2CAN049208, Forwards Addl Info to Support 890831 Relief Requests from First 10-yr Inservice Insp Interval Consisting of Listing of Limited Inservice Insp Exam Coverage Estimates for First Insp Interval

Forwards Addl Info to Support 890831 Relief Requests from First 10-yr Inservice Insp Interval Consisting of Listing of Limited Inservice Insp Exam Coverage Estimates for First Insp Interval

ML20101B086
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/30/1992
From:	James Fisicaro ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN049208, 2CAN49208, TAC-M76001, NUDOCS 9205050310
Download: ML20101B086 (9)

Text

.. .. - . .

e_-~ E ntergy P o-l x

. Operations 1_._____ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ _ _ _ _ . .

April 30, 1992 2CAN049208 U. S. Nuclear Regulatory Commission Document Control Desi-Mail Station P1-137 Washington, DC 20555 Subj ect: Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NFP-6 Submitting Audition.21 Information Concerning the First Ten Year Inservice Inspection Relief Requests (TAC No. M76001)

Gentlemen:

In letter 2CAN088915, dated August 31, 1989 Entergy Operations submitted relief requests for Arkansas Nuclear One, Unit 2 (ANO-2) for the first 10-year interval. These requests were for relief ftom certain ASME Section XI Inservice Inspection (ISI) requirements because only limited

( examinations could be performed. The NRC subsequently requerted l additional information concerning these relief requests in letter dated Septa.mber 10, 1991 (2CNA099102). In letter dated February 13, 1992 (2 car 029202), Entergy Operations stated that ANO-2 was unable to provide the soecific infarmation requested but committed to submit a best estimate of the percentage of the Code-required coverage. The purpore of this submittal is to provide these best estimates for the coverage.

l The Code required coverage was estimated and placed into four categories.

These categories are 0 to 25%; 26 to 50%; $1 to 75%; and 76 to 100% of the Code required coverage of the weld. Attached is a listing of those welds that fell within the first, second, third, and fourth category.

respectively.

l l

The attachment also provides additional information, including items such as a description of the examination area, examination volume and/or area, the category of the weld, and the method used to perform the examination.

Based on further review, there are several welds in which the Code required coverage was considered to be met. These welds are those identified by 100% in the attached list. It is Entergy Operations' conclusion that NRC relief is no longer necessary and the relief for those welds is herewith withdrawn.

9205050310 92 A30 <

PDR ADOCK 05000368 0 PDR l 1

' U.-S. NRC April 30, 1992

( , Page 2 L This submittal provides - the information necessary for the NRC to complete-its review of the ANO-2 first 10-year interval limited examinatien relief requests. Should you have any questions regarding this issue, please contact me.

Very truly yours, M' cav James [J.Fisicaro ,

Director Licensing JJF/RWC/sjf Attachment ~

cc Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV_

'611 Ryan PlazaLDrivo, _ Suite 400 Arlington, TX 76011-8064

.NRC Senior _ Resident Inspector

-Arkansas: Nuclear One - ANO-1 & 2

' Number 1. Nuclear Plant-Road Russellville, AR 72801 Hr.' Thomas W. Alexion NRR Project Manager, Region '1V/ANO-1 U S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 i

'One White Flint North i

=11555 Rockville P84e Rockv8.11e, Marylana 20852 Ms. Sheri Peterson

'NRRLProject Manager, Region IV/ANO-2 U.-S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 Ont White Flint' North--

11555'Rockv111e Pike Rocks 111e,. Maryland 20852 L

L lt ._

. s OtQQM ESe :fL20-1 ANO-2 UMITED ISI EXAMINAT10N COVERAGE EST1 MATES FOR FIRST INSPECTION INTERVAL EXAMVOLUME AFKVOR AREA ESTIVATED COVERAGE %

ISI NO. h CATATEMNO. REMNtKS COMPONENTIDENTIFICATION METHOD (S) REASON FOR EXAM: NATION UMiTATION RFOs EXAMINED 0 25 N50 51-75 75-100 .

EXAMINATION AREA DESCFtIFTION EXTENT Code oniy requrres 5% of weld ler.gth 01412 BA'B t.1 Weld Metal + %t Base Metal Surveinance Capsule Ho! der / Attented 100% per Reg Guide 1.150 Reactor Pressure Vesset Vof for Bentine Region.

tower Shelf to Middle Shet Weld 5% 2R62R7 Code on8y requires 10% of weed 01409 B A'8 I .1 Weld Metal + %t Base Metal Surveillance Capsule Holder / Flow Skitt / le,gth. Attempted 100% per Reg Reactor PressureVessel Vol Guide 1.150 for Betthne Reg:en.

Lower Shell Longitudinal Weld @ S0

• 10% 2R6/2R7 Code only requires 10% of weid 01413 B A'B1.1 Weld Metal + %t 6ase Metal SurveiItance Capsule Holder / length. Attempted 100% per Reg Reactor Pres 2re Vessel Vol Guide 1.150 for Bettline Region.

Middle Shet Longitudmal Weld @ 90

• 10% 2RM/2R7 Flow skrt is not noted in data as 01401 B-B/B12 Weld Metal + %1 Base Metal 100 % causstg scan Mation. Fut Code Reactor Pressure Vess21 Vot See Remarks coverage achieved. Rehef ret Bottom Head Dome to Peel Segment Torus 5% 2R6 necessary.

01C08 B B/B12 Weld Meta! + % t Base Metal j Flow Baffle Assembiv /

Heactor Pressure Vessel Vol '

%ttorn Head to Lower Shell Weld 5% 2RS 01416 8 B/812 Weld Meta! + M Base Metal '

Nonfes /

Reactor Pressure Vesse' Vol Middle Shell to Upper She# Weld 5% 2R6/2R7 01417 B-B/B12 Weld Wta! + %t Base Metal Nontes /

Reactor Pressure Vessel Vol Upper Shen Longitudinal Weld @ 90

• 10% 2R6CR7 01-018 B B/812 Weld Meta l + %t Base Me.af Nonfes /

Reacto- Pressure Vesse! Vol Upper Shell Longitudinal Weld G 210

• 10% 2RS/2R7 01419 B-B/B1.2 Weld Metat + %t Base Meta!

/

Reactor Pressure vessef V.,i Nonies Upper Sheif I wigitudinal Weld @ 330

• 10% 2R6/2R7 Co+ rWy requ?es 10% of weld 01402 B-B/B12 Weld Meta? + %t Base Metal 100 % length. Code ccverage ached on l,

Reactor Pressure Vesset Vo! See Rema Ks 27% of weld langth. Hehet not Peel Segment to Peel Segment @ 30

• 10% 2R6 necessary.

Code on8y requires 10% of weid 01403 8-B/B12 Weld Metaf + wt BaseMetal 100*, teng*h. Code coverage achieved on Reactor Pressure Vessel Vol See Remarks 27% of weld length. Re!ief not Peel Segment to Peel Segment @ 90

• 10% 2R6 necessary.

(3) Distributed uniformly amor g three areas eound vesselcircumference (1) "t'of shett or head (2) it of Main Pipeng Run/2* Branch Run (4) 21 of Pipmg71 of Support AttachmentMember ("t'of support)

m

• s ESP 92220-2 OVJ0r92 AP10-2 URRITED ISI EXAhmNATION COVERAGE ESTIRRATES FOR FWISTINSPECTION sNTERVAL i IS' NO. CAT / ITEM NO. EXAM VOLUhE ANDOR AREA ESTIMATED CoraPAE% ~

l COMPONENTOENTFICATION METHOO(S) REASON FOR EXAMINATIONtNITATION IEMARAS

EXAMINATION AREA DESCRIPDON EXTENT ' ffOs EXAMINED Os 2fMio 5t-75 75-100 .

l 01-004 B-B/B12 Weld Metal + %t E,ase Metal Code only requires 10% of weld .?

Reactor PressureVersei . Vol Sae Remarks 100 % leng*h. Code coverage actneved on Peel Segment to Peel Segment @ 150

• 10% - 2R6 27% of weld length. ReEef not l

! necessay.

• 01-005 f

B-B/B12 Weld Meta! + nt Base Metal Code enfy requires 10% of weld l Reactor PressureVessel Vol ' . See Remarks 100 % 8=ngth. Code coverage achie.ved on Peel Segment to Peel Segment @ 2.0

• 10% 2R6 27% of wead length. Remef not

~

01-006 B-B/B12 - Weld Metal + % t Base Metal Code only requires 10% of weld  ;

Reactor PressureVessel Vol See Remarks tW5 length. Code coverage ochieved on Peel Segment to Peel Segment @ 270

• 10% 2R6 27% of we8d length. Rehet not  !

l ._ .

"'C'55'"I-01-007 B-B/B12 WeM Meta! + %i Base Metal Code onfy requees 10% of weld Reactor Pressere Vessel Vol See Remarks 100 % lengtts. Code coverage achieved on Peel Segment to Peel Segment @ 330

• 10% 2R6 27% of weld lengt*t. Relief not necessary ,

01422 BC/Bt4 Weld Metal + %t Base Metal (1) Examination limited for nozzfe bore  !

Reactor PressureVesset Vol End of Nozzle Bore / scanmng only. Shell not Emited. l 4

Inlet Nozzle to Shell @ 60 * ?00% 2R6/2R7 i

ic 01423 BO/B1.4 Weld Meta! + %t Base Metal (t) Ceranstaor:Emited for nozzle bore j j Reactor Pressure Vessel Vol End of Nozzle Bore / scanrang orff. Sher not Emited.  ;

Inlet bioloe to Sher @ 120- 100% 2RS/2R7 01-025 B0/81.4 Weld Metai + %t Base Metal (1) Exammaton Smited for nozzle twre Reactor PressureVessel Vol End of Nozzle Bore / scanning or+f. Sher notlimited. l J, tolet Nozzle to Sher @ 240

• 100% 2R6!2R7 ' '

t j 01426 BOlB1.4 Weld Metal + %t BaseMetal (1) Examnation Emited for nozzle bore  !

Reactor Pressure Vesset Vol End of Nozzie Bore / scaqrung only. Sher notimited.

i inlet Nozzle to Sher @ 300

• 100 % 2R6/2R7 4

!' 01421 B0/81.4 Weld Metal + bt Base Metal (1) TM wald was prevousVrcorrect!y l' Reactor PressureVesset Vol integes! Eviension/End of Nozzle Bore Shet Bore idarQied as01-027 which is not Outlet Nozzle to Shet @ 9* 100 % 2Rti'2R7 Emded. The sher side & nozzle bore scarming coverages are as indicated. f i

01 024 BC/B1.4 Weld Metal + %t Base Metal (1) TI e shet sida and nozzfe bnre Reactor Pressure Vessel Vol integral Extenson/End of Nozzle Bw Shet Bw scanrung coverages are as indica *ed.

Outtet Nozzle to Shell @ 180

• 100% 2RS/2R7 (1) *t'of shellor head (3) Distnbuteduniformly among three areas around v , set orcumference 4 (2) It of Main Piping Rin/2" Branch Run (4) 26 of Piping /21 of Support AttachmentMe r.ber (*t'of support) f

a  %

l - ESP 92020-3 : 0%$N ,

j. ANO-2 UMITED ISI EXAMINATION COVERAGE ESTIMATES FOR FIRSTINSPECTION INTERVAL '

ISI NO- CAT /! TEM NO. EXAMVOLUME AMWOR ANA ' ESTIMATED COWERAGE%

COMPONENT 0ENTFICATKW METHOD (S) REASON FOR EXAMINATIONIDMTATION REMARMS EXAMINATION AREA DESCRIPTION EXTENT RFOs EXAMINED C'27 :4 50- 51J5 75-100 ,

01-L443' B 4 1/81.9 FLs between Threaded Stud Holes

• The limitation prenoush reported was Reactor PressureVessel Vol See Remarks 100 % for a nonremovable obstrucconat the Vesse'F:ange Ligaments 2R1 bottom 2* cf the stud hole. This is l 100%  ;

outside the examinate stAsme of the

!!ange ligaments. The flange q ligaments were luny exstraned. ReGet

st necessary. .rt 02401 B-C/B t.3 + e.-;d is

• 4t Base Metal i Reactor Vesset Closure Head Vol r c.g i,9 i ge Configuration /

f Flange to Peel Segment Torus Weld 100 % ee4. "-'

03402 B-B/B3.1 Weid Metal + % t Base Metal Stay Cylinder Base to Lower Pead Vol Blend Radius /

Steam Generator 2E24A 5% 2R2

. 03003 B-B/B3.1 Weld Metal + 41 Base Metal Peel Segme it to Ped Segment @ 60

• Vol Nozzle /

l, Steam Generator 2% 10% 2R2 i t

03404 BB,B3.1 Weid Metal + %t Base Meta 8

$i Steam Generator 2E24A Vof Nozzle l / l j- Peel Segment in Peel Segment @ 138

• 10% ?R2 l i

j j 03405 B-B/B3.1 Weld Metal + %t BaseMeta:

S'eam Generator 2E24A Vol Nozzle - /  ;

Peel Segment to Peel Segment @ 210

• 10% 2P2 i i

l 05 009 BO/B22 Weld Metal + %t Base Metal (1)

Pressurizer Vol Heater Penevatier.s J l 12* Surge Nozzle to Bottom Head 100% 2R1 '

I 4

l 05-010 BO!B2_2 Weld Metal + %t t t,e Metal gt)

! Pressurizer Vol Nozzles I /

4* Spray Nozzle to Top Head 100% 2R2 l I" 05420 B0/B22 Mozzle hside Radiused Section I f, Pressurizer Vol Heater Bundles / ',

12" Surge Nozzle inner Radius Section 100 % 2R1 i.05-121 BC/B22 Nozzie Inside Radiused Section i, Pressurizer .

Vol Nozzfes /.

[, 4* Spray Nozzle ir.ner Radius becLon l 100 % l2R2 [

i j.

(1) *t of shellor head (3) Distributea uniformfy among three aress arour=d vessel crcumference (2) 1t of Main Piping Run/2* Branch Run (4) 21 of Piping?t of Support AttachmentMember ('t'of support)

' ESP 9202G)4 - 0%b '

ANO-2 URAITED ISI EXAAAINATION COVERAGE ESTIARATES FOR FIRSTINSPECTION INTERVAL

. ISI NO. CAT / ITEM NO. EXAM VOLUME APOOR AREA ESUMATED COVERAGE %

COMPONENTIDENDRCADON MED00(S) REASON FOR DAMMDON LMTADON REMNWS EXAMINADON AREA DESCRIPDON EXTENT RFOs EXAMINED 025 26M 51-75 75-100 . ,

_p 05-122 BOlB22 Nozzle inside Radiused Section .

I Presrewizer Vol ' insulation Bracket. IM Luc. Nozz!e /

6* Saiety Nozzle inner Radius Secten @ 0

• 100% 2R4 08-0?4 . Bf/B4.1 Weld Meta! + %t Base Metal I

Reactor Coolant (2CCA-5-30-). VrAsur Insutation Support Brackets /-

Elbow to Safe End Cacumferen'ialWold 100 % 2R1/2R2 L C8015 BJB4.5 Weld Metal + %1 ~ ase Metal 1

Reactor Coolant (2CCA-5-30*) Vol Insulation Suppor. Brackets /. i l Safe End to Pump CircumferentalWeld 100% 2R2

?. 09409 BJB45 Weld Metal + % t Base Metal

Reactor Coo' ant (2MA4-30*) Vol Insalation Support Brackets /

1 Pump to Safe End LacumferentialWeld 100% 2R2

, 24049 BJP ? 5 Weld Metal + %t BaseMetal A 1%V calibration enabled fut two-l Safety injection (2CCA 23W) Vel See Remarks - 100 % drectionalamal coverage to %

4 Reducer to Tee CircumferentalWeM 100 % achraved from reoucer sde.

f 2R6 Circum ao u e; coverage also attained.

j i

Re6ef not nu.a.f.  ;

25-01 B-JU4:5 Weid Metal + %t Base Metal No asial scan p," .M due to

? Shutdown Coohng (2CCA-25-14") Vol Hanger Support Bracl et / hanger support tracket and tee j Tee to Pipe CircumferentialWeld 100% 2R6 con 5guraten.100% crcumferentan c scan vu.wn m ,

4 l i 15-10 BJB4.6 Weld Metal + %t Base Metal (2)

} Reactor Coolant (2CCA-1040') Vol . Cable Wnip Restrarrt / l l

12* Branch Conrection [ 100 % 2R6 '

l 03030 C-NC1.1 Weld Metat + %t Base Metal r3)

Steam Generator 2E24A Vol Insulation Suppmt Reg /

Intermediate Sheti to CcnicalShed 20% 2R2,7R4/2R6 r

03431 C-NC1.1 Weld Metal + %t BaseMetal (3)

Conical SheG to Upper Sheft Vol Insulation Support RingA-Besm /

Steam Generator 2E24A 20%

}H2/2R47R6 i

03 032 C #C1.1 Weld Metal + t Base Metal (3) I

, Steam Generator 2E24A Vol Insulation Support Ring /

t Upper E5eu to Top Head Torus 20% 2R2/2R4/2R6 i i  !

03433 C-A/C1.1- Weld Metal + %t Base Meta! (3)  !

) Steam Generator 2E24A . Vol insutaten Supports / l l Top Head Torus to Top Head Dome 20% 2R2,7R47RS (1) *t'of shellor head - (3) Distributeduntformty amorsg three areas around vesselcrcumference

12) It of Main Piping Run/2" Branch Run (4) 2t of Paping71 of Support AttachmentMember (Tof support) 9

~ , ,

. m (

.. ESP 92023-5 OQWEZ mez uumED IS8 EMARANGADON COFRAGE ESDERATES FOR FRST WISPECDON WTERVAh ISI NO. CAT)tTEM NO." EX#MVOt.UME AN[VOR AREA ' ESTIMATED COVERAGE % i COMPONENT 0ENTIFiCADON METHOO(S) REASON FOR EXAMINATIONLIMITATION REMARMS I EXAMINATION AREA DESCR4' DON EXTENT RFOs EXAMIPED G25 2650 51-75 76100 .

j: 03441 . -

C-C/C1.3 ail-de J Weld Metal Steam Generator 2F.24A Sur Insulation Bradet /

4 Snuuber t.ug @ 270* 100% 2RS 4

04430 .

C-A/C1.1 Weld Metal . %t Base Metal (3) '

, Steam Generator 2E249. .

Vol Insulation Support Rrig / '

lotermediate She8 to C.micalSheE 20% 2R2f2R3;*2R5 >

t 04031 . C-A/C*.1 Weld Metal + nt Base Metal p)

Steam G..erator2E248 Vol Insulation Jupport Rir:g / ,

ConicelShell to Upper Shell 20% 2R1/2R3,2R5 04432 C-A/C1.1 Weld Metal + % t Base Metal (3)

Steam Generator 2E24B Vol insulation support Ring ./  ;

Upper Shell to Top Head Torus 20% 2R2/2R3/2RS i 04433 C-NC1.1 ' Weld Metal + %t Base Metal (3) l Steam Generator 2E24B ' Vol insutation Si pports /

Top Head T(,rus to Top Head Dome 20% 2R1/2R3f2RS 50415 GE/C2.1 Weld Metal . %t Base Metal Ebutdown Cooling (2GCB-5-14*) Vol Pipe Support l / l Pipe to Pipe CircumferentialWeld i 100 % 2R2 o

d 56407 CE/C2.1 WeW Meta! + %t Base Metal Welded plate located outside scan Shutdown Cochng(2GCGB4*) Voi See Remarks 100 % area on pipe side. A 1%V cahbraton t Reducer to Pipe CreumferentialWe'd 100 % 2R6 enabled fut two-d6eedonal axiaf f 4

coverage to be achieved from both i j' sides. Circumferentalcoverage also ,

attarwd Relief notnecessary. j 57409 Cf/C2.1 Weld Metal + % t Base Metal instrunwntaten nozzles & lugs located Shutdwn Cooling (2GCB-10-10") Vo! See Remarks 100 % inside scan area on heat exchanger >

, Reduce-to Heat Exchangar Weid 100 % 2.32 side. A 17.V calibration enabled fut 4 tro,.' G ! axial coverage to be .

i achieved from reducer side. -

Carcumferentialcove age also attained.

ReEef ret necessary. *

~~

t L

f f

i l l (1) *t*of she8 cr head (3) Distributed uniformty among three areas around vessel arcumference (2) 11 of Main Piping Run/2" Branch Run (4) 2t nf Pipimf21 of Support AttachmentMember (*t*of support) -  !

t' i

im , . v ( , - . . 3 .i r. ._. -- ,. . _ . . , , . , , .-

ESP 92020<, 04h '

ANO-2 USAITED ISI EXAAAINATION COVERAGE ESTIREATES FOR FIRSTINSPECTION INTERVAL -

, ISI NO. CAT / ITEM NO. - EXAM VOLUME AMVOR MEA - ESTMATED COERAE%

COMPONENTIDENTIFICATION METHOD (S) REASON FOR EXAMINATION LIMITATION fEMARKS EXAMINATION AREA DESCRIPTION EXTENT RFOs EXAMWED 0 25 26-50 51-75 75100 .

i' 58411- Cf/C2.1 Weld Metal. %t Base Metal Two betrumentation nonleslocated Shutdown Cooting (2GCB-11-10*) Vol .. See Remarks 100 % adjacent to weld on heat exchanger Reducer to Heat Exchanger Weld 100% 2R2 side. A 1%V calibration enabled fut l twodirac5onal axial coserage to be [

l achieved from reducer side.

Circumferential coverage also attained  !

i, wth 1%V calibnMion. Relief not

, necessary.

59 035 C-F/02.1 Weld Metaf + %t Base Metal .

Instrumentation nozzles & lugs located i

. Shutdown Coohng (2GCB-16-10-) Vol See Remarks 10c% insi&_ scan area on heat ed iw

. Heat Exchanger to Elbow Weld 100 % 2R2/2R4 side. A 1%V rafitwation ensbied fut two-directional exial coverage to be  !

achiaved from elbow side. l j- Crcumferential coverage also attaineri  ;

ReGet not necessary. j

. 60 027 CE/C2.1 Weld Meta! + %t Base Metal Two instrumentation nozzies located Shutdown Cooling (2GCB-17-10~) Vol See Remarks 100% adjacent to weld on heat exchanger I l Heat Exchanger to Elbow Weld 100% 2R2 side A 1 %V calibratior. .eabled fut two-direcbonal axial coverage to be achieved from elbow side.  !

I. Crcumferential coverage also attained i 4

with 1%V caubration. ReEef rot I

accessary.

j 58003B CJ/C22 Weld Metal + kt Base Metal [

Shutdown Coolang CGCB-3-12")- Vol Rigd Support Hanger / j j E! bow Outside Long um Weld 100% ER5 i

53421A CJ/C22 Weki Metal + %t Base Metal I

!' Safety injaction (2GCB-3-12*) Vol Welded identfication Tag / [

Elbow Long Seam Weld 100 % .2R2

! 55429B Cf/C22 Weld Metal + % t Base Meta'  !

i Safety injection (2GCB-7-14*) Vol identibcate Plate /  !

j Reducer Long Seam Weld 100%- 2R5 [

4 >

17-024 C-G/C2.1 Weld Metal + %t Base Metal r Feedwater (2088-1-24-) Vol Nozzle /  !

Elbow to Pipe CircumferentialWeld 100 % 2RS 19416 C-G/C2.1 Weld Metaf + %t Base Metat I Feedwater (2DBB 2-24")  ! Vol Nozzle /Vafve Configuration / I Elbow to Valve CircumferentialWeld l 100% 2R6 1

f

,. (1) "t'of shell or head (3) Distributed uniformly among three areas around vesset circumference I t

(2) It of Main Pping Run/2* Branch Run (4) 21 of Piping 71 of Support Attachment Member (Tot support) 5

! L

2 -

B 6 '

0 a 3 e w o 4

r a os -

nnl l bl a 0 aoiae e .

saamgy cix t r oa .

r dl eb4f ev n i

r S sn ca do i

K e v c -

R A

M i V d

e i n 4iaeir hcrJe ot E

a aenr R l o tcA6ee .

d dte1 bml f

f e

ie aiutouR pwf ei .cr t

r e d gC de .

o plea r L pibe p p avdt e. ia n -

A unnoit Soecsa V

R E 0 T 0  %

N 1 / 0 /

.I

% .E 0 1

N E 7

O I

T M

R 5 C E V

7-E O $

1 P C S _

N D -

I E 0 e T 5 c T A 6 e n

S M 2 r e

R T f F

I S m )

t E u r o

R sO ic c

r p p

O l e

u s

F s f

• to S s E e N v C

T O d A I T- n u

r e

d 1 . TA o b r

1 i a m T e S N s a M E AL e t EN ) r n E l 4 a e MIO' a la (

e m G RA T t Mp ee t e l e

r h c

A ON M a ep h a e P t t R I e t E GM

1. A st n a e s

a Mma g A n

o t

V #XD Bc B et sC tr o

O t a t at m C EhRN EE %dj  % Bo r a y

p p

I

.Af s + p u -

N UOM lao l +k p 8m S tara LF A lau r O O NX em teS o f o

I T V OE Mte4 .Me Me r f

in t A mss AAO da d R dg d u T g

N XEF leos rR le e3 eR le n2 aR e in I

S A

ERF WP2 WS2 WH2 b t

u P

p A ir t

f o

X is 1 E O. D 2 I

N)S ) )

( 5, -

.SI MD T 1 2

1 2 C

3

(

4

(

D tI OH N I 2 C /

E /

iT E T C-%

/

G4 0 l

Gl 0%

1 E

T AE X - c0 - o0 4r0u0 f

R CME CV1 CV1 CS1 R

U 2 - .

O . f '~

N .

n A N u O ld ld t R I

e e n h T e

.OINP W .W )

• m c

n I R l a

l a 2 1

h ar TC A S it n

i t

n .6

- c a D

.C1 E t

e e 1 t

• FD I

)

• e 4f r ) r

• e 4f BA Ea l

2

/

n T A 2m 2m -2( g r u NE ER 4c u 4c u get d R Bi r Bir n a g DA BC BC tinI h e n TI N De D or oe ip 2 e' 7- r NO I (2 p (ip Cg o P ET nan 3 i a n NA e P rP e r

2~ o e o h ia 0' .ON t at t

at WowH s M 2 OPI 3 ww ww 9 dg f o

9 NM M A 2do 1

- 4Meleb d o' 4

0ui t n fo P S OX 4eb r

• t

CE t

9 el 9h p S'

E I 1 FE 6FE 5SS

)

1

)

5 4t 1

(

2

(