ML19345F515

Safety Evaluation Re Potential Consequences of Refueling Accident Inside Containment

ML19345F515
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/30/1977
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML19345F514	List: ML19345F513 ML19345F515
References
NUDOCS 8102170764
Download: ML19345F515 (14)

Text

{{#Wiki_filter:- ATTACIM2iT 1 Revised June 1977 ( EVALUATION OF POTENTIAL CONSEQUENCES OF A REFUELING ACCIDENT INSIDE CONTAINMENT - BIG ROCK POINT PLA'IT CASE 1 - FUEL TRANSFER CASK DROP Discussion Amendment 10, Section 12 of the Big Rock Point Final Hazards Su= mary Report (FHSR) evaluated the drop of the fuel transfer cask onto the core.. The acci-dent was assumed to occur at twelve hours after shutdown with 22% of the fuel damaged resulting in the release of 520,000 curies of noble gases to contain-ment. All halogens were assumed to be scrubbed out in the vater and the con-sequences of the accident were concluded to be insignificant in comparison to the " maximum credible accident." The following evaluation of this accident utilizes Regulatory Guide 1.25 assumptions in adc.ition to FHSR assumptions considered applicable. In order to evaluate both the area monitors response time cnd off-site consequences, calculations were made for two cases: I

1. _No Mixing: The evolved activity does not dissipate appreciably and, i

therefore, provides a point source geometry to the erea monitor.* Since the activity does not mix with the containment atmosphere, the release rate outside the stack is eqral to the rate of activity escape from the reactor cavity. 2. Uniform Mixing: The evolved activity dissipates and mixes uniformly within the containment (free volume of 2.66E + 10 cc) to provide a semi-infinite cloud geometry to the area monitor. No credit is taken for the time required for the activity to diffuce throughout contaiment. 1 Since the off-site doses are directly dependent on the length of time necessary to isolate contaiment, both the isolation valve closure time and the area moni-tors response time must be considered. Assumptions maximizing the cavity re-lease rate would not be conservative for calculating the area monitor response time and, therefore, may not si ve the maximum off-site dose. In order to deter-i mine the conditions that result in the maximum off-site dose, both the no mixing and uniform mixing cases were further subdivided. Two extremes in radial peaking factors and two different occurrence times were combined to maximize in one case the cavity release rate and, in the other, the area monitor response time. These two subcases are: Accident occurs 12 hours after shutdown (FHSR) and the. radial peaking a a. factor equals 15 (RG 1.25). b. Accident octtrs 5 days after shutdown and the radial peaking factor j equals 0.6. The following assumptions are applicable to all the cases evaluated: ' Cloud diameter less than 1/3 source-to-detector distance. f 'k fyO2/70W I n

4 1. Fuel assumed to have an 80/20 U-235, Pu-239 fission mixture. 2. 22% of the fuel in the core is damaged (FHSR, Amendment 10). 3.' Reactor operation at 240 MW. g h. All gap activity from the damaged fuel is released. This consists of 10% of all noble gases and iodines in the rods, except Kr-85 and I-129 for which 30% is assumed (RG 1.25). 5 A decontamination factor of 100 is assumed for all iodines (RG 1.25). 6. Release occurs over a two-hour period (RG 1.25). New fuel storage area monitor alar =s at 85 mr/h (located - 8 m from 7 a. reactor vessel center line). b. Spent fuel pool area monitor alarms at 160 mr/h (located - 6 m from reactor vessel center line). 8. The following meteorological conditions exist per RG 1.25 a. Wind speed of 1 m/s. b. Uniform vind direction. c. A fumigation condition exists. These assumptions and the methodology described in Appendix A vere used to obtain the results contained in TabJ e I. Conclusions

1. - Area Monitor Response Times Response times are calculated in this study to range from instantaneous

(<< 1 second) to approximately 15 seconds for the extremes considered. If the new fuel storage area monitor fails for any reason, the spent fuel pool monitor, located approximately 6 meters from the reactor cav-ity, vill alarm at a level of 160 mr/h. Response times for this ranitor would range from instantaneous to approximately 16 seconds, given the same conservative bounds cssumed:for the new fuel storage area monitor. 2. Site Bouniary Dose The maximum site boundary gamma dose is conservatively calculated at 3.3 rads assuming stack release of all neble gases released to contain-ment (ie, no isolation). Automatic isolation of containment following ] an area monitor clarm would take approximately 6 seconds. The maximum i (_ site boundary thyroid dose would be approximately 2.h rads (7 seconds total time). If the provision for automatic isolation is not asailable by the next refueling, approximately lh minutes would be available for manual isolation before 10 CFR 100 (300 Ren) limits are reached. 2 1 i

^ i l CASE 2 - SINGLE BU' IDLE DROP Discussion-The drop of a single bundle onto the core can be evaluated using the conservative methodology of Appendix A and the assumptions for the cask drop (Case 1) with the exception of the percentage of core damage. - Damage of all the rods in a single bundle would result in the release of 1.2% of the core gap activity or 5.h% of the evolved activity in Case 1. Table II summarizes the effects of da= aging a single bundle.. Conclusions 1. Area Monitor Response Times 4 Response times for the new fuel storage area monitor are calculated in this study to range from approximately two seconds to approximately nine minutes for the extremes considered. If this monitor fails to alarm due to a I mechanical or electrical failure, the spent fuel pool area monitor response times are calculated to range from approximately two seconds to approximately. ~ five minutes. 2. Site Boundary Dose The drop of a single bundle and the resultant release of its gap activity would not result in off-site doses in excess of 10 CFR 100 limits even under the assumption of no isolation of containment. Automatic ~ isolation 'i following an area monitar alarm results in calculated tr.aximum site boundary doses of approximately 2.2 rads,_ thyroid and 0.252 millirad, ga=ma. i. J IP l 3-

[ TABLE Ia Fuel Transfer Cask Drop New Fuel Storage Area Monitor No Mixing Uniform Mixine Units P=1.5/T=12 h P=0.6/T=5 d P=1.5/T=12 h P=0.6/T=5 d-Area Monitor Response i Exposure Rate @ 1 s (10'm) mR/h 145' 5.6 897 3k 5 Response Time s <1 15 << 1 2.5 i Sit'e Boundary Dose d a. - Thyroid Dose Dose Rate @ l s Rad /s 0.35 0.06 0.35 0.06 ~ Total Dose Assu=ing Auto-matic Isolation Rad 2.4 2.2 0.001 0.0007 Total Time To Reach 10 CFR 100 LiMt Min lh 79 57 >2h b. Gamma Dose Dose Rate @ 1 s mrad /s 0.h5 0.017 0.h5 0.017 Total Dose Assuming Auto-matic Isolation mrad. 32 0.255 0.002 0.0h3 i Total Dose Assuming No Isolation-Rad 33 0.12 33 0.12 i 4 i ./ l(. ,_L,,_.-

TABLE Ib Fuel Transfer Cask Drop ~ Spent Fuel Fool Area Monitor No Mixing Uniform Mixing Units P=1.5/T=12 h P=0.6/T=5 d P=1.5/T=12_h_ P=0.6/T=5 5 Area Monitor Response l Exposure Rate @ 1 s (6 m) mR/h 233 10.0 1.h39 61.h f Response Time s < 1 16 u1 2.61 Site Foundary Dose i a. Thyroid Dose 4 Dose Rate-@ 1 s-Rad /s 0.35 0.06 0.35 0.06 4 j i Total Dose Assuming Auto- . i. matic Isolation Rad 2.h 2.5 0.001 0.0008 l t 1 j . Total Time To i l Reach 10 CFR 100 Limit Min ik 79 57 >2h ] b. Gamma Dose . Dose Rate 8 1 s mrad /s 0.h5 0.017 0.45 0.017 i 1 Total Dose Assuming Auto-i matic Isolation mrad 3.2 0.272 0.002-0.0th } Total Dose Assuming No ) Isolation Rad 3.3 0.12 33 0.12 J ) I 1 (. a t .. -, _ - ~ - -,, -... -,. w -.- r r- ,-ms-.. _ .c. r-r, i---

TABLE iia Single Bundle Drop New Fuel Storage Area No Mixing Uniform Mixing Units P=1.5/T=12 h P=0.6/T=5 d P=1 5/T=12 h P=0.6/T=5 d Area Monito';> Responce Exposure Rate @ l s (10 m) mR/h 7.8 0 302 h8.5 1.86 Response Time s 10 9 281 1.8 h5.7 Site Boundary Dose a. Thyroid Dose Dose Rate @ l s mrad /s 18.6 3.h 18.6 3.h Total' Dose Assuming Auto-matic Isolation mrad 31h 1,826 0.10 27 Total Dose Assuming No Isolation (and No Decay) Rad 13'. 25 13h 25 b. Ga==a Dose Dose Pate @ 1 s mrad /s 0.02 0.0009 0.02 0.0009 Total Dose Assuming Auto-matic Isolation mrad 0.34 0.252 0.0001 0.042 Total Dose Assuning No Isolation (and No Decay) erad 173 6.h8 173 6.h8 (

(~ TABLE iib Single Bundle Drop Spent Fuel Fool Area Monitor No Mixing Uniform Mixing Units P=1.5/T=12 h P=0.6/T=5 d P=1.5/T=12 h P=0.6/T=5 d Area Monitor Response J Exposure Rate @ 1 s (6 m) mR/h -12.5 0 54 77.8 3.32 Response Time (160 mR/h) s 12.8 296 2.1 h8.2 Site Boundary Dose i a. Thyroid Dose ~ Dose Rate @ 1 s nrad/s -18.6 3.k 18.6 -3.k Total Dose Assuming Auto-matic Isolation mrad 350 2,196 0.11 3.62 ] Total Dose Assu=ing No Isolation (and No Decay) Rad 13h 25 13h 25 ? l b. Gamma Dose Dose Rate @ 1 s mrad /s 0.02 0.0009 0.02 0.0009 Total Dose I Assuming Auto-matic Isolation mrad

• O.38 0.272 0.0001 0.0h3 Total Dose Assuming No Isolation (and No-Decay) mrad 173 6.48 173 6.48 l' ;

k i l

APPENDIX A Refueling Accident Calculations A. No Mixing Case 1. Area Monitor Response - Point Source Gec=etr,r 2 R/h = (C)(r)/s where C = reactor cavity release rate (Ci/s) T = ga=ma dose rate constant (R/h @ l m) s = distance to monitor (m) 2. Site Boundary Dose a. Thyroid Dose Rads /s = (C)(B)(R)(X/Q) 3 where B = breathing rate (3.hTE-Oh m 73) R = adult thyroid dose conversion factor per Reg Guide 1.25 (Rads /Ci inhaled) i-X/Q = atmospheric diffusion factor per Figure h, Reg Guide 1.25 (1.8E-OL s/m3) b. External Fnole Body Ga==a Dose, Semi-Infinite Cloud Rads /s = (0.25) (Ey) (C) (X/Q) where 0.25 = conversion from MeV to Roentgen @ 2n Ey = average ga==a energy per disintegration (MeV) B. Unifo = Mixing Case 1. Containment Accu =alation and Release Rate Accu =ulation Rate (dC/dt) = C (1 - TR) where TR = containment air turnover rate I I(10 cfm) (h72 !* )) 0.00018/s = 2.66E+10 cc k k i/ f t 1 Release Rate (dr/dt) = / dC/dt 0.00018 Lo i A-1

s. s 2., Area Monitor Response - Semi-Infinite Cloud Geometry t R/h' = (0.25) (3,600) (ly) I dc/dt r o where 3,600 = conversion from hours to seconds 3.' Site Boundary Dose a. Thyroid Dose t Rads /s = (B) (R) (X/Q) / dr/dt 2 i o b. External Whole Body Gama Dose t Rads /s = (0.25) (fy) (X/Q) I dr/dt o + 2 t j i. I A-2

A! z i.g -*- t - - i ta. s b E - 1} _--h - n__ s*-* I.,.n 1 mM.i t g P q u!q!] L,a pIHyl jij k y l p c

gp

p 4,

,7 J~.6 w,- j f>;b'al' p _p y 3 m m i n c.i T d g ;ii b T k i, b E EU j r s y-y !. N~jV. N._@g. - U d I. 37 t 41 ihb 'iYIh l Ili A m.y!il 3:.. # .[ ,w : lu 4,,u...m n. - nl_ l_- s a-r e,qrs e ut.+ y,2ilw, nig pg y A g g 41;g:g w p,.m .q

,e p__

is m.y.i s.w m.h ,5 e -r 2 1., a...

3),4 ;i 4 (m~)

l"s. w 4 I ~ lM!. M ~A,T h, y A, ~l' 1* T, ' ',' j et5 '! ;. n, jzy -e -.u-- e .f kM**l g -4 Q't,.d, f,

• la.J j :I, ' _l%ed;a j l

ma ? 3 m~ ..Yg . _ I -- l, M.i .e -+ -4 ( l .i 2

le o3L 4

1 es _,,,,,,4 g-4 g, 9 9 { )J

(

A

n-

[i $,, d. %l# .J..j!? i,,1 4O [ (F "- N

• a,~- C._J.!

1 F, . ~ 7 Trn ',> Rl ?A.1._A. l r e M. ..h 1; i 'l; s ' 2 0 9 -/- l ,a

• , ~ ' ~

.l-1 [ .g;n : 7 in i j 3 r_-,f,y. ---., ps l.,, ~, - - 3 p%,# 4-- .u .. s; .... l ' tr-~ a r. 6 d e/ t'lU [4 d9 l .g u y AM i C_L_{5.h qa .A ..y

+

g y 3 51

• O

.b s, t E8 % l4 I I .,P. I ra ~ ' t? ' N il,) +m l._. m'. c p1 f. p, l m:. j . n-j fij ? 'lgJp 2 d:3.L'f,._. y fl_; y g/ y e.; a s9xd, r. i 1 ,- a -p q. q g a q* y $ - s, 7, *::: - -l 1 '--.,gi.(kM d Ib i:. 6 4 t.3.d,- lM, h .!I_#,tt,i P?a" M, Whu, a?i p,h %r

i r.

s a,t ?*,. w .p a. t. M ~ 1 3 =h, D ', . Q ,Sv 4:7 d' .. d.-{g p;T j 'TFnO !!j u; W'i @- g>J e

L 7'- 3wJj u,

/ 4, p! -y e r i fv.1 . _,,V ' ' 7i p [ J. ]!.!, %.a!YilyNpy: il M.._)-

V y

3-m x p .y n.1;,!,.; 3k-ij,ld[ [< g ;4 j f [ 3~~ M - p32n wT.t--u( 3n .g n. o + w e, -l'

i. :n

.a i -a. i m'd 7 L 4: / \\ 3: . 'd.H. A f.a fg_. ) d.~,., ' - p'1, .. Q]g {h[4.,--- Q, 4 e . t 4 - W g,r s. u, 4 v ~ ~-~- ~'_,' l 3L T Ts b -~ .i a . h *!, C* Y /I M-~'-[gI ~ ~ ,L ' - - - - - ~ ~ - - - - - - . n-o s _ _ -* i, g b sf 7.)b.,,8! . w . - N, 4

• r 7.

8 . # ^ly * -- p ,h.u p, n$.,j:t 1 a i ...... 4... - --[ . N'.h I +.. '{g._ d**M 6 Y { d y ;,g i,, i, y_ 7, .......,j .sL' ' *D .v, j_ g {, ,g ~ '21'.... i __ N_ r 3._. .. i! l ivl fll 5-- -g-l _ms 1 @s,l 3.,,4 -g--

d. >J 8 I

'I f. J2j bi !!b

i

--!-,,!+etyl.j i y. m 7-e i i me - y d.. v 4 : -d -- Ll,1 ju aA :; s tm j _. e; y g u +s. ;7_ r, .4 g ,a 4 y t,, l '.* 3 4

jl; I l t.

't s p,.ii--+-+;-+- f + 4 ,,4 a ; 4 Iysiflgh;g:q n p;[;i!gi l g ! I !' :"" - 1-- .g j .; y Eg)j i f., s,j et i i,. _ _ _ __? _.___u_, ! ] 3 5 l i L-~; 3kII'bb Of! [ N 95P.,.., N' ( ~ q'~,'d,A i i ' ' 5: r!lljiili iii!!!s. !Ili '~5 1 ~ ' 1 e x 1r.) e w1

i As. SUPPLY Al. SUPPLT v&Lvt3 _~, AI. EINAUST v&LVES J _ PANS CONTROL _ ,SoLENolo VALytS _ Cv/40s. A cv/so, a, INoiC Af tom _ CV/do.4 4 Cv/40.S_j _iNotC aflou.--, y y y es est "h I C S* C9' t?il ,p> tesa., f tata .=9

_eg, 2,

o +i 3 ~..., . g, mO '' ]y,8" , it, gip g, Wp "8 3K w> 3r : lGCOS t *,3,,.. .,,**..sent Swas Y., < 8 i Sv 84 *: ": S. tii 3 F1> 4462 i,.. S

g"g, O

Svs3== eos to etsi t<> .v,, go gg g W> E Wi g, ?4> C () 2 2 3 2 2 2 2 2 G R G R G R G i i I I I e i e re. on C 20 *** 2,'y,*f,'",, T, 's n in = ges r os ro4 isiv o-C re e,. g olS T. e 20i 30 tot 203 e PANEL A" 24) [ I'> " "["55' "2 W 5 8 g N ~ 22 ,,,IE,,,II,,,I I,,, 'bes Pos 'p o s 5 091 EESTES E j stR4 l....: CLosto eTiri iT5 e,oa sion so CLosto ............ iv - so WNEN d 4 3 J 2nla WNEN 4 4 di v&Lvt 7 F vatyt ' 7*-" 'o st o i CL is orth v is oPEN gp cy es2 er. cero vaLvt as at O it re cLosto 2, a a E st.: cre O ese ag., E C CO w u e..., u,.. c2..-. y CLoSto sin wNaN s e mvt i. v<; <4; ap, f,,,,<; g eLoito.~/ p... 4 4 p SYS 4 q ,, 3 ,g g 3 3 .o .o .o <msn .,gite con m<>c.. REACTOR BUILDING VENT ISO L ATIO N V A LV E S c e., o SCHEME 8501 Cor 'Wl 1 i l.i ' ta t + l 31 o',_*,'. 5"=>

• --&..... ~

ii. M N Cor NIGH R ADI ATION VENT ISOL ATIO N CIRCUlf SCHEME 8511 i l --- ~. - - - - - - w

. ~.. BIG ROCK POINT PIANT. Reactor Building Ventilation Equipment Normally in Service During Refueling EQUIPMENT DESCRIPTION CAPACITY-LOCATION i Supply and Exhaust 36" fans 10,000 - 14,000 cfm Outlets of 24" Vent Air Fans Cycles containment air to stack and maintains supply and exhaust containment vacuum. air lines f Pipeway Coolers American Air Filter Company 3,000 - 6,000 cfm Floor elevation 6]#'% Unit No. V2270AC Circulates and cools air within the recirc pump cavity of containment. Heating and American Air Filter Company 6,000 cfm Floor elevations Ventilating Units Unit No. V2270AC 616' and 599' Circulates, heats and cools air within upper parts of containment (4 units) O "o NR P; M 1 4 w 1.

3, I I b =vn.. t n k;'f y ~ u ~ I h h 9 4=l>u:.M.y g l;;. ll gg is. "4 v- ; q: f 'j g(;J. l t. ~,v$ t s!.s T a' md e e [a 'f 4 m .$ l3 2 -S m l a i i 1 s r. 1 it i c.T; s 4.l'}lt- / ;..!(1 3$ A l} l; + o i :' 3 - t 4 c I I .I b $$ ci d 4.', o .i .y. d !) lt II 'I j;['{~ ]~][l)j 'M W .Ij { I* i j j,:, 4 e /NN l i s?

• ri a

-o n Em.!p !e; a, ,u

H 2

.<,.. t J;; i 1 ~* x.dl t d. _i

g

_.,;a_ L .q. g k) i,g y F ,, ~3;g';)!- - J _, ', ~ c. s !.0 [; ' + - e f g!1/ J ~ f e[ i 11, . i i. n . spgi p2 _sq g n. e,a - i, m

j

" r, $g-s g', is J r ;.,. J; 1 -,4 il l' s j8 A ,i cie,s, 'r n g.---.----q ] g < p< i n 3 *. o V f g 4 , p g. T. ' I' ' ' j w e,,.. q.e., gA'j e 5, ( 1 l 8 I.F ^ ' r3 p, .=g. l[,ik:. m., e m i@u e.ed ,s e _r. ' _ _ _ _ I t. - -S 3 q l -. i!!

M!

lle , ?U - -- -l'g;lj.p.w l! c. gg g -

• - :q-.-

v - e-eqli n l7 (

• i{

jjg ~M' i mi.]f

o u.v.

, g - fl Im.M k,I, !..f. j F ll l a ! E,l If I: ; 3.'

• _.a I

't i

-I

Cl I W.91 !!

i l ji H tsn*? - dl r l'd i mi ,i _2 i: ). ..r. n 7 _k - pw,,-- a tr o UIC4 pga,L_.4! f l,l' b' g a b; Cl - 9 ? d e i - w 'l 4 M Xt'.) { i g i E a { il - pla. a:1 n ., g ___ r- - ,,-a e p t,,e o e as e e es 3 e 4 d O b 1 4 .A g -w Y" o O M Oo Do w I 4 m

-s BIG ROCK POINT PLANT Devices Currently Associated with Containment Ventilation Isolation on High Radiation DEVICE DESCRIPTION SAFETY CLASS LOCATIC,N POWER SOURCE Area Monitors a) General Electric Gamma Detector 114B5778G4 Q-listed Reactor Terphenal suspended in polystyrene scintilation Deck detector optically coupled with a photomultiplier tube. Range 1 to 1,000 mR/hr. b) General Electric radiation monitor type NF01 Q-listed Control 120 V a-c 60 cps Includes d-c amplifier and trip circuit for Room Pan,el lY control room alarm and vent valve radiation (Turbine buildig; trip modules RS 8179 and RS 8180. electrical equipment panel) RS 8179 & RS 8180 High impedance millivolt alarm trip module for vent Q-listed Control 115 V t-c 60 cps (Scheme 8511) valve high radiation contact SVX5, Moore Industries Room Panel 1Y Model MVAO-10 V/X-X2/117AC. Contacts de-energized (Turbine b1dg, electrical open. equipment panel) SVXS Vent valve high radiation trip contact. Q-listed Control 115 V a-c 60 cps (Scheme ~ 8501 & 8511) General Electric relay 12HGA11J70 Room Panel lY Contact de-energizes open. (Turbine b1dg, electrical equipment pan Mn n

gy;M 195

7 u.s. nucle AR n 6mA wa r --

• h NRC DISTRIBUTION r=. ART 50 DOCKET MATERIAL

~ FROM: DATE 07 DOCUMENT g'.. Consumers Power Company 6/28/77 Jackson, Michigan o,7, ggegiv,o Mr. Don K. Davis David A. Bixel 7/1/77 kETTER ONoTORIZED PRCP INPUT FORM NUM8ER OF CCPfES RECEIVED ) _t I (o AJ G.8 Ml!!N AL LASSIPIE D accer I E N CLOSU R E IEScl.8?Ti1N ) I c a t t Consists of reque4ced additional information regardingpostula(edrefuelingaccidentinside f containment....... B0 NOT REM 0YE y_,, ACKNOWLEDGED. PLANT NAME: Big Rock Point /g DJL 7/1/77 FOR ACTION /INFORMATION ENVIRUNMENTAL 6 9AFEiv ASSIGNED AD: V. MOORE (LTR) __! ASSIGNED ADr I [ EANCH CHIEFt OAd(5 LG) BRANCH CHIEF: PRQJECT MANAGER: 9, L.-g PROJECT MANAGER: I LICENSING ASSISTANT: /bif LICENSING ASSISTANT: a.r B. HARLESS INTERNAL DISTRIBUTION ,T'x 7} orn *Tird 3 SYSTES SAFEIY PLANT SYSTEMS SITE SAFEIY & D T PDR HEINEMAN TEDESCO ENVIRON ANALYSIS / TAE [L/ SCHROEDER BENAROYA DEN'lYJN & MULLER ' / nri n T.ATNAS CRUTCMrTrt.D I 3CO'SSICK & STAFF ENGINEERING IPPOLITO [ 4AWifr# VNICHT F. ROSA ENVIRO TECH. I ERNST MToc BOSNAK V SIHVELL OPEFATING REACTORS BALLARD t a cA9E Anvn PAWLICTI STELLO YOUNGBLOOD I / ET9ENuMT Pan TFrT MANACEPTNT REACTOR SAFETY /I SHAO } cE0VF0f T ROSS /1 BAER P. COLLINS NOVAK [ BUTLER GAMMILL (2) l I HOUSTON ROSZTOCZY / GRIMES SITE ANALYSIS t VELT2 / CHECK VOLLMER MELTEE E BUNCH MR ATLI l SALTZMAN / J. COLLINS i KREG ER I RUT? ERG CONTR CL NUMBE R , EXTERNAL DISTRIBUTION IffLPDRt L@vltd J W 3r _ [/\\ l ,i,,'. i / TIC [ NSIC g / NAT LAB 7718200% I REG IV (J. HANCHETT)l l 2 /) / 16 CYS ACRS SENT CAI3GC PY U / / ( ( e.-----. ........}}