ML20101K579

From kanterella
Jump to navigation Jump to search
Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station
ML20101K579
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 06/25/1992
From: Tucker M
LONG ISLAND POWER AUTHORITY
To:
Shared Package
ML20101K578 List:
References
NUDOCS 9207060021
Download: ML20101K579 (26)


Text

{{#Wiki_filter:_ _-..- _ _ _ _ __...-.-. _ _ _ _ _ _ _. _ _ _ _ l i t I l t P l P Long Island Power Authority onoreham Decommissioning Project Shoreham Nuclear Power Station L 8 A Technical Report on Water Processing and-Water Management Activities for the Reactor stessure Vessel and Wet Cutting Station i l-l l Prepared By: M. P. Tucker to June 25, 1992 i 9207060021 920706 PDR ADOCK 05000322 W PDR _.,_,_,_..2--.. .a

Contents Page 3 Summary. Description of Equipment. 7 Water Processing Practices. 14 Final Treatment 17 Offsite Dose Consequences. 20 References. 23 List of Figures Page Figure 1, WC$ and RPV Filter Operations. 12 Figure 2, Filter Operational Modes. 13 Figure 3, Simplified Diagram of Water Flow Paths During Shoreham Decommissioning. 19 2

Summary This report describes the changes in equipment and practicos being utilized to maintain the quality of water in the Reactor Pressure Vessel (RPV) and Wet Cutting Station (WCS) which deviate from those described in the Shoreham Nuclear Power Station Decommissioning Plan (Reference 1) and the associated environmental assessment report (Reference 2). Details of operating procedures, radioactivity control levels, and water processing flow paths are provided to allow assessment of the impact of these changes on the overall ability to process and release liquid radioactive waste. The above documents state that water in the WCS and RPV will be processed and clarifled by use of an underwater, skid-1,nounted filter and dem' talizer system. As-presently installed, the processing equipment in the WCS and the RPV does not include the capability to domineralize the water. This change was made as a result uf revised cutting methods to be employed in the RPV and WCS during the decommissioning of Shoreham; specifically, the deletion of Metal Disintegration Machining (MDM) as a method to be utilized for RPV internals segmentation. The MDM process required that capabilities be provided to limit the conductivity of the water in the RPV and WCS. Excessive conductivity during MDM cutting can cause a dispersion of the current with resulting loss of control of the cutting process. Conductivity control is typically provided by operation of a domineralizer unit. With deletion of MDM as a 3

t 4 cutting and segmentation technique, the requirement for demineralizing the water was also removed. Deletion of the domineralizer units from the underwater processing equipment in the RPV and WCS provided several advantages. The most notable of these aret 1. removal of the need to handle and dispose of radioactively contaminated resin, 2. removal of safety considerations for regeneration of resin using bulk acids and caustics, 3. removal of the need to address (by design of the flitration unit) the potential for resin " blinding" (loss of efficiency) as a result of insoluble particles deposited in the resin bed, 4. simplification of the design and complexity of the filtration systems, 5. consolidation of the waste from RPV and WCS water processing activities into a single media type, 6. reduced potential for other contaminants (chelates, etc.) to becomo part of the waste media, and 7. removal of the potential for resin spillage or escape to the RPV and WCS through retention element

failure, A final benefit -derived.by deletion of the domineralization 4

1

equipment is a reocction in the volume of resin required to be disposed of as radioactive waste as a result of the Shoreham decommissioning. Domineralizer units are installed and in use as part of the permanent liquid radwaste system at Shoreham. Deletion of the domineralizers in the WCS or RPV filtration systems simply means that all removal of ionic radioactive impurities will take place in these existing resin volumes; a concentrating ef fect which leads to the statch reduction in radwaste volume. Removal of the domineralization equipment from the RPV and WCS causes no substantive impact to the conclusions reached in the environmental assessment of the decommissioning of the Shoreham Nuclear Power Station. Radioactive materials released into the RPV and WCS water as a result of cutting operations are primarily insoluble and, as such, are more appropriately removed by a mechanical filtration device rather than a resin bed. THs is not to imply that a resin bed would not remove insoluble m. "al but, in water treatment processes where domineralization is no, needed, a mechanical filter is a better choice. Because the soluble materials are such a small percent of the total radioactive contamination (estimated as 3.0 E-7 uCi/ml), the dosos to workers involved in segmentation activitias are not significantly increased. Radioactive contamination in water at a level of 1.0 E-6 uCi/ml would produce an cxposure rate of approximately 1 uRem/hr.

Further, the offsite dose estimates previously provided in Reference 3 which result from release of liquid radioactive waste 5

...- - ~.- . -... - ~. J 4 from the RPV and Wcs assume no removal of rt.Jioactivity in the RPV or WCS such that deletion of the domineralization equipment has no i 1 1 1 f f impact on those estimates. i Li i b l i 1 v J i 4 a i f e i, h ( 1 t 4 h i P i 6 I I l ,n....w--,++,- . i, n-. -,....n~.- -n ,r,,.. ,,-,,4.=..-~.+, ..,en ,L,-,. ,,. ~ e

i Description of Equipment R08 tiltration Unit nCS filtration unit is designed to provido a method of filtering water to maintain clarity and quality in the WCS in support of internals segmentation activities. The filtration unit 1 can also be used, as will be described later, to supplement filtration equipment in the RPV. The entire WCS filtri. tion unit, including discharge hose lines, is completely submerged in the WCS. The WCS filtration unit consists of a submersible pump located in the center of a pump housing tube. The pump housing tube is connected to four (4) filter housings by inlet section glenums at the bottom of each filter housing. Each filter housing contains a cartridge-type fiber filter capable of removing particles in the 10 micron to 50 micron size range, or larger. Decontamination factors (DF) can be estimated from the fiber filter efficiencies. A fiber filter of 10 micron size will removed 100% of insoluble particles sized at 10 microns or larger and 95% of particles smaller than 10 microns. Thus DF's for such mechanical fiber filters are typically between 50 and 100. During operation, two (2) of f & (.61 hinged filter lids are open and provide the suction flow path oc the pump. WCS water is drawn in through the center of the two (2) filters and the pump i discharges filtered water through a discharge see and hoses back to the WCS. The ends of the discharge lines are equipped with 7

_. -... _. _. _.. _. _ _ _ _ ~. _ -. i k 4 i i l diffusers. The remaining 'two '(2) ' filters Lare available as standby j: filters lor to support vacuuming skimming'or slag tank! operation. ? I The slag tank operates as a cyclone separator to separate plasma i slag and other_large solids that=could-damage the pump. It also 4 l provides for localized cleaning near cutting operations, if needed. i l These latter operations may be required to correct water conditions 4 in localized areas, remove surface debris, or remove accumulation l from the WCS floor prior to final draining of the WCS. i i The WCS filtration unit is equipped 'with suction-and ' discharge { isolation valves. Flow. elements'with remote readout are installed-l to monitor system performance-(such as pump--flow rate and filter loading). The clean filter flow. ate is approximately 550 GPM.. A I simplified flow diagram of ~ the - WCS filtration unit.is shown on i Figures 1 and 2. All water drained from the WCS is'sent to the j permanently installed lig;id radwaste system for processing prior. I to discharge. o the environment.- RPV Filtrt ?. q;L Cr i t The RPV fil' t at io. unit is _ a stand alone unit which is installed in i the RPV and is entirely submerged inside the RPV when in operation. It can be positioned within the RPV to filter water and maintain-clarity.and quality. The RPV filtration unit is-similar in design to the WCS filtration unit and about one half'the capacity. It . consists of a submersible pump located in a pump housing tube. The. l L pump housing is connected to two - (2) filter - housings by inlet - 8 i ,.-r-. yi-- p-,.Tw---- 9 y -&gw-- pgrMq-j u ny m g Vpg .,,wg.- g-.qq .g enp-u y-M y w.- .5 T'"vit*'TTN' FP'**'V' WN"' NTW M-4's.-pwt=-

l plenums. Each filter housing contains a cartridge-type fiber. filter capable of removing particles in the 10 micron to 50 micron size range, or larger. As described previously, fiber filters of this type have a DF of from 50 to 100. During operation, ona (1) of the two (2) hinged filter lids is open to provide a suction flow path to the pump. Water is drawn in through the filter and the pump discharges filtered water through a discharge Tee back to the RPV. The RPV filtration unit is not normally equipped with hoses or isolation valves. Instead, it is positioned in the RPV to provide maximum filtration benefit. The RPV filtration unit can also be used to support vacuuming and skimming operation. Furthermore, the RPV filtration unit can be utilized to supplement the WCS filtration unit should the need arise. A flow element with remote read out is installed to monitor system performance (pump flow rate and filter loading). The clean filter flow rate is approximately 300 GPM. A simplified flow diagram is shown on Figures 1 and 2. All water drained from the RPV is sent to the permanent liquid radwaste ' system for processing prior to discharge-to-the environment. RPV Transfer Pumo Tne RPV transfer pump, in conjunction with the WCS filtration unit, can be used to provide an alternate method of filtering water in the RPV. The RPV transfer pump is similar to 1.ne pump used in the ( WCS filtration unit. The RPV transfer pump i k. not normally 9 l

i l } installed in the RPV but can be installed to provide alternate or additional filtration of the water in the RPV, via the WCS 1 filtration unit, if needed. The RPV transfer pump can draw water directly from the RPV or through a slag tank which can be installed in the RPV. The slag tank operates as previously described for the WCS filtration unit. The RPV transfer pump discharge is connected through a hose to the suction of the WCS filtration unit filters. During this mode of operation, all four (4) hinged. filter lids would be closed and the RPV water would be filtered and pumped back via hose connections to the RPV by the WCS filtration unit pump. The pump discharge is equipped with a flow element and remote read out. The discharge hose in the RPV is equipped with a diffuser s ilar to those in the WCS. Water levels in the RPV are maintained by monitoring and balancing flows to and from the WCS filtration unit. In this mode of operation only the water in the RPV is being filtered. A simplified flow diagram is shown on Figures 1 and 2. RPV Bottom Head Filtration Unit The RPV bottom head filtration unit is an external unit located in j the shielded vessel pedestal area beneath the RPV. The unit is designed to aid in maintaining water quality in the vessel and provide an additional method of draining and sampling the RPV water. The filter housing'contains larger mesh filters (20 micron to 50 micron) than those installed in either the RPV or WCS 10

'l i filtration units since the purpose of this unit is not solely filtration. The area in which the filter housing is located is q typically not accessed (ie., not a high traf fic area). Appropriate radiological controls are established to minimize exposures which may result from the operation or maintenance of this unit. 1 A pump takes a suction from one of the CRD stub tabes and discharges through n filter back to the vessel through another CRD i i stub tube. Hoses are used to connect the various components of i this filtration unit both to themselves and the CRD stub tubes. Flow rate through the system is approximately 130 GPM. The filter vessel contains twelve (12) cartridge-type fiber filters capable of i removing particles of 20 micron size or larger. ' Drain connections and hoses are installed in the unit to provide a method for draining water-from the vessel to support decommissioning i activities. In addition, a sample connection on the suction side of the pump-has been installed to provide a sample point for RPV water. A simplified diagram is shown on Figure 1. e 11 4 i

WCS AND RPV FILTER OPERATIONS = , T2 _3 m 4 + (5-x, y4_______________________, l ,,,,,,,y,, ~ n v_,, a n,. a. =- M. i l 1 A-j i 9' A. ie. 8 g4 " :2 Om N M-VMMM [t 'A I> f .rs numan ~_._,,.o s -.__ra-- r%tt


ad I

1 Y_.&2-l l. -d -o w .ns

==. - ns,- - n1 - g e g 1 's V. g g l =- .m _m a = = ~. -M-sqJ L ] g i g cym@A m _ s,9 n_ l 5 n 3 5 rrv ntrums -.a win a J hy Gg_ etur no uste - o, a, t.y. r j s ( ,g r - ). . - m, / Ml* ,/ N / ii pl. , ~,. 'h I r P .r - m f,I NM5 N*M3 h 'N / trI sonow Man / 70 ta9 sasTE J" $AllP!Z POINT k' COMPCSITE FIG 1 +

4, M-+n m u SJ+ ,J: A 4 p3AJ--..4.p.+, -J. -,4 .J6 ..m--d LJ .JJA-m 4 -daz-- A. de -A1.sh., A saa _ ._ia. 4 I N l e e r i 8 M 3 5 en. g m e 0, g i e gli g-32 l %-vt l g r j.1 8"j bl z I \\ Ng hs an y a g8 big w' c : a 9= 7 a..g i u~ i rl i i esa qr p g, ca i ee r r f #l O Lp d f e@pfg bI 53 5 l h ,6g h,3 EhfE I i f-N I W~by $d 5g i -i I 3 Ese _L i .W-Ya i I" h m 8 ise)- .,1 i q i l-i- gd s Em s i+ 7 i e 2 e g y h d 1 1 l k g m g. } ,[ - 1 -g n; p i g-ve i Z g "b - ' .S ge I g-vn -{ i j? ?;h'a.ide-i b* h!.1 z. i o x .4 i i 8 7,ie p/F7 I du 1.rl d - F, f!m' e-i t - e g y! wm -y$ew i i 1 h st t ri-e-Id r l i i i G.Jh i _ d-b { \\s t s;9 {xci q-@ 7,===;! t i wv2 g p gd 1 =, 5 - i i -{ $h og s-

i. gg i

EEt L 3 -t i ug._3 _ I R. g 3 21 g g t W-~Y M 1 .,_..,..-.,__,;_-,-.~.,....--,-.,-..,,-

i i Water Processing Practices i Each of the-filtration units are operated on a "as-needed" basis. That is, there is no prescribed time of operation nor are there { specific - requirements-to operate the filtration units during: cutting operations. The RPV Bottom Head Filtration Unit is + typically operated on-a continuous basis although the pump is i secured during sampling and while draining water-from _the RPV. The l other filtration units in the RPV and WCS_are operated to support administrative 1y established radioactivity levels for water,in the RPV and WCS. As previously described in Reference 3, the maximum radioactivity concentration expected in either'the.RPV or WCS-is 4.44 E-5 uC1/ml. Operational levels have been established below this maximum concentration to ensure such a level is not exceeded. The operational levels selected _for-the early cutting operations in the RPV and WCS-reflect levels which are routinely detectable by ~ gamma-spectroscopic analysis in the-Shoreham _ Radiochemistry-i t Laboratory. A high level has been established which-is based on assumed deposition of. particulate radioactivity-fromL water contaminated at _ the high level and' the - ability to limit-the resulting surface contamination levels.. All operational levels.are subject.to revision as decommissioning personne1' gain _ experience ~ in the ' coordination of filtration and cutting activities and --- as_ a; 7 history of water rodioactivity levels is ' developed for the process. 14 ,,, _ _ _ _ _. _ - ~.__ __

l ] Nonetheless, all necessary measures will be taken to ensure the maximum radioactivity concentration listed above is not routinely or repeatedly exceeded. These measures included not only filtration of the water in the RPV and WCS, but may also involve draining water from the RPV or_WCS (to the permanently installed liquid radwaste system) and replacement with domineralized water. Filter Chances Filter changes in the WCS and RPV filtration units are performed using underwater tools. The need for filter changes is determined by pre-established radiation levels or as a result of reductions in flow caused by the accumulation of filtrate (typically 60% of the clean filter flow rate). Filter changes in the RPV bottom head filtration unit are performed when the filter differential pressure reaches a predetermined level and also if radiation exposure rates reached established limits. Draining Water From The RPV Two methods of draining the RPV are available; one through the permanent RPV bottom head drain and the other through the hoses connected to the RPV bottom head filtration unit. Prior to and during RPV internals.?cgmentation activities involving Dry Tube, Top Guide, Guide Rod and Feedwater Sparger removal, the bottom head drain is the preferred method. After these. internals segmentation activities are complete, the preferred method of draining the RPV is through the hoses connected to the RPV bottom head filtration 15

unit. All water drained from the RPV discharges to the permanently installed liquid radwaste system. Drainina Water From The Wet Cuttina Statt193 Two methods are available to drain water from the WCS. One method is to pump water from the WCS to the RPV using the WCS filtration unit and hoses connected between the WCS and RPV. Water thus transferred to the RPV is drained from the RPV as described presiously. The other method is to drain the WCS using the installed drain valves on the bottom of the WCS. All water drained from the WCS discharges to the permanently installed liquid radwaste system. l E 16

Final Treatment As described in Reference 3, the Reactor Building Floor Drains and Reactor Building Equipment Drains provide the ultimate disposal path for waste water from the RPV and WCS. Waste water meeting-the administrative levels for draining, is collected in either the Waste Collecting Tanks or the Floor Crain Collecting Tanks, as appropriate, where the water is further analyzed to determine the required treatment process prior to discharge. Station procedures provide guidelines for selection of the treatment process based upon analysis for radioactivity, Ph, conductivity and total suspended solids (TSS) in the waste water. Filters and/or demineralizers which are part of the Radwaste (Gil) Liquid Effluent Treatment System are utilized as needed to remove contaminants from the waste water. Af ter processing, the water is again collected in either the Discharge Sample Tanks or the Recovery Sample Tanks. Final sampling and analysis is performed to determine the suitability of the water for discharge to the environment. Figure 3 provides a functional diagram of the liquid radwaste treatment system. The proposed sequential decommissioning of this system remains as previously described in Reference 3 (LIPA Response 10) and includes the scheduling and equipment requirements necessary to adequately collect, sample, process, discharge and monitor the waste water generated from cutting activities in the 17

RPV and WCS prior to discharge to the environment. 18

4 'Y ' v%R-%%) Wf:y q'Oc^R'^'W*YNOW & & y QWMEW W M"@ -} 9 C e ' Y'M-M Q f f'$' { % ',"Zf-W %C ti.'4-2 W i-Q,ek Q y -y4^ :yz %. p ey,g%'% y y A y.i.&,:;_, {;h sgiNk LL:L:as.3 M.hiO4.sjQlsw.:-. ._ u x

k n

9 a < ;J.&.i'L:; - n x, '"?! D b } N 'n

+--

a '/d N y hi@ iE O yd Vif ?.~ fn:$ en 9 %a v1-p %o3 y: -q; m mu a c t j te 4 9J:{ y :Q D e c:. s:>_

  • o

}f';Y D ff' ) g [3 4 it W

w

{_? gcf c [ ae n t w ca 4 Qc P:2 pdE i e# ta e w m fa"= p#3 r y -g o p i: 4 e )w pj 2 y aw y, N,3, {^ r--- t' 4 FM r~'- ,gy p..t a, u.4 3s + -/ h.iA W d ,k hd. h f $d. a a p p e +-4 4 { K fid pij 3 p Fq 1 a t :4 O:a g=p--g y a J -[. A 21 r s-p + 5'

  • 3
r C

91* f. ~. ^ B n v* G g j(.,;@ 2 g V; L, V? w g l']4 m E <n.:ab4 n uw a i e .4 I o n.t $. p; 1 :- . d]g .n w L:fs Ig% E'. L3 7

M S

y;4)3 N g94 -19 q w 5, t y;. g; l bj h3 f r-M eg P A M }m, I a x x m a m x u [a .b ' C c I 5 E 2 p-y tc4 --w c a n - s

v., g b-.s g

bg d 4 .i:: b LM 4 r m ad pa a e (M 7 3 +- g %g gU g x m a N1 D 4 ~ = s '.3, g 3-2 m H n .g p n n:4 s-q m. n r J v:2 3, 3 'p O g g: p'q w w

== o 4 <j s-g g f.3,, /, m,"* m D N,: h M m um l-: 4 W h i "~~' h U O

)s On c.

Eh md d.y k n n (pdi f? Ch w _g .a g gn 7-- w., n H ou pt r-W x p pi f4 4 ,p fa m og iTa pl g E o %c.3 p g O m na a ww as p f I':) a l$ l Us&Y 'L. gg ( n a a p 5

O L

eK %r! $8s 4 ga_memmm,}'s y C ~(' & si H e la a e go g 9 ybaandC#1shahaamEMhss ,5 w d 9 }W 2 by u m f Ed d {+MW* +NM*.:#**T5??t*'?"'T*N*52] 3 i: om.ih=., aaaannum, -. o i hd mq tsa g p g Wt p i LR {W: Y g. 8 g[fQ D. "pU 3 O {;#4, g l':N m. k4 j c w-n a e m ('5i$ k ( h.C':} O M %' Mj 0;-a bli {S.] 3 s[ R5o ejis.. OQ c' cr n;u s -M vi im d:: M .W 'U x.; 4 ..;.y m y3a e

a...;

'q:) 4- +%, q a {p: .y 1 l'G;'l th

I S

3 l-~%l% f:.

p s,i
p 5

k, Q b,;. yl b O .f:; m c e s n hy Q e .s ' v::d:: ms ";;:a u w :s 4 n@M { e{h bA g-pp f, a y: +: k h g- . ?l g. h3 S. h!M m[$y ps 1mg 'a, F kN E @ m m m m w rr w m w & m W Ai a - w--auma W c r e M g-g g aa T 9 %} PN g "9 y ( y N td y c 5 B V. 4;n y c,. + e R

i:!,
g Q

$$-..~ v: WQTWWW: ; ?"3 ( f**"V""~' amn .aChm"a'*hbA7enus'WN un

j 1 ~ Offsite Dose Consequences Reference 3 (LIPA Response 22) provided dose _ estimates for liquid releases which result from decommissioning activities. Included in these dose estimates, were the discharges of waste water resulting from the cutting activities in the RPV and WCS. Briefly restated from Reference 3, an estimated 87,000 gallons and another 72,000 gallons of waste water will be discharged from the Wet Cutting Station and the Reactor Pressure Vessel, respectively. The dose estimate assumes a uniform radioactive contamination concentration in these waters equal to 4.44E-2 uCi/ml. It should be noted this is a factor of 1,000 greater than the expected maximum radioactivity contamination concentration in either the WCS or RPV. In the dose estimate provided in Reference 3, no removal of radioactive contamination is credited to-the filtration equipment installed in the RPV or WCS. All removal of contamination in the waste water is assumed to occur in the permanently installed liquid radwaste treatment system _ where a single-pass efficiency of 95% is assumed (DF equal to 20). Dose estimates for the discharge of the waste water from the RPV and WCS have been calculated utilizing the methodology provided in the Shoreham Of fsite Dose Calculation Manual (ODCM), Section 3.1.2, " Method 2: (Backup Method). " The estimated dose contributions 20

i I after each of two successive treatments in the permanent liquid 4 radwaste treatment system are provided below. A successive treatment implies a batch of waste water is collected, canpled, processed, recollected, resampled and found to be unsatisfactory for discharge to the environment. That batch of water is transferred from the discharge tank back to the original collecting tank, where the process is entirely repeated. Dose Estimate after 1 Treatment Source Estimate WCS 1.6 mRcm Child Whole Body 12 mrem Adult Organ (GI-LLI) 1 RPV 1.3 mrem Child Whole Body 10 mrem Adult Organ (GI-LLI) pose Estimate after 2 Treatments Source Estimate WCS 0.08 mrem Child Whole Body 0.6 mrem Adult Organ (GI-LLI) RPV 0.065 mrem Child Whole Body 0.5 mrem Adult Organ (GI-LLI) i The total dose estimate, as provided in Reference 3, is 0.148 mrem Child Whole Body and 1.1 mrem Adult Organ (GI-LLI). These doses compare well to the limits established by the ODCM, even if all releases occurred within a single calendar quarter. When compared to the total allowable dose for a three-year period, the above doses are minimal. The deletion of the domineralizer equipment as part of the water treatment process in the RPV and WCS does not 21 l

impact these dose estimates since, as previously described, the use of such equipment was not considered in the calculation of dose. Additionally, as previously described, the deletion of the domineralization equipment leads to a reduced volume of radioactive resin requiring disposal, t 22 l I 1

References 1. Shoreham Nuclear _ Power Station Decommissioning Plan. 2. Environmental Assessment and Finding of No Significant Impact 4 Related to the Order Authorizing Decommissioning of Shoreham Nuclear Power Station, Unit 1 (TAC NO. MSO951). 3. Shoreham Additional Information in Support of the Decommissioning-Plan for Shoreham Nuclear Power Station - Unit 1. (Working Meeting November 7, through 8, 1991), November 27, 1992. 23

1 ct: lg h,, a ll f i f t, i l ? I g e I J! 84 2B5 E I l l lf I il I If , g,f,i cJ uke =n.J l.l 8h. Ii -A eun r-r........ ... n l ::::::: ::.. : ll ... l [ c u-- eJW I-Y l . (. I u' -,e g -3 g w e mm4w-s..- ? l r I g

9 El c i-f. )I 4 l' llI t .i . (i U l I L j . h U l 'l N o !J ~ T B .H N IQ g M ~ f J ,,d .j [ U N, il i s- '3 = vr-8 J p,,- 1 Ill / n / W l i liil 'I fil! I I l l i l l t. l

s r io ad .4 4 ~3 1 I 5 a a o 8 s 2 d7 I 7 si \\d p-os 3-M .lA a 5 m E 6Rl_; l h 7* t e e o Y ~a$ c i ,Q = g, '@.,,Y f E< u ~ h y. ~ .Y h f& ... ) W f &l ? d t ~ t ; p , y,$- Mi,\\ l 5 l i e a sua 7 s .~ g y i l D p, p ~ 1 9 y I .a 2 t } .,ff. a &=~= ~1 ~ jj L y. s, e t a it; %LZZM ,/ h6 g l \\ Q v r g i r-7f i "(- +$ff'$41.6 s. m L,; l h sl 3 1 We

a,}

======. l r4 lf 3

  • f 9

ir g s j e. -.._ .J' = = 4-a '4 9 ^- 3 2 0 I ,... - - _ _}}