ML20066D296

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Quad-Cities Nuclear Station Units 1 & 2 for Dec 1990
ML20066D296
Person / Time
Site: Quad Cities  
Issue date: 12/31/1990
From: Hamilton L, Robey R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RAR-91-2, NUDOCS 9101140306
Download: ML20066D296 (21)
v • d • e


Text

{{#Wiki_filter:6 4 4 e RAR-91-2 i January 3, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Monthly Performanco Report NRC Docket Nos. 50- 2 5 4 0,nd_,50-2 6 5 Enclosed for your information is the Monthly Portormanco Report covering the oporation of Quad-Cities Nuclear Power Station, Units Ono and Two, during the month of December, 1990. Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R. A. He o Technical Superintendent RAR/ LFH/klm Enclosure cc: A. D. Davis, Regional Administrator T. Taylor, Senior Resident Inspector nrereprt 9101140306 901231 PDR ADOCK 05000254 g PDR l' l

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MnNTl!LY PERFORMANCE REPORT I DECEMBER, 1990 COMMONWEALTl! EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. f3-254 AND 50 265 LICENSE NOS. DPR-29 AND DPR-30 nrcroprt

1 l TABLE OF CONTENTS I. Introduction II. Summary of Operating Experienco A. Unit Ono B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenanco A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NPC Approval D. Correctivo Maintenance of Safety Related Equipment IV. Licnnsco Event Reports V. Date Tabulations A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions VI. Unique Reporting Requirements A. Main Steam Relief Valvo Operations B. Control Rod Drive Scram Timing Data VII. Refueling Information VIII. Glossary nrcroprt

I. INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The Mississippi River is the condenser cooling water source. The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,

1971, and March 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor criticalities_for Units One and Two respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two. This report was compiled by Lynne Hamilton and Karen Mc

Dearmon,

telephone number 309-654-2241, extensions 2185 and 2240. nrcroprt

II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Unit One began the month of December with the continuation of the refuel outage. Reloading the core began in December and 477 bundles were installed. Normal refueling activities will continue into January 1991. B. Unit Twg Unit Two began the month of December operating la Economic Generation Control (EGC). Normal operational activities woro performed for the month of December. The unit remained in EGC or operated near full power with only two interruptions to perform routine work and testing. Those two interruptions are as follows: on the 8th of the month power was dropped to 310 Megawatts Electric (MWE) for Stop Valve maintenance, and on the 29th power was dropped to 400 MWE to perform Monthly Stop Valve Closure Scram Function and 2C3 Ileater Work. l nrcroprt 1

III. PIANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANG A. Amendments to Facility License or Technical Specifications There voro no Amendments to the Facility License or Technical Specifications for the reporting period. B. Facility or P_rocedure Chances Recnirina NED_ Approval There voro no Facility or Proceduro changes requiring NRC approval for the reporting period. C. Ignis and Experiments Reauirina NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period. D. Correctivo Maintenance of Safety Related Eauipment The following represents a tabular summary of the major safety related maintenanco poformed on Units Ono and Two during the reporting period. This summary includes t the following: Work Roquest Numbers, Licensco Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safo Operation, and Action Taken to Provent Repetition. nrcroprt I .. -. - -. - -. - ~ . - - ~.

ITNIT I MAINTENANCE SLMART - WORK REQUEST': SYSTEM 'EID PESCRIPTION WORK FERFORMED Q88931: 7300 Breaker, ACB Electric-As found: Breaker won't close probably due to lack of 480 VAC NEN #N003 lubrication. As left: Lubed.the reset spring bolt with mobil 28 and tested operable with breaker test device. -=.__ ;.-. -.x-.-.

l ( UNIT 2 MAINTENANCE SLM8. ART WORK REQUEST SYSTEM EID DESCRIPTION WORK PERFORMED. Q87160 2400 Controller. Temp Ind H2-02 'As found: Heat trace circuit TL1 vill not maintain. i Monitor HT Tracing _ . temperature at set point of 270 F/FII. As'left: Heat trace was operating all the time, but not reaching. 280 to shut off.- No physical problem was identified 'when' testing individual components. The system was then left as found and Tech Staff is to issue a minor design change to add heat tracing. 4 ,I I i i i L t I i . =

IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units one and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications. UNIT 1 Licensee Event Report Number Date Title of Occurrence .90-25* 12/6/90 Group II Isolation Reactor Level Instrument Return to Service 90-26* 12/20/90 Control Room Isolation Due to Toxic Gas Concentration 90-32 12/24/90 A Fire Diesel Inop for Greater than 7 days 90-33 12/23/90 A SBGTS Auto-Start and RB Vents Isolated 90-34 12/23/90 Failure of Chlorine Monitor to Isolate control Room Ventilation UNIT 2 90-13 12/14/90 Torus Low Level 90-14 12/20/90 Torus Level Transmitter 90-15 12/21/90 HPCI Drain Pot Lines Outside FSAR 90-25 and 90-26 reports for the month of October have been-downgraded nrcroprt

i l D 6 t V. DATA TABULATIONS The following data tabulations are presented in this reports l A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions i i l nrcroprt

f4 J--..J.,s &#.a. M A _aal___ .oA Ae.M mMa. A..d si.ll A4$JdERAA*M M* a MAi he A M d 44OA -~sJh a - 34 6 e4S,%4-- a4 X M *wM a ^ 4s-4 44 4 ~h A- ,# B M A 15J-* Ah J M- .M h 4-=-e+AW.h-+= d*A.Em-i-n=4--m y 8 4 g 4 g a 4 g 0 4 h h,I L I I f., L>. ~ s. .v, b C*- *9 9s f f '. b' 's .4# v L*lt E' t [ $319 .Ilt.J'y 3, !?Il C:ttletet ty

iore sitd t
"-

j ' fit;' 96 ??4 i!3 *2s! i 1 1 .k. 4 4 O A% q j sO *) I4 4..aiie.e.. t _'.i. ).r 1' E ) 5#!Ii *0,*$ If #iOO#I k&" Ei!.!.. 5 ?)['(('s" fl *! *d h. .#7EP.I$7 hL!D5"l!ii kI# ifVf $'ntl) ff I h !I f *'d. ISII!! -' I* kit I f ~ Sti! *v9Iit;lf!;&If-it!P;IFAf*hiti 759 Is h!*IT klif t0 hblEI IIIkrl!!ft llk b#V) I'#f*btI I ' k 5 4. -,i, 6P, o. 4. ~ b, Ne$It".CY NOR*1 kid!IO' Nil (r$Iltd} .I I $b*I I idhl.I t. Pra:!:t fettrvs ihttt:41 H:tri. C.0 f.L 341L1 i n.9 = *t t. 3, .m54g*.F a' a- -t f.p 9, . 0;P1 teotriter Ji Line v0 aars.V s p 1 4 . 3 =3 - 54 4 Ilk 9fiI'VI DIG U$#3 N0?rl Y,. e! 'a,s TC > 'I.' Eftt5 I"Effel-iftf;y E9"creta: IFkm) 17'. IIli f. 0 77273 IIA 0rD th;5 :ss ilect tcal Ere jy Seit*4ted ('n') L' !542787 0 653i!!!4.0 II.' het E!ettri:al Li r;y i4*etatet (*ct} !!!!,0 5? 3E!b$ ?3173:41a I t . !!. Practc St* vide Fa:t:r 0,0 33.! ELi . il,Gra:tcrlvatiatilitiTe:t;* ~C. ', i3.5 01.2 !4. tsPJ iervitf ia:tc'- 0- C 51,1 ??d i d< J'it f u 0 stility Fact:* C.0-5 ! 75.0. I* 4f b t' e 5

17. Of!t Capitity I tcr.0.51r; _It 51;% FLt)

'hI ~77,2 thI I 4 ~11. L'it f:ttej Osts;e Oatt EF? - l- $ !2 2i i a e e 2 9 -4 . j =l' 4 i e : - 3 e y j 4-

Tdd, h-Viits }n Illt $t6tsi tir!Gr i; 2017t' tid! 0;4'itiC* !t I0Tt:35$

- 4Ehithe: initial Of!!!: alit). - 4 Illdf$kI [rffd$ $$ -n.~.... I ..1 d.

  • k 1

if j -.. - -~. .4.. -, -.- _ -.....~.-,_..-.

a .4W*. L J-s -+A4'N si, C+ mmA#ad ame&#d A..ae M - .Aa, >M&O4 M a 4 WMJ A +- AMAN *f--P"4.M-M 45,h 4~,M-_H*h-;&-.JR.JSM-

  • '4--**ehme

'+La-p.hm3-+5 g+2,,,_____gg4cA,.3,,,._--4_a m 4 g,4.g g ag y n. 4 e g ' 9 'g 9 t hk I%.s ' {, -- ~ e ?.N $.$ h4 --a sh h m. l I #Dh N b* D t If hlIt [3*dI"7 I5 {CG} tit! f.V Ly*P4 EAN !!'

  • ele;t:+

'09-t!2 ::4! i I J - DI[IJIIN}ET&Tc! .? ? * ?.t*??!AR A&..Aza4 Ae.. - != Iv")'k$ 1 I#1 h s.../ flu b#C$5 )l I kf f 5 $! ! I'l!iI.I...... b e' $$) bIf hYh de d' s 'hhk 4 l l 1f h{"h) { P df hkf e - !et!;eIlt:ttttal Fatit; "it-%tt; 1,2 } L-I:ver '. eval t: i+!:5 f estricted 04 A"J IP-te-teth iLi t i : Elli 05 ID' Ifitfl: lift !!f I"f}i t 2 i ~ M -su 4 3 9 4 4 4 . hka F Yk $ b N !wT s' ... *N de t 7, FDa s fer:friter On !!ft 714,J s!!!.$ 1 !!!*.0-I. U-(t Feser ve' f rtto:w" 4:,Fs - 0,0 3, 6 702.1 ' 9. Bress' hire 41Ittegyfecereted(Pst) 1732507.0 lIE34704. ' 2 t ?:.'! !!h l b L*cas !!sttrical (*t gr ie trates 1"in 171514,0 _ 5?:1 Ln IA4!!!(7.? A 11/ Net.ile;trical. ( ergi iet eretet (vii) 5!!f43.( 4 !0103,( 795't!!!.0 !!!,'Itaster 5efylteFeito-130.0 724t! 77,3 - 3

13. Eetti:e Availittlity Fa:ter 10(.6l 72,0

?;.;

14. Unit St vice Fa:t:r

!B0.0 7hi 75,7 !$i Unit fit;litllit) I&:tC* lih( 7h& 75.7-111~,kritCape:ityF#:t:r'fLiin;**C)- it.9- ~14.s t!.t' 117. UtlI Catit* t) Fi* t0P. (Cl!rs Ittig'! MWi) 54.7 67'.0 LI.2 .15. 06tt F:rces Octa;v Pete 0.? 7;5-lii tut: tant it^e:elec C,-tr Ar:!.6 ?:stti (Type, Inte', an: :-s(tt: :1 Ea:t): t i

2) [dk bhV*, )?t0 3* $*d GI Ef 0#t SRIkCI, E$t$1dII) (dkl C 3IlttC0k 3

91till Crill:1!Iti -!sitarl Elt:tricitt Cr ner:!al.0:tratten '.!! ? 1

~n_.nn-t I 1 I I i.' D e g 0 + l P { f tA 'il ', f>. kf. w'hk..: h,Y k..l. l s. 6,gI= t.g. f h. e t r, 6 L ^' i ' Ft s' * *. t li' ' n' Y,', 151 ':%tet is - p* t stic

  • ta. L u.. t * - ; a. r t. v-( :

o. / y%*p - +rsts u n d'rt. t i 1 t s ) V' M. P S, N "4 9PWf, *e. f ' tgit r y h,M s t 'e t,L def .y.N N,' V ;r.. 4 4

48. *%

3 P PI +a-J l{ f**

  • 291 a f.

Ph p g i>s {d i! @h{*\\ () f A . L' .i t .r ) + ! ?. . t. n T .? 's y .t a '(, .7 '4 -O

  • I.

= vi - A" l

  • I

.I 4 , I-6 I .e.[ f -i

1 f

i 1

c.

t .o 4 A s ^,. .t . 4 *< I s Ax F. is ,? "1 t 0 .? 't ~i' 0: 13

  • i 3

-E p -.g y t i.,

i. t

. f: 4 6 i i lh 1 i ? I , 4dtm.,-4.% _ h tais-Ws 'litt the atrage nihyit'::.e* "al H be Net 4 ent ny la *nt re:Utir; eta" 3 -- Cercitista the rearett e;1t As; suit. l 4He ypes ailhe Sty: te 1:t a gen' 4: on ieprtig :ith et that #r tN:a demul-: an.:ity n ate <: twat ea:th:o ntn; e tu at, ni e m n =ut:n er ta ony sana. D 't 5 D 0 k f Vfit f *Mr 'd;d delt 5"it.0 th ihhstti it O dil; itt lif P!Nt A%'ily s 1.!!*5 . t .. _... ~. _..., _,......, _. ~ _.

k ? f a e +, 1 1 I; I + h b k o ;e..e v.., =p.t c :: t e.5 r. 4 6 s . n l-c h 4' 'a v.e j a s,A s.- (';.918 L =. s =4 6 Aa -{ 4 g 8' ta b 9 s o s - e

  • 4 4

4 g**s s#;f. tral' t ; 411 Ift;)ttf-d ty i) 't fit;It tr. l-i f l P, P $ .' * " 4 ) A s ta k.A a.i. ' h 'r*rVV &' ? y 4 't w 4o 4 e g (%t4t!! . !%g Ait! r f $7 I. (..

    • ?

n e S

  • II

.i f.. 49 / + h 'f -4 7M N 7!! 5. 774 M 141 .6. 70-l2 Ils -7 747 3 -47 E 6C 74 7!! a, Tu i w< 5 \\. f & C.. O, f 5 4,- r4 1:a 34 p.- 4, t II 70 3' M <.I , n. ,4 i (f. s 11 i ff - h(? -f s .o q, qd' = '4* . p$ k I,6 m Ih k* thIl_ iDf tg. il f t iht ' AVPi}& j)I!1 L"!! '," pF 2 f vfl.l* N#-Vit d6* $30P dty in thf ff?:'t!'y *:*.tP. 0"iNtt 101.hf;hf Vfit hf 0}i PF(#if tt, i NnP-ij;/nfulltewtef1:.M:t a gra;* +g nu rn: ti. ; 09. 1 tr ut JP orieg ege;inle. L-tnadtv at use: ir the ret detr!ttl reuP; ei the - : there ray b :":estet ne* "t nih ams;t. DF 10d tuHN thf 103 line b !!4 rettfl:id ;nP 1e4] 11W b R P (!te!, be D Frp Gily u*P, catt.:cth! dett tM.'s te it:inctn t:. rt; dan its ap;vint v: tai,t

1. ' H

~. -. -.... - -.. -. -. ~. -

1 f 4 o 2 S n 2 T n e N o t 4 E i l 5 9 t i 6 P a m O u a 9 C n H 0 / i. 3 S t e e N ng n O oa m I ct 3 T u L C rO A o Y fl B E e V nu D E I wf E N T oe T O C dR t H E E I P R un J P E R h e S v M L O e O E C el C T nE e O e tl i c ny UC SNO ITC 0 X w@" X U 9 S D 9 L N$ o" E E 1 R U F R r E e ) 'DW b l O m XP e w@" C a I c R n DD e hmE i 9' f NN D ( EA P 1 PS E O E N N AN ST W NNT O EER D CVO TU IEP N T L E S R R O T P I E .O"h 8 N R U e* 2 Uog $yM C N) OS e I R n TU 4 o AO 4 RH 7 t U( i 0 D n 9 U 9 1 s " 5 s., S e i 3 wg 4 t 5 i y 2 C r a E 1 0 d u T 0 5 a n A 2 u a D 1 Q J 09 O E N MA T N E O K T E N C I T O N A D U D 5 {lll. I.

ll IlflIlllf, D I D A D O l T I C N E T E .O E W T AM N E O. 9 9 0 0 J O D a u 2 1 9 2 A n a 1 0 T u d 2 8 E a 5 r C 0 y i t 2 g. ,3 i 6 e 5 S S w5" s 1 9 U 9 n D 0 i 1 ( U t 7 4 HR OA T 4 4 UT w 9 5 RI o SO ) N B B Eg5 MhU-4 4 U hU= R N E I P T O R R S E L T N PEI U OVC M T REE O D TNN N O TS T W N E H NA 1 O E SP P ( D AE f e NN Eeg c DD in e I a "8o m PX l b O ) e WD E ,r R 1 R Oo{h 9 E 9 D ~ "@w 0 U C T I O NS WU MU or an ri ii ,k t nt t T eT aw nw T C no ao C E O d n P OR E P cP !P Mo eo E ow w R P ne e E H t r r C O T h T N E lR R I E D ye e V d d E B Cu u Y lc c A ot t C si i T L uo o I y rn n O n e N n f f S 3 e So o / 0 T Cr r C 9 i R O a A2 S f 6 m MC t f 5 i o E 4 l F' l p N t i ue T 2 o na V S 2 n ct a 4 t e l 1 ir v o e n ~ Il !m

i VI. UNIOUE REPCRTING REOUIREMENTH The following items are included in this report based on prior commitments to the commission: A. Main Steam Relief Valve Onorations Thoro wore no Main Steam Relief Valvo Operations for the reporting period. B. Control Rod Drive Scram Timina Data for Units one and Two There woro no control Rod Drive scram timing data for Units one and Two for the reporting period. ? nrcroprt h

i VII. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresdon,-Quad-cities and Zion Station--NRC Roquest for Refueling Information", dated January 18, 1978. t nrcreprt 1

OTP 300 532 Revistor.2 QUAD CITIES REFUELING October 1969 INFORMATION REQUEST r 1. Unit: 01 Reload: 10 Cycle: 2. Scheduled date for next refueling shutdown: 11-12-90 3. Scheduled date for restart following refueling: 1-28-91 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: Yes, a proposed change to Technical Specification has been made to relax the Minimum Critical Power Ratio (MCPR) safety limit. This proposal is based on the Unit one Relond 11 Cycle 12 fuel loading, and has received approval. 5. Scheduled date(s) for submitting proposed licensing action and supporting information: AUGUST 31. 1990 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: ~ NONE AT PRESENT TIME. 7. The number of fuel assemblies. a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 1681 8. The present~ licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies: a. Licensed storage capacity for spent fuel: 2657 'b.- Planned increase in licensed storage: 0 9. The_ projected date of the last refueling that can be discharged to the spent fuel _ pool assuming the present Itcensed capacity: 20_08 APPROVED (final) 14/0395t 001 3 0 1989 C).C.O.S.R. ~.

OTP 300-532 Revision 2 QUAD CITIES REFUEL.!NG October 1989 l ' INFORMAi!ON REQUEST 1. Unit: 02 Reload: 10 Cycle: 11 f 2. Scheduled date for next refueling shutdown: 9-7-91 3. Scheduled date for restart following refueling: 12-9-91 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: NOT AS YET DETERMINED. 4 5. Scheduled date(s) for submitting proposed licensing action and supporting information: NOT AS YET Dl;TERMINED. 6. Important licensing considerations associated with refueling, e.g., new-or dif'erent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: NONE AT PRESENT TIME. 7. The number of fuel assemblies. 4. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 2011 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies: 4. Licensed storage capacity for spent fuel: 3897 4 b. Planned increase in licensed storage: 0 9. .The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 6 APPROVED "i n'" 14/0395t OCT 3 01989 O.C.O.S.R.

l 1 o VIII. G LOSS ARY j The following abbreviations which may have been used in the Monthly Report, are defined below: ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - American National Standards Instituto APRM - Avorage Power Range Monitor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor i CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations Facility GSEP - Gonorating Stations Emergency Plan HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT - Integrated Primary Containment Leak Rato Test . I FW - Intermediato Rango Monitor ISI - Inservico Inspection LER - Licensee Event Report LLRT - Local Leak Rate Test LPCI - Low Pressuro Coolant Injection Modo of RHRs LPRM - Local Power Rango Monitor MAPLHGR - Maximum Avorage Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio MPLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concontration MSIV - Main Steam Isolation Valve NIOSH - National Instituto for Occupational Safety and Health l PCI - Primary Containment Isolation. PCIOMR - Proconditioning Interim Operating Management Recommendations RBCCW - Reactor' Building Closed Cooling Water System i RBM - Rod Block Monitor RCIC - Iaactor Core Isolation Cooling System RHRS - Rosidual Heat Removal System RPS - Reactor Protection System RWM . Rod Worth Minimizer SBGTS- - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Modo of RHRS SDV - Scram Dischargo volume SRM - Source Rango Monitor TBCCW - Turbine Building Closed Cooling Water System 'TIP - Traversing Incore Probo TSC - Technical Support Center raoroprt >}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20066D296&oldid=4433756"