.. }. w' a, z,. .+ fdgk . 'i J.+' _. r I D..#...$' ',, ' M. _. TM*Dr m> g a.. $ %_** [.. a 1. 0 ,y. - re,- i Qn 3 * ' ; ;. - ~ -,

  • A

-A8'4 e .m ..t i s. + y'g_; u.; . -se- .w- .y r

", Q. ;,*. y e.,

i .** p^n ,, G.,, ;;..~'*i,... < *r - '.. * - ' ? P;'.-*' . d L "' 4

4. W 3,[j.4.
  • '.;( ; *

(U.g' fj; n,' ' - l.5}7 ~?% '~ - e A.rs .b* 1 *a u.+.c.., m... e j u ,y

  • /

g g

  • ,n.>, *-. j,.:. -

.a.. 9- ' s * ,n... .e 5 ,*4 ?- + .w. .'*e.e- .3 a g.J.M I . y>'" .7.-- [ g

  • ~i 7,.

m, g 9 N. D u.m . q, m.. _o 2._ g. Mh' Z*" '7..-. '. M ~ ~. ,((. "l*.Y I [* 2. ..,. -...M '.~. ... -. = ~.m,. ', b.~s,.,s.s >.y -.- ~ e.y g .m ~

    • ~4 y

&4 8H-3 .,w .w a .m. kI. CSSC EQUIPMENT 'NECHANICAL HAINTENANCE

SUMMARY

%': s For the Month of January 19 83 . 61 ;, ; [. n' fc.,i. ~ ~. l7 b i EFFECT ON SAFE ACTION TAKEN tt:

SYSTEM-COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF

'10 PRECLUDE t MAINTENANCE ' DIE REACTOR MALFUNCTION m LFUNCTION RECURRENCE kd 3., Radiation CAM 90-256' air leak none. faulty o' rings air leaking around replaced o' rings O 7%.' Monitoring particulate filter TR# 283603 s - holder j

  • C '

C I 112.' Reactor 3B1 shu'tdown air handling none bad bearings air handling unit replaced both l %gt Ventilation board room air inoperational inoperable bearings handling unit TR# 326S06 ~ Lhwr. te'. 12 HPCI HPCI gland steam leak none head gasket seal gland condenser replaced gasket 3 ]$4 seal condenser blown nonfunctional TR# 340819

w...

'l 07.. RHR FCV-74-74 valve inop-r-none clutch gear motor runs, stem does replaced clutch ll 4, erable broken not mpve gear i%. TR# 275594 .0% %i9h HPCI FCV-73-3 valve inop-:., none packing remove valve inoperable insta11ec' new I.E.~L' ,( erable 1l L y } ~ -Y for repair of packing to >,%.$P seal ring TR# 297268 2 -l 14 vL' 'p205: D/G thermostatic, replace oring's none faulty valve valve nonfunctional. replaced thermo-

yl$@

valve

.U.

& element., static elements, A en b assembliesM;.' o' rings & body 'C khb.'~N,.. gine lY ).T $ gasket sc, M ?... 2 37- {.1* f - ; TO P,3 !,% 46 i TR# 297201 (/G #g. f Mv - 3 : Q97..., f b: Qf, Ff = lube oil' coupling [ 9 46f worn flex spider coupling not changed flex ,~D none

  • NE circulating-nonfunctional'

~ grammet supporting pump grammet iTs pump couplinh properly TR# 342313 6.; E a~ D/G A - @4.,,% -sy ~' /* -~+ "e _gg

p-
i. e a a

r.- 6 wat2r,aleak'%' a FCV-75-80 #[i ~^~ none 49 b'onnet bolts bonnet flange Icaking tightened bonnet Core Spray f; h.. loose & in need bolts to 234 ft.-lb;

m. i.i_

. _ _. [ 1 a (

g f of torqueing slowed leak to less
.c

~.y.s than 1 drop per min. TR# 297295 P. 4',. m. 8 s. -*-D ,-Y - f. T.- f _-. C 2- ~ . --~ - g n,_

w - 1 & Cor. hon Page 3 BROWNS FERR* NUCLEAR PLANT UNIT 7, !!F E"Sil. hJ ELECTRICAL IIAINTENANCE Sl[!M RY ^EE" CSSC EQUIPMENT 9/29/82 z NU For the Month of January 39 83 W& p Effect on Safe Action Taken [ '.s,. Nature of Operation of Cause of Results of To Preclude D . g r. a System Component 5fntenance The Reactor Malfunction Malfunction hecurreace t, 12/28/82 Diesel Central Annuncia tor None Bad annunciator Annunciator panel Replaced.the bad {i': Generator Diesel infor-panel inoper-panel (XA Inoperable. inverter, annun-yN mation center ablo. 41A) inverter. ciator panel op-f2f". annunciator erated properly. pg panel (XA TR 6339220 41A) inverter i - for D/G "A". . pc ,p 'r :;.

1/1/83 Air Con-

"lA" Control "lA" Control' None Bad compressor. Purge unit inoper-Replaced the bad. 4-ditioning bay chiller bay chiller able o'n "lA" control compressor, purge , {)l~ (Cooling-purge unit purge unit' bay chiller, unit operated Heating) compressor, inoperable. properly. w" TR //277510 ?1.- . Wy-an -. !1/,4783 Air Con- "lB" Control '"1BW Control' None Bad flow switch "1B" Control bay Replaced the bad ditioning bay chiller bay chiller (FS-31-6). chiller inoperable, flow switch and M.7 (Cooling- ' flow switch inoperable. performed EMI 60, GW- - Heating).. .FS-31-6. returned control n.n .ct: WE., -- u.?~ 327;. service. g ~ bay chiller to. e. ~,~c -s p-u TR #277519 r

4..
1 r r;.,,

. l y.r;en. ..;; r %7 .{. 9 ,. i g.g-2.'lh e s 5 ' Frt ;,: SS? %.:-e: ry kb-M ? .,~ ? l:h W :.; - L.g,? "T5 ?~ gv;m -~;

u.- 4 BROWNS FERRY NUCLEAR PLANT UNIT 1 6 Cor/ mon Pa p 3 BF CISIL 30 ' L,4.. -*;. ~ '@r '. i;;.; ' O ELECTRICAL MAINTENANCE SUN &\\PY Appenofy. B W CSSC EQUIPMENT' f;.., ' 4

.r.; w ~ '.

9/29/82 n -- , J.

g.. M. -. r:.d...,, '

=,. - t .. u..c.

L 3

.For the Month of January 1983 .- : -v g. -m 7.f._ g. n Effect on Safe t Action Taken .g 7 -Maintenance The Reactor Malfunction Malfunction Recurrence j Nature of' Operation off Cause of Results of Ta Preclude hDte. System ' Component lirr.b l @Q /13/83 High-Diesel fire _During the 'None, the CBl and CB2 were Diesel fire purap Reset circuit 6 Pressure pump. performance of diesel fire in the "off" would not start from breakers and the Fire- -SI the diesel pump could be position and panel 9-20. The diesel fire pump 71:1 Protec - fire pump fail-started locally, the system necd-fire pump could be " start" circuitry g*d[_ .2 tion ed to scart-eledtric fire ed to be reset, started locally, operated properly. 4,f ; from centrol pumps were TR #340015. Igg.; room panel operable. h" 9-20 (HS-26 ' k 106A1). .A C O. L - .M- {1/20/83 4KV Shut- : Contact 2-2C A wire on con-None, contact See nature of The function of con- ,The wire to con- ', F. 3, h, -.? - down 4 circuitry of tact 2-2C of 2-2C of relay maintenance. tact 2-2C is to trip tact 2-2C was re-4 K,M y . lay 81-6 in 81-6 caught in effect on the er 1612 to shutdown transfer relay Boards *.': transfer re- . transfer relay '81-6 had no normal feeder break-paired and the wm and Buss-

$ a-. '

res j4KV; shutdown the compart-control func - bus 1. With the 81-6 returned to

ty (
bd.'D.

merit door . tion of shut-damaged wire, con-service. !k, 1- .+n hinge, shorted :down bus 1. tact 2-2C would not TR #244975 -Q1p >. to ground, and have performed its Q*-' -g; Q burned into. a-function. < MW:t GU*Jf;.

ff{b can also be tripped

'j NOTE: Breaker 1612 4 gy W.Sfg* - A y* .j.)., .~ _ j; by overcurrent . :.h..- - - - 2;.4.- g"1 g. -w. re1ays. m 4 J -I Q,,., %.,. - - ' + - .,M .'.s? - F4. i v. H I $1T f. ~ ~ .,L 7 n~. m M

yQ"ih.
2. '

'*"._ p. _n., .d,t. W4 f C l[ * '. '~~

& ~

l W G.* , m'.... z- .f $ g e 2.. .? .4-s y gp p' , $+$E YbkN-.- = E A4 . w.a w.

w. -

n3 BROWNS FERRY HUCLEAR PI MT UNIT 1 & Co$nmon Page 3 [, L'. TF tJISIL 30 r h '.. 9/29/82 CSSC EQUIPMENT 1 ELECTRICAL MAINTENANCE SR5 MARY Appendix B g.6..;...* '~ f.-b For the Month of January 19 83 Q?k m.- - w.. Effect on Safs u. Action Taken W. ? ^ Nature of* Operation of< Cause of Results of To Preclude m kDItitl' I Syhtem ' Component Maintenance The Reactor Malfunction Malfunction Recurrence '/23/83 Fire Pro-Supervisory Received a None Undetermined, Lost power to some A patrolling fire

.# r,.; ;,,

tection circuit for trouble alarm trouble cleared of the 16 detectors watch was estab-p[y;g;*,,. h,;;;.. ' zone 14 smoke on XA-39-119A2 while trouble in zone 14 on con-lished, troubic pf detectors panel 25-325. shooting. How-trol bay elevation shooting began control bay ever detector 593. Battery room (verifying proper ,ST.7 elevation 593 XS-39-104BM was

  1. 1, battery board connections) and t,

his found to be room #1, unit pre-the problem 8'*fl8:' loose frou base ferred MG set room, cleared. Zone 14 [ ~ and a probable and RPS MG set room was returned to khE; ,.4 cause of failure. for un,it 1. service. A mount-Aq ns... p;.7 - also poscibly a ing bolt was re-gG loose connector, placed in detector hsL XS-39-104,BM and V' f Q

  • ; ~

2: 0;.y the detector Qidc 1 t tightened to ba.se. mm.. m.. %.m.. TR 9340088 w A y TR #225268 u.. gw(; il-- LER#BFRO-50-259/ i ?*L% -~ k' &~ w % =' a ;+ - 8305

. -.;;;.
er

. -w r.

  • ffT; Q^ W.-

"T& % q.,. ,~ 24;& ,.g.;. L.'~ g _a u*~' y;, d't.'

  • J 7,

i.^. -.. 17 wr

my.

1: - M *r. ~.s;

,~ p g:,.;._

n p, ' Y'

  • r'

, ' ', '..[ 1 s%. , i h '... - _~--v- ._.Q'~;;3 ~--. r .,N;I ~~ ev.. f :- k:,.. I'ihN...QM; Y l.h. ,z, v O ; _, ,= e . ! d. w

  • '" 5 *.'

M.- 5!. ib$2-l =E4:$Q ' Y-m.., a,, n~

f..d 8 3 h. BROWNS FERRY NUCLEAR PLANT UNIT 2 .a l l .,,.,) a yt b* CSSC EQUIPMENT ELECTRICAL MAINTENANCE SUd!ARY A;'pendix B rh 4 u p., 9/29/82 c. tz M xn _.. f-- For the Month of January 19 83 U?y ~~ hI@. g Effect on Safe Action Taken h.y,,

  • y Nature of Operation of Cause of Results of To Preclude StDars System Component Maintenance The Reactor Malfunction Malfunction Recurrence EA:..

Q. 1/16/83 CRD Insert sole-HCU insert None, unit in Loose connection Insert solenoid'on Tightened loose b ;. noid on Hy-solenoid not refueling on (Insert) IICU 30-27 inoperable connection, sole- ' g.g draulic con-operating on outage. solenoid coil. noid operated 9f trol unit insert signal. properly. WG 30-27. TR #339978 %E 5/29/83

RHR, HFA relays, Relay coil re--

None, the re-- Failure of lexan Relay coil retainer The listed relays ih Automa-10AK15B in tainer (lexan) lays were coil retainer spools cracked. were replaced per yg tic Blow-panel 9-33, spool inspec-operable. spools. Ref. NOTE:,The relays SEMI 37 and re-g.y dowry HPC1 2E-K21 in tion. HFA Relay Coils were found to have turned to service. ,;1p-e and RCIC ' panel 9-30, Service Advice cracked coil spools TR-#179933 ha 23A-K13 in PSM-721-152.2 during inspection. TR #179937 w M{,

2. - -

panel 9-39, FSR 366E8138. relays were still TR #179936 M ir-13A-K26'in operable. TR #310880 ! M*# ~ panel 25-31, TR #310881 2 Mb:

  • * ~

and 2E-K9 in hk panel 9-30. . ~w

  • e l g., S i v.re:,,y a,.;, -

NfQ[.. f ]Q;d. '.J. j Fw _,.i

  • - - ~

i 'ij r rg+:- - p ": a:=; p.: ~. s t$ G 7;N- ~ ?AM;. ,n w w. Q Q[ -. It. .:;;L -.- _u.;,;- - v b $

l. L.-

=-RY- - pyn-p.- .,w M,Q.

.N. mm y

,.f,f[Ai u' p. -..;s ' ^' Q.2

BROUMS FERRY NUCLEAR PLANT UNIT 2 I" W 3 [._ g. !. " l.' S 1 L 3c f CSSC EQUIPMENT. ELECTRICAL MAINTENANCE SU$1ARY PW" 3 P _ 9/29/82 .j ~ ~ " ~ ~ For the Month of January 19 83 N. - Il__ ??.s.. Effect on Safe Action Taken w: [fDato

  1. N."

Nature of Operation of Cause of Results of To Preclude System Component Maintenance The Reactor Malfunction Malfunction P,ecurrence y /14/83 Fire Pro-Annunciator Annunciator None, heat de-Loo:,e annunica-Annunciater TA On failure of g 31/83 tection TA-39-113 TA-39-113 tector opera-ter card. 113 would not test. 1/14/83, the input circuitry. failed to bility was not control room annnn-wire 2M1123 uas test.

affected, ciation for the 1ifced and reter.n-M'[2 affected heat detec-innted, the annun-filIf ~r.

tors zones was still ciator was tested NT' available and oper-and operated prop-

k.,*/2 able via an alter-erly. The

@{j q. nate alarms path annunciator failed Q Q..; through central again on 1/31/83 E' panel 25-313. the annunciator 1 p s.- circuitry card g[yr y g was realigned, g F i. tightened, tested, kIM@- and returned to service. N TR #339956 b.~ 'IR #A061006 rWW O. J-L:. ~ 7 /15/83 CRD _ Hydraulic N211cak around None, unit in Bad 0-ring seals Loosing nitroger. Replaced 0-rings

thur ?..

control unit PS-42-43, LS. -refueling at PS-42-43, LS-pressure from HCU-for PS-42-43, LS-h./20"/83 -i PS-42-43, 34-43, and LS-outage. 34-43, and LS-42-43,llCU-34-43, 34-4 3, and LS ffl LS-34-43, 42-43. LS 42-43. LS and IICU-42-4 3. LS-43. Replaced LS- =' d@ g 7. jy? LS-34-15 and PS-38-07 bad. inoperable. 07. i LS-42-43, 15 inoperable 15 and PS-38-07 34-15 and PS-38-07 34-15 and PS-3S-pg;. r.- and PS-38-07. giving low NU TR #339969 K94 alarm with Ng2 TR #3399El c. , Nkk ai .s Pressure TR #310133 [#% ~ normal. TR #310134 .s ,M? A,. TM. =

4..

.\\Q2,p. n.c [',h*. ~ 5

  1. k..~,.(..-

,.. o gpg g $ br..

hee. . = =.. e.=. BROWNS FERRY NUCLEAR PLANT UNIT 2 Page 3 i y BF E}!SIL 30 M A pendix li l@- CSSC EQUIPMENT ELECTRICAL MAINTENANCE SU$ MARY P 9/29/82 h '. - j' For the Month of January 19 83 ) un 4, gp;m., at Effect on Safe Action Taken ag-Nature of Operation of Cause of Results of To Preclude

f)
te System Component Maintenance The Reactor Malfunctfan Malfunction Recurrence F.

l1/12/83 Main Relay 16AK2C Relay inoper-None, unit in Burned relay Received false Replaced the re-Q, Steam. in panel 9-15

able, refueling out-coil.

" Steam Tunnel 111 lay and function-

g. ;

age. Temp" annunciation ally tested. ~ fi on panel 9-5. Com-TR #311092 T' puter printout on h#, C1547 " Steam Tunnel .O 111 Temp". Relay g dacnergized causing Q, 'i isolatlon. b.L u: l z:. h14/83 CRD. Scram accum-Local accuin-None, unit in LS-34-11 lead Circuitry for cet 4 Cleared ground at gf ulator icvel ulator monitor refueling. grounded. hydraulic control level switch 34-11 e . switch LS panel 25-22 units at accumulator and replaced fuse, g... 7"'Tp, 11. fuse blowing. conitor panel 25-22 circuitry operated &L 7 inoperable. properly. u @ l. TR #339267 ? yyn v.. g4. - )./14/83- ._' CRD -CRD c.ontrol HS-85-48 was None Broken ucchani-Required care to be Replaced the gf 4 1 switch (HS-not operating cal stop. taken by operator broken stop, j[$E~ ~ 85-48). properly. to avoid operating switch operated ,.M the switch past the properly. l =., c._ desired setting. TR #339921 4 kf.:. - P 'I w. ', I5*!U j +1 ri-ET. '. ~: .i $,Nn. - $Nt . wig mti. ' .i. . J~.. ..en: n (( --. ..= =

m... i Page 3 BROWMS FERRY NUCLEAR PLANT UNIT 3 4

  • ~ ~

h RF EMSIL 30 ELECTRICAL MAI)TTENANCE SU$ MARY Appendix B M CSSC EQUIPMENT

b. i. --

9/29/82 1 '.. A For the Month of ' January 19 83 If,w - rpt.* - p.A, _ Effect on Safe Action Taken @@i na;; _ f Nature of Operation of Cause of Results of To Preclude MTDatst TSystem Component Maintenance The Reactor Malfunction Malfunction Recurrence VL. - I/20/83. Heat exchang-Valve red in-None Bad limit switch Valve indicating Replaced the bad RHR {Qj ;. er C dis-dicating light light circuitry limit switch, rr. charge valve on panel 9-3 inoperable. light circuitry F"@ HCV-3-74-22. inoperable, operated proper 1y. d%.- TR #313382 e2 f:: . w.::.,: m. p-1/29/83 ' HPCI-Condensate 3-LS-73-5 None Grounded wire Condensate drain Pulled slack from '. h. drain pot inoperable. in junction box pot drain valve wire, cut out dan- ~ chg , n.- high level due to open (3-LCV,-73-5) was aged portion, s >;r; switch insulation. made inoperable. relugged and term- . lQ.. (3-LS-73-5). inated wire. The

! Wy:;

level swi.tch cir-k,il3M ; ..1 _... cuitry operated kg . _ $~ ' Properly. g 0 2'.5,;; .~ TR #269417 I ..w. += ,n :n,'fp., _ ' ~ ' '

m,.7, x

ll$Q-W

    • *.g'l u. d *.

j @@,.l cyge -f y 9 g 3 . w. _,, m ~ .3 f r. ~ % y o. ~% N h e.:; ' ?>i.-. i ,e' u T ' qe4 fg]{.. 5 ;-{;.. E, ]7 n:;, x %,-TJL r*- W W.5;. 'Ny... . u v Up.' m._.=.,.s=c_.

  • c

,1 K,Msu' - .,; 6, O M.h ^'., '4," .; :.M,- 9%.

,.py_.

c w

r. a-
  • 'mo n-5h*.

l 2 p.- ,] 'y.h. ~'f M.. 1 0 1.. J,. - Q4.

  • i.g: W - -.

y u.. - m - mm ; .t "4A-Y 01 .e

w.. [. Tu.' $ BROWNS FERRY HUCLE/.R PLANT UNIT 3 c.W I.., g r. E' i ._ J ELECTRICAL MAINTENANCE SU$4ARY Appendix b T 4 CSSC EQUIPMENT t- ' r ^0 4 .f

T' ~,

,_1...;a.. E. 9/29/d2 s ...'...a~ .y y i For the Month of January 19 83 J, ,,.. m -..

m.._r.

4 y.. 2 n- -. .1 a . gW6 y Effect on Safe Action Taken ie,3 T[,tj ',. y :.h. 'i( Nature of,, Operation of Cause of Results of fe Preclude

JDie~

System

  1. aicomponent Maintenance' The Reactor Malfunction Mal f tm c t i on decurrence bk :

1/11/83 Core NW core spray NW core spray: None, fan would Wiring error NW core spray room A TACF form was ' bi, Spray room ecoler room cooler :'a start when any (internal junip-cooler fan failed to issued and the rw 's fan circuitry, fan failed to set of. core era missing and start when core wiring error cor- "' d f start when spray pumps wires not lifted spray pump 3C was rected. The ' hf 8: core spray wers started from terminals started. drawings will be lfYgE-*'-~ pump 3C was as required by 11 and 12) in corrected by FCR. started. technical breaker coc.part-TR #291783 ' {d$.F '~ ^ specifications.

ment,

.(, . ~. kT"i* . w. 2 - None Bad magnetic Receiv'ed a false Replaced the bad f/l'4~/83 HPCI -Testable - Received a ' r , Qqf ! check valve valve, "opett" switch. valve position switch, position f;;r 13-FCV-73-45% indication...:1 indication, lights operated u. E if - position in- ^ with valve in? properly. f }Q 'dicating'3 TR #313325 U closed a 4 , g f. f . circuitry.'y _ position.-e. p . &' a c.

1/15/83 RHR LPCI MG set MG' set tripped

.None, unit in If the motor MG set tripped on EMI 71 was per-b m. 3EA b. on attempted cold shutdown, doesn't reach attempted start. formed. The

1[M:.n

_ l? . C.f # f s tar t'.- RHR Loop 11 rated speed in motor generator 7.. ~~~J ' .3.7~k '" y -! y available. 45 seconds over-was successfully ~ %." N current relays started and re-Q- 9 w a n.... ~ ?

d _

^ ?. ~6, T g'. will trip it. turned to service. 1 nac

2. 4 j?E' E T

';N3' 3 The motor gener-TR #340834 $'g U~ ator requires 4 close to 45 scc- 'T J 1 f Q#,. ~ ~ ate normally. c onds to acceler-a j ; ys[{J@ .27 g~ 4;t#I P2 ',I It appears the ! { $7;;._. ~ C J motor generator 7 G. B.T failed to reach

S,d,

rated speed with c. " ES:t m e. in 45 seconds.

  • 6.3

.~.-., $ - ; E

,
n. :~ u= g -. -.

..p@,. s ~ ~ ~ ~ w: exw .s 'E.dy[p ,z .fwinmI d.*'

      • " j
  • .,* f

.. r. 5 g. I RC'.JG'tf 6 .TG '.4

w. .......o.44 ..u :,. _,A. :. :n:m n y i fV: F T.C IW:-I C. FCR 7.!E

  • O';HI CF January

, ga jy

y. ;
  • c,ya e.- - -

. KA T,.*R.E EFF1.C 0:; SAFE cat;< E i L.l;l ' 5 Y5 3 - CCMPCNC;T OF. OPEF.ATIC'i CF OF . s x.,.. - U i +. "... t.,-

r. 0 i c..

r MAIF ESA*;C2 TEE Ft. ACTOR P, Q y g ;";- g ; l n7 - g.gr.-.. y.y g...,-. f: v it. 68 - PDI-68-7 (rep ace None End of Life Instrunent Drift Ncne 1 y 2, 1 PS-1-76 Replace None End of Life Spurious Contact None ' Q. Operation s2 .~ + ~- 1(

  • 75 PI-75-4 Repair

~ i"W'S None Over Ranged False Indication None g 75 - PI-75-13 ' Calfbration None- ~ " ~ Instru$itii) rift y.- False Indication None . ~3

e..

.W. s. 'I7g.C i df'.A $.e 2 J{,f 3 LR-3-53 Repair. I(d FNh beh Invalid Alarm Nonc f 64 PDIS-642-7 Replace- .p 'hoA* J End ofb.ib. n g ~... . w 'c s.~.g r. Improper Switch Nonc ~ ki Q p u . c p m, 1,.. Action w %s...,..,. q w. * +.NR .?... 'ea.f.t. u.,.e,. e..g :. ~ e v....g? a.. : c- . :.s,. +e 4. ,4 J w..,. e e - .u ~ . r .se. 4,,. g, , e >4. . ;,u.,

u..

g f g4- . =, ,h j q ."6%.7..1t'.y , %;' 9.

  • r., J "S.g ;
g.,

gg p,

g., 4 - s s

A -* n... .y...

4. a *

.e c i. e r, ; y ~. . w e ,t, ay +a. m' - ' _< 2. - ; -1; m e. y> s g y.. _ e - ..w ... n c-Kn 1 set *~.' .;i L - *' 'y

  • ,..i,

.'"*s A ^ - . i f-

f.,

, '.,'~..,

h..N.. % ;)

. a...h M.? C..., - . 7 -- @s ,i. e g 5,k.; -:. ., A~ YV n 2 1., - E m e, Q Y I = . ~ ;._[ e ua %, +,4,. 3,,, a

g

~m 2, u:

p..s. y

.L,..y ,,. r ,.,~.5 -n s e,. - ~ S m. ~ - -v,.v .--z _. g r.- y. r p. g e... .6 g. ,v .e +Vs; w.R j.m n f,;> e> s 3 '.. s. y ., #.,.-. m. s.'. p:.,.. , m.- ?.-- , s.- y .+ w p'r .;

  • upe,-

g e.,,.'...r..w. ad,m..r - r e t p .w g ~ '~ ' 4 'p. [ -.~.;..'. - An:(;# A .[ ...I e ,.n.r n ' _g. Ee l-, *- .w-q g

t..

-.,j-. _... ,rgl/c,gi c .q.a .~. '.n ? .h . sg W.. c ... a n .ca. m - .c-1 n V5'. '., s, M f*_* ~, h'f f r '- j, "l] e 5- ,. p, 3 g- -+ g ;< vg e k (fL/.! +- . ).y '~ 1 g,':{ ' y;p r ~, ng "'. y, .!3.. - - v >, $,. q '. 1 :

  • J Q.L.C ;,,.. a -;

' '. E -J 3 2.@ J~ m1 s W. , f, ,3/ f 2;. . 3.g '.=;.,. u. ~., ,iV 2% ~ ~ ~ [t y g 4 g&,' t' 4 .%'. u m.%... _~. f * ~ ' ' * ^

  • g f

_ I **Q ? ~,w ? .__m -i. w a. e _...,.,..'N,^'-* 'n., 4.l ' um ,. m , e> +g - W.-

34 .... e FIELD SERVICES

SUMMARY

January 1983 Maior Work Areas A. Refuel area - the fuel shuffle in the spent fuel pool was com-pleted in January in preparation for loading fuel into the reactor pressure vessel. - Upon completion of the fuel shuffle the jet pump plugs were remove 4, Ot.har preparations were conducted, Surveillance Instructions (SI's), etc., to support the fuel loac* ing. The fuel pool gates were opened on January 23 and fuel reload was started at 2010 hours January 24. Fuel loading is still in progress. B. Turbine - the "B" low pressure turbine assembly was completed in January and successful testing was performed on the two thermo-couples which were installed the previous month. Coupling align-ment was completed January 24 and oil flush was started. The oil flush was completed January 29. The generator air test was started and is continuing. A stroke check on the turbine bypass valves was performed during January. t C. Electrical - during January the primary work performed by the electrical group was as follows: 1. Completion of LPCI Loop I tie-ins and post-modification testing. 2. P0392 - all instrumentation was calibrated and the post-modification testing was completed on this modification. 4,.. x +~,;,,u.,,e 8, 'e. e6 c w.,.;. ii

b 4

1 ' e s.Nk; k Ir %e't o A v.*a 'Whe e.h r-#/MitN5mEm WdMm&"i >%MNMr '). N#ws

0 l 35 i FIELD SERVICES

SUMMARY

(Continued) January 1983 Ma_ior Work Areas (Continued) C. Electrical (Continued) 3 Completion of all electrical work on the inboard MSIV's in preparation for fuel loading and started electrical work on the outboard MSIV's. 4. Started work on the STEAR for recirculation riser instrumen-tation installation. Junction boxes were fabricated, installed, and cable is being pulled and checked for conti-nuity. Instruments are being mounted. 5. Work continued during January on L2115E. This work supports installation of the two new MSRV's on the "M" and "N" tail-pipes. 6. PO479 emergency lighting - all lights on elevation 565 (reactor building) were completed and operational during the month of January. Forty-eight of the seventy-one lights are 100 percent complete, fif ty-four have conduit complete and j fif ty-two have wiring complete as of January 31 7. Other electrical work performed this month includes: a. Completion of all electrical work to support P0630, thermocouple modification (turbine), except final cali-l bration and checkout. l l l' ,.4 ~ s o:~.. n-y > -v; .. e.,e, ; p -

4. #

e 3 4 cf.p. e,, k kg.4Mpaw[hk a f.n*gdd&de.t.Ap* W *d+$hJ Q )2 A'. a,. / $ 14.. P/ s./.'.% e,' is h&Tkt. jiffsmhteitgrMh J w

36 FIELD SERVICES

SUMMARY

(Continued) January 1983 Maior Work f rqag (Continued) C. Electrical (Continued) b. Installation of conduit and cable for the torus vacuum breakers. Manually actuated vacuum breakers and set limit switches. Awaiting service air to be placed in service before SI can be performed on this modification. c. Supported the preparation for ILRT, completed Field Services Group' portion of the main transformer 2 "B" work on January 14. d. Started spraying flammastic on uncoated cables in unit 2 reactor building elevation 593. Supported the prepa-ration for the unit 1 torus modifications. e. Completed all work related to Electrical Maintenance Instruction (EMI) 71 and completed rework of conduit supports on P0590. D. Mechanical - the mechanical portion of P0392 was completed during January with the completion of hanger ir.stallation and air lines to the vent and drain valves. In addition manometers were installed on the east and west SDIV tanks to support instrumen-tation calibration. After completion of instrumentation calibration and the post-modifification testing, the CRD timing j l "4 a U' I

  • "M" g

-T , [ b*@8" T .h s +4 p , r wcsw A,e .. <. -* z.*,. x,..-dws t te,whyghsch%,je.w amm.hbd2 m ca. e - -~- l 1 -- : -- em 3 'n s. e x 1.-.,< n

i 37 FIELD SERVICES

SUMMARY

(Continued) January 1983 Maior Work Areas (Continued) D. Mechanical (Continued) test was performed. During the timing test various problems were encountered including the star valves leaking, and two drives indicating they were uncoupled. All problems were resolved and no CRD's required changing out. All inboard MSIV's were reassembled after passing LLRT, (in support of ILRT) and turned over to electrical for final assembly. Some mechanical work remains on the outboard MSIV's. 1. Other mechanical work: a. Completed plugging last two feedwater heaters and turned them over to Operations. b. Completed all MSRV torquing. c. Completed all contractcr work on the "M" and "N" tail-l pipes. Vent header final inspection is in progress. l d. Completed all mechanical work on P0361H (H 0 m difi-22 cation), e. Completed all work on P0384 (change stroke time of con-tainment purge valves) except for an FCR for splicing cable and adding conduit. FCR has been approved. f.- Completed repairs on dampers and ventilation ducts on "A" and "B" drywell coolers. 1 1 ~ ~~ p v :, ,, n w, ~ r i,L, '%iv y, eter..., ev l J i^ _ ?< ,1. p.%;M4#Vt Edi alu it 'TwavseWd k%nsosu;inde>tbdapr tthcLArgM4d, gh e

d 38 t

  • e FIELD SERVICES

SUMMARY

(Continued) January 1983 Maior Work Areas (Continued) D. Mechanical (Continued) 1. (Continued) g. P0612 MSRV air supply - work on this modification con-tinued with completion of all pipe welding. During flex line installation, problems were encountered which required the rerouting of at least five lines. Two crews have been assigned to this work to support the upcoming IRLT cohedule date. h. Minor work still remains on the debris screens, and will be complete after painting requirements are resolved. i. P0392 - install fence around SDIV tanks (WP 6895). Interference problems have been discovered with the installation of the 2 inch drain line valves. This problem is being reviewed by EN DES. Also, there is a potential problem with delivery of fencing material. J. P0392 - install SDIV access platform (WP 6867). EN DES is resolving some problems as identified above. Prefabrication work is underway.

.w-

~ .. s,,. . u., z. w. ._wm,w. ens..;4cm-,~ - - - maa. uke. 3

39 s FIELD SERVICES

SUMMARY

(Continued) January 1983 Maior Work Areas (Continued) D. Mechanical (Continued) k. Repaired valve'2-74-85 (30 inch torus suction hand control butterfly valve). This repair' required drain down of torus. Also during inspection of 74-85 and other valves, valve 75-29 was found partially closed and parts had to be machined by the machine shop in order to make repairs. 1. TIP tubing - some prelainary checks were conducted this month to support the tip tubing installation and the installation was started the end of the month. 2. Work performed on unit 3: a. Changed out gasket on floating head and plugged six tubes on 3 "D" RHR heat exchanger. Performed mainte-i nance on valve 3-74-53. E. Torus - during the early part of January, work inside the torus consisted of above waterline installation of new hatch, vacuum breaker conduit, rebuild and checkout of vacuum breakers and bolt down of grating. All vork was completed during the first half of January, except "D" vacuum breaker due to lack of parts; but by month end work was completed. 4 .n N s s *<mr_ - . ; yy _ y.ro.,r ",,g. ~q < <. bam&.4aw.qad; eu ukwanueursswndww,,meL:" wkG e c,.u ,g, b, *. n: w ~ w w d; r

r V 40 .e FIELD SERVICES

SUMMARY

(Continued) January 1983 Maior Work Areas (Continued) E. Torus (Continued) Outside the torus, lapplate work and ECCS gussets continued throughout January. Torus snubber work consisted of rebuild of 11 units onsite by vendor. Installation of all snubbers was com-pleted by the end of January; however one unit developed seal leaks after installation and had to be returned to vendor for correction. This snubber has been promised back by February 8. Seismic lug shim rework to new tolerances started in the middle of January. This work progressed to where all shim sized were established and nineteen of thirty-two installed. The machine shop is fabricating the balance. i By the end of the month, two MKII for tiedowns, one torus anubber, one set of ECCS gussets, one set of torus snubber gussets, and nine sets of lapplates required completion. Sixty-six torus related workplans of eighty-nine were closed. l I l 1 l .,,c.,.- , n. ,,,*sn'.- ^>y s ayy

  • dyppgggm yg.Q Qmm&myL L

.!s_ s aki A. a s_f

Y
n. - w s

~, g}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20071F347&oldid=4417119"