NUCLEARDIVISIONBaltimore,

MA R TIN COMPANY Maryland21203

Mail No. 845

February 12, 1965

Refer to:ACC-376

U. S. Atomic Energy CommissionDivision of Material LicensingWashington, D. C.

Attention: Mr. Robert Brinkman

Subject: Application for Byproduct Material License

Enclosure: (1) Application for Byproduct Material LicenseForm AEC-313

(2) Application for License for Radioisotope-Phosphor-

Photovoltaic-Generator (RPPG) - (3 copies)

Gentlemen:

The Martin Marietta Corporation, Middle River, Maryland herebymakes application for a byproduct material license to possess 100 curiespromethium-147 for utilization in research and development effort inconnection with Radioisotope -Phosphor-Photovoltaic -Generators (RPPG).

Attached is Form AEC-313 "Application for Byproduct MaterialLicense, and additional information supporting our application.

Very truly yours,

MARTIN MARIETTA CORPORATIONMARTIN COMPANY - Nuclear Division

C. W. KellerNuclear Accountability& Licensing Representative

CWK:mal

A DIVISION OF

MAJVrIETA

Form AEC-313 ATOMIC ENERGY COMMISSION form opproved.(5-58) APPLICATION FOR BYPRODUCT MATERIAL LICENSE Budget ..e... No. 38-,2027.4.

INSTRUCTIONS.-Complete Items 1 through 16 if this is an initial application. If application is for renewal of a license, com-plete only Items I through 7 and indicate new information or changes in the program as requested in Items 8 through 15. Usesupplemental sheets where necessary. Item 16 must be completed on all applicati6ns. Mail three copies to: U. S. Atomic EnergyCommission, Washington 25, D. C. Attention: Isotopes Branch, Division of Licensing and Regulation. Upon approval of thisapplication, the applicant will receive an AEC Byproduct Material License. An AEC Byproduct Material License is issued inaccordance with the general requirements contained in Title 10, Code of Federal Regulations, Part 30 and the Licensee is sub-ject to Title 10, Code of Federal Regulations, Port 20.

1. (a) NAME ANDSTREET ADDRESS OF APPLICANT. (Institution, firm, hospital, (b) STREET ADDRESS(ES) AT WHICH BYPRODUCT MATERIAL WILL BE USED. (ifperson, etc ) different from I (a).)

Martin Marietta Corporation Martin Marietta CorporationBaltimore, Maryland 21203 Middle River, MarylandInternal Mail No. 845

2. DEPARTMENT TO USE BYPRODUCT MATERIAL 3. PREVIOUS' LICENSE NUMBER(S). (If this is an application for renewal of olicense, please indicate and give number.)

Nuclear Division New Application.

4. INDIVIDUAL USER(S). (Name and title of individual(s) who will use or directly 5. RADIATION PROTECTION OFFICER (Name of person designated as radiation pro-supervise use of byproduct material. Give training and experience in Items 8 and tection officer if other than individual user. Attach resume of his trainisng and ex.9.) perience as in Items 8 and 9.)

F. Huffman, Staff Engineer R. J. Brisson, Supervisor - HealthJ. Neace, Senior Engineer Physics Section. Resume submitted

with March Z9, 1963 application forbyproduct license 19-1398-9.

6. (a) BYPRODUCT MATERIAL. (Elements (b) CHEMICAL AND/OR PHYSICAL FORM AND MAXIMUM NUMBER OF MILLICURIES OF EACH CHEMICAL AND/OR PHYS-and mass number of each.) ICAL FORM THAT YOU WILL POSSESS AT ANY ONE TIME. (If sealed source(s), also state name of manufacturer, model

number, number of sources and maximum activity per source.)

Promethium-147 100 curies as PmC13 in solution or as PmZO3 as powderor compact.

7, DESCRIBE PURPOSE FOR WHICH BYPRODUCT MATERIAL WILL BE USED. (If byproduct material is for "human use," supplement A (Form AEC-313a) must be com-pleted in lieu of this item. If byproduct naoterial is in the form of a sealed source, include the make and model number of the storage container and/or device inwhich the source will be stored and/or used.)

Please see attached application for license.

A.IPPLIXCiTION! FO

R O S ' E R . R - VOLTAIC.-.

fiNF:'Rif OR (FPPG)

CONITENTS

SECION A

I,: Introduction . .. . .. ... . .. . . .. . .

i1, Physical Location

II.H Radiotkot.ope Chaacteristici .

IV,. Safety Criteria

V, P1hosphor Preparation Procedure .. .

Vi. PS'PG Fabrication~

. II, Radioactive Waste Disposal, .

Id VIII. Hazard Evalu-uation, . I . . ..

.ig. re It.. .. .4. ..

-e~ l r~ 1 .. . .. . . .. ... .. ... . .. .. ...

2

2

4

7

9

10

12

SSCTXON £~,

i~ Description of 2t~ UediciogicalPragraz~t . .. ... 13

'SECTION •C

1.stmwa~ of Uaeorz

Fred Nornanu Eufi'u:an

jaoe5 C., Neac~eo,~ 0-

26

2&l

RU3?'ERENCES:

, 4 ; • nd ,z .-/ ,adley.- c -edin!3a ,ofhE E-leven'th', A"nrue1 Reea antd Deveje-

The i:bi~J(iea-D~ -v.r;ttecry,N i Ociiti

2~ NYS 9£AZ•4g ""StaWt, 1Lt c Plhcýsplnors to $r-,tv Radiation'

EEC? IQY A

applcatoa c th phaootaic cŽAoctvin tai (in~r~i~~

t~ico -a alax' call, ce~ll ccmnvrltS the phrsten2 intor an elect-rical

Q~tptby., riears 1of a P-M 3 Ntn? Zntin Toot-i

*CICC'stty mcx-d sfilzc~1•~h .revtae requirerd witfZh bright-,

AWsZ ;:mr-, rd~r~ 0 ~r-~d~d higttar than ior~Y~

j ~ ~ ~ ~ ~~~a 0raj3 ;~e~~n~i~. A conceptuiai design of a

/I r c', - r a( ooy ~ -v1- (fzPPG) untiliin

The' Y-a.-tr ~ tm .io rývjT0V3 I ' 0-znO .--:I R-, ht -sr rh. p, d~en n 81

of 1010h~ tYh-

U2..X~orrn'C-oating G ýC ~ tdosts yr'-z~z load-

ow*-~* -rt-c-,th

e. . t, 4..UJ C~. <&-,rei i.. ýý m 7 a ;:7', a ý -e

-~ rt ~5ThC "'~ ±iacpactc2P3e: tiatŽrhxra&

1 .1 .... . .TCA . LO,.nrAmznw

The phosphor coatIng, pr&oram will be lotzatoGd in the

radioiacotope laboratory (N4J 13-aildi1) of the Mavttn faciTitiec

at Middle fliver%, Yary~hittd., 731.Týi lac-ility '!z locat"ej Pa. a ifrd-tot-3

access- arealcp Ur a raa~triCted 00;ctor- Of hkMrtign prerOPtly.~ -?'ng-70

2 shows the location of the facility. The floor plan of tihe

radioiaotope Iaboratory is givren in, -im. e30r

14J P&-ý RADlOISOriVPE CH!ARACTERISTICS

The pprcmthiun-3I4-Y raoov ill be obtai-neds £rooa Oak

Rid.e Natleeni Laco~ratosy., The radRoLsotope w-Il be aged and

,necielt' p.r'."ssed io.r ei.-,m radiation and chemical imppurlities.

* Tho'&t~ CC k~c~flŽ~ ~'t~s~y isexpec-tesd to bo ap~eI

zs~hy-D O~ per. At-x'AC i0•' it,-4? TraT2 v~s A -24

(..o&,•, ;, ..... s g b , 3 . / (Yin"ga o? ....P)) w .l1 also po reseznt,

Pilo n~'ii?-~ ± be PmCi- -:h,. eC zl too Te cancezntra-

&o5~ vn.A b e mu, Xo;L, z t han Efl nod~ no A.e e1P rh '~ than a0uu rcgtl

The c ~hexcl rrit i~i~ hobeterthwa &SS peroo"nt0.

hat, rPP--- yar, it aw~ vinzim beta

(r- -1 cpTbi-esoe/ it i? eM14-"

A30

C-.T D 3-a" e.

IY'o SAt3METY CRIT"RIA

The liafl.hood of urdue radiatiton expasiwe and coantamina-

tlon will be rinimhized byv

I The ,ra-doisotopo hanriling proceduree irou-i r-eeipt

of the prornethi -- .. ... hloride, soluticn to w,.ste

di Sp0sal will be unrd:r the s0arveilEai " of

LMarti:. Comipany L:oait.h Physics Sectiozr

2, The radfir•ot~on laboratory i3 relatively iola.to.d,,

has f"itered aEndt.latior,+ and continuous sanplog

of the Btack- The atzosphere •.n the work

area is continucct.y ea-mped for airborne radio-

aC•ivity trogi the use Oa? a ,onstaxd air mionitor0

3.- All ra 112.1he1.otoppc handling will take place inside aN

4c at.te•ý! Pu. LaW. 20C-4;,04 glove bor. equi.pod with an

-Iecý! a.,rdk ai- filters"

A negativeo pr"esure ,l' at least 1/4 inch water

F..ua.e 11l14 wt1a.,.d Within the te o GloCve

p•or•; cer, wil. •2trd Protection wehen the glove

cog'izct• S-S abf- t.i.'-Sier' to th.e filtered

ojxh~auc-t, oy-toJt iKJ' £at.'lr--.Lf~i%¾

O., Cold rum; of th, . wet ohezistry apeatiou; will >ae

to .&Za. e th. coutit"I~ proc nrund to. -st-aLMi--;1q aate

5. Initial radioisotope runs will be at a maxiwum

activity of 10 millicuries in order to further

refine the handling procedures,

6. Typical wet chemistry operations will involve

batches of approximately one curaie (ten curie

maximum).

7. The maximuxm promethiuw chloride solution inventory

Inside the glove box wzll be reztricted to 20 curies,

Vo PUOSPiORi P1-EPARATION PIOCEDURE

The gemeral phosphor coating operation is outlined belowy.

The specific loadizg procedu-es zwill be developed using mock

lue! (saz-ariam) coatinga -, iiandlin& techn..iques •All be refined

dur•.nr iznitial h!ot runs w'hich ar.-e restricted to loading of lees

than 10 'iiues

* , Concent.;ration of; tohe PrmCi3 sotlu.tion is not expected

to :-1n che event thm4entraton Lg

roequire'A, a nuitable quantiýy of PrCIL soluation

tie-, tafrrepf.om the ahipn'nti. t a

" bea",,zke.. The solution wili be slowly

CcK2snrctcito on. 2000.m/r 4 with either a hot

2 . cz onnt r-ate -ao n ic. etranerr ed tod th

'Yooe and PtZL so.lutio0 n

;;;~rtt-- t"adde6d rt i! P-reciriltatior

~;o.~ pic.n~.2i~csae earth' t-gylloxidec-s a~re inasoluble

in near neutral solutionst, promethium will be

precipitated as 13M(O1) 3 which coaeulates around

the suspended phosphor particles. The supernatant

is then transferred into an absorbing mediunt in a

plastic waste bottle- The coated phosphor is dried

over a hot plate or with a heat lamp. In drying the

hydroxide is converted to a coati•g of Pm2 o V .This

configuration favors the efficient conversion of

beta energy to light by minisizina the beta aelf

absorption-,

4. The Pm 0 coatead phosphor is next transferred to a

polystyrene capsule uaed as the source holder, The

seurce ie ocaled with. polystyrene cesento

V1. RPPPG FABRICATION

A sketch of the t.eipat-ed RPPG configuration is shown

in Fig. I.. After the ccatad phosphor ia sealed in a polystyaene

capsule, the plastie button will be checked for contamination

and cleaned as required prioa3 to removal through the air lock

fero evaluation as a light so-uceo The inte-rity of the

olystyene cpsal willbe checked by iowersing the capsule

in di lled aaor for a period of one day, The distilled

water %Ywill thezn be evaporated and the residue counted. Ainy

. O ccunta- aoove hjac1,groun6 wil be evidente of a

u're vhich ,%•.Ji be J.`ther disposed of or repai.reEo

Polystyrene encapsulation is chosen on the basis of its

stability to radiation (Ref, 2). The preparatrion areas will

be decontaminated as required to preclude the transfer of

contamination out of the glove box.,

All source removals (eog., encapsulated light sources or

planchetG) will be through the air lock after being placed in

a closed shielded containier by suitable handling tools0 When

not in use the light sources will be stored in a closed and

labelled shielded contaiaer in a filtered hood. Optical.

evaluation of the sealed light source will take place in the

counting roora of the critical facility (KC Building, refer to

Fig .2) which is adjacent to KJ Building,

Selected light soures will be combined with photovoltaic

eeils to fork coomplete radiolsotope-phosphor-phrtovoltaie-

generator• (1ýNGs)-. Shields and handling tools will be used

to riinimize e.Eternal. radiation exposure during fabrication,

The asrembled phosphor-photocel sandwich will be placed in

a shield and sealed in plastic for additienal protecton.•

The Bhield will reduce the RPPG dose rate to less than 10 mr/hr,ý

Li... ht sourcee not uced i-' RPPG fabrication vlll be w-raitored for

light deg;datieon and leakage of radioactive iaterial;

Vill r{ADICTW A$TM? .... DISP0SAL

S~i ~t~~~wt eea~d Ur,-'jrP% eonrce, preparati~on

bil e reeQ;o!Cd r' t g~oa'o iienu i.ln fid

tle';Tiqa.ee sealed in a pla t-ic baff and placed in za closed-

I.OX appr-oved waste contairier for uitiatate disposal. a" an

approved site,, Liquid wastes uhall be poured into an absorbing

medium in plastiz-- bottles and handled as solids,

V1111 HAZARD EVALUATION

The external radiation hzard arises from the harder

couiponents of the soft brenastrat~±ung produced by the Pm-147

beta. For light shieldinagv the Pei-146 contribution to the dose

ratc is vecry giuch leias tihari that of the PeR-147 bremsstrahlung,ý

The radiciaotope is suifffJciently aged and piurifled so that the

Pm-.146 iupturity as well, as europlum~ and rniericium tracce

aetjrit~m ake negl1ýiblo contribut~ion. to the as rate..

Calculati ocs 31io that t ypi cal stwuface bremsstrahluxng

d c.t5 rates on i't 61ce-nical glasswar'e surface will range around

'0 IR/hr for one c.-ic of azed Po~ in the configuzration shown

.RFig,, 4, ioevý th'it lo-w elnrg~y radilatien is rapidly

attennated,, Local1 low ato*.,-"c apamer s hel-ding and handling,

tools -V1AII be used to re~nce perounel. expezure, The dry,

bo oveS wves prcvide b"-Ata ad the design of the

ph~o~phcr coating apparctt-v 'vtii. miimz the, bema-strahliung

d(Bs'e tqo tho bhancz v-.1 ar wtz Dcubi~e gloves will be rased

to make 1':aad c2Kntar..U-at* O..e Phomphox' coating

epe'atnn on an i-box tra and spills, if any7,

Thu dose rate at the surface of the encapsulated phosphor

bultton is expected to be about 100 R/hr (Ref., 1) of predominately

low penetrating radiationc. Tongo, shielding, distance and

minigiun handling time will be used to reduce exposure from the

sealed phosphor button0 The stt.face dose rate from a eompleted

•IU'PG generator will be less than 10 mr/hw.,

The on.ly inflammable materials which are required in the

glove box are a snall quaatity of polystyrene cement and a few

absorbent wipes. as r equired0 In additlon. electrical power

will be supplied to the glove box only when responsible personnel

are in attenýlance and glove port's will he covered when the

box is not iAn usCr I, Thus, any fitre hazard cL- danger from cU plosion

Anside the glove bwoul. d nppcar to be re..ote.

,-i.Sail nwitehes are instal.).ed ½i the exhaust duct of the m&ai).

sysztem to provide an air'm to indicate etnhaust system Malfunctioonand~u~o~a•Ical~y swittch tc., ... orr ..d a atalytem oncy power. Vilters on both

the •intake and exhaust ,ill1 prevent radioisotope leakage from

theglove box in 1the. lXowv; prohab.ality case of ventilation loso

from both normial and erergency .

40he c30r credible vccident .ould he a snill -ithiL theglv.e box. dur!n.. the ..pho.•• r_ coatinz procedg. As in the case

Of e4h±u:3tZ San faluei ý.,3 'y Awill be contarineUýOr the 1asis ;l tlhe it.ewein topL.'t- i appevm'

a rI; I abicaIo no t l . inenthaard t0 fac-lif.ty

1~~

Pages 15 through 16 redacted for the following reasons:----------------------------(b)(4)

Fig. - -11-

I I 'I W IFg.2.A C~ FROMSURFACEOU, e

ofOeCreo Age Pm4 in Aqeu Souin(oert

ita000on i

-

- ----- -

-

6 •-

t~ f.

.I2 3 4

Fi.4D[TNEFO SRFC FSUCICE

Dos Rate vs.itnefo ufc fClnrclSuc

of On Cui ofAe":1 inAuosSltin(oert

is giena ponPln h idln f esuc)

SECTION B

-13-

a. t Cat.-~ Yz4. o -r'Cýf t i vL t r, 9La f c t

~7-xV" 0ht taJ. CC rA 0622 -jaw)

T -Lm.c. react. rt

~~f;l !Z~r T,2-c. 'CK - mr r:c

(A~~~~~r wi na~'t- ~.~. t

a9 o4, o- c~Xst

-.O ie.ii .IMI -lo *9. soji-4 .&mv -

pz.grw zzppcrtm the - uflew ac cticma; ..

-14-

pl2aeSp2; haot call operatio, at4

,,,, Lar• s3vas~Q oa'iy~otmext&X zeoitoI~ia• aMd ,•atte diarsal•

•adaten r••e~le radicac tivenai@m ii. .r' :loftatioi• prbha&! "0

'Mle• lovise" e• •e a h rda io rtieate f•:

the!° @• assgmncairea~ aM'e.S.,uatr~eh tatifr dotelop• sa~t9c~u

pth w aor, ati olv(; Y-rGtd, aiyn

Tl h Zeeitlatphv*h • t c is SA.o perov:ctiv c-orpieto Capability fori

radia-tion pr~tol:.a.,on mnax-,gement om a oie'yoicoofaeffort bacio. IlaG

Suporric@•s -2ealtb '-Raynioc SC-tioa cor to the ObeSsf "aoiUrýty

I atsent lwho it ot to t"v a fsenetiof Support D:vlr4a'ioa,

In addition~ he rer-vrtv. Oa a "Uot tot i'W~ O the V'ice r-residont0

UcletIar Divziocln and Gervea wn th~e reMiation protectiosa offtioer0

T-bw Rea3lt TPaýyz!Qc st'aff Coo tnit of heoalth physlicits who' tire

prt"arily rpoitt for the adiat~iou pretetioa provx~z an

the wr. a-ssigrne areaso o'vez> aact staeffý -ornber Participates

intetotal p~egran- and anxy (-ne Cen fy'ntrtioa in any' locatiorn.

St~vveyo are vcxil tofrzdby A gevoup of technieiana Uiidur

ttw emeveOF ofa hoci thphsct

RL adiationi - Contatcirsationz Ccatrol Kheazltwss

AtaXtg-Ouetion

Starwvey cind co2trol euc are ntizdto evalvate racfloo

logiQ )a~ar& and~tabii~heffectiTOeco'entrol Meaet!xrest ls

'peruon.'al ezy-t-reo0 Mewa snsrveys a-ev eondu-vted to determine

radiation level<o the reso0nae or absence of surface coutanination

-15-

a~~cwae~i vŽazoaztt~y cx, -saýuw areas. Ilmstmrc

.G e Uh-ao • ccEctrca pCical. Safety Program lse

dencibeGin. Tab'le

As o, 1res&nlt Of. tblee e'y s6tablc -co 0tro1 rneasurevf are

activeomatorias w:c adceatrA yeron att 0120 - 'ii?•,•# tzrsdnc

a e-tea t e -6 tMa zCaro r•!-'eyc i y the .ro1rk ar

by a•.tstng oaith •iosŽ?n fez atior iOf ail eullrwys, are recorde

otre, 11 eperat l x-oz 1 lona! e

rthable tf •oztz .strt- or

insvmen cmain ac!ni vlaed ta eer•Ioy arr '•heer wit ofe

tlhw rAiation to oi•t k Aol P rb12 iastr unea• e

are-c~ at lea=t Gave ovary3 mornt- and after cach repair.

Ea'Aa area wbr ttta' materialrc are utilized is surve~yed

for tiac rrooonmc of fixed ean tsacsatttnti7e b fr-equency

of thfeac *-mrueys imwrndb tlie mi"ntre ?Lrd type' of' Owaratioms

yer,ýfor7:,m Q & An aceelewntcO ;re eoezla is enloyed dtkyins the

imitial plaau-Oo of any me- wcr.R orý chang'o in trork iatilsinz' radio--

activ'e matoerials o deerntc any Viuntzu-m radiological ha~zard.

Theroafter, a gen---ral cdhatly zurv-ey is~ae dia the Tork area

at locationo which, are ;mc'cýt lihsly t1o inUdtoatat ChaA gesin oontaam-

Inationm le-Voelti If, thiiasgeacrol asurvey indicates an in.raei

ccnaainaton Levl ~ o etatedaarvoy ic iniatiated to datermiv~o

thecaW and institulte meaellres to Podtmco or possibly eliminate

the sotWrce of contaninatipn 0

&oaom contanination Is evaluated employring the wipe temihnique

which consists of wiping an- absorbent paper % ver Ean area Og'

-16-

appr~q natoZly 100 =2and coc'wst-ing tbho nipo ia2 a Ohielded detector-

Fixedcot atc3 2rr"01r.a a:-?O znnxtwc corGploying Poertable mono

itoring~~e•t

D. Contamination Criteriat

Th'e cotcrntincrtri Grrntly in lice is,!

Uorestricoted Area R•atorable Ft sod

Gross Be&tGao mma 1000 tqyw/100 =2 0.2 mrVad/kr v0approx. I In.

Gross A pha (Tranauranirc 100 @m/vO0 Vm2 1000 dpm/6O cm2

Cgross 3,0.0~s~ 10OG0 dpvlioa (cn2 1.0 meac/hr- 0approo in 0o

Groes Alieha (TransczrarK-SO4le0 r 10,000 dpxm/6O rm 2

foements )

,M Surface Conttnirvation Coatr-o2l

&c-rac ýz•c! cootamnnatiotz .Q c clied in tho laboratory area by

esMPieyFitg onaR o- 1A Gi 5ti'a tho £otlUoving te-rhniqnea?,

I~. PqrroaEng ro.nr eus''eya to ctermino olevels

2= Prord!{ttg filtered vwntilaitim. at the souroc of 4elpersable

contaminan.te

3- Establihsg isoaa-ted .arasea ttos aisporab3.e contanhimants aro

geuerated.

4I Utflizing absorbent e•apere cl.yethy1eua and coatings on equip-

me-t and o Lauginl those durim the Course of the work,.

5o Requiring the use of autt'centsmtnatioa clothing0

The spead of disporsable owstamicants to unreetrtcted areas i%

minimized by:

-17--

,Est.ab1•.sh_7ng buffeyT 7onr- betweein the aroan and providing

2b onzterng ptranncf at the point of egress from the work

S30 lMitor5.g equipient amd, v°tflizng azn eqipment obect tag

* system.

4° Providinr revoptablcs ftr voatlv!;iaated wacte- amd uzed anti-

cork twardzazt±0r4 oloth'incg

5 Controlling the weayritg of anticcovtwuiation clothing out-

cide of a restricted area.

Note: (Aati-cor4tamination clothing in not alloed inICompany Cafeteriao0 )

YFo Personne1l Contamination CDontol

Anticonjtnminatloa Clothing requirements are specified by Health

Physivs prier to starting any operatiou whoe, potential con=amiuants

naoy be encountere6 These requ•r•ments are bazed upon operational

Ln-perlient anad/o P urvey .. .tm..

Ant~~ora~mtzatonclothinz in le~nse after use in aL MarCiU

Comp uadyY~~yrecfcal cala fcr cctaminatod -clothing0

¶ao la undry wasteo are handlad and dLposed of in accordance with

IOCF•Ra• Laundeore items are monit ored on a random b•e.s sine•

operating erperSemiae ine adicated offective decontamination of the

G±othingý Furthermore, highly Contaminated iteme are segregated and

.avndered F-eparately Qr discarded as solid radioactive waste.

o D'nCriptien cf DeOf ontn tio. Tcehniques

Floor coatrination is nor•maly removed by sar,ýIbbing with mor

mad detergent solltions0 Persistent contamtatiom is removed by

emploxing a Mecbmnical scrubbe- and steel wool pads. The scrub

selution ie removed with a wet type vacuum zleaner and finally

-18-

Bqupzent con t i-r~aia-on in ror'ove by Gcrubflig wlith detergents

carroF~ion, Cotzize anul~n q~telmp n ie r

IOVOI contumiwati.Qi !n doimtdf- in 6omitatizalted are=-a.

Tho laborntoz~ i aquljpc uV-' a caaiwaotuw Air 211outor

of their' S=Por in r~iio to Go1e ae&pleg of tke atmos~pher-e

adjaentto tile 1rbr M;?Oa. .act monitor ±o adjuted to datiectv

Furherare te - oniturng unit 1,,s enppe with an audibl~e and~

vimal aarn ~ic ~ta atatoCif~ thle e1born radioactivwity exdeoeds

the pzrerseoE level.

Ad~itionA1 24 ihouw air sumpea ar* collacted from the ventilation

systomexhaust stact mad ale-* anaxygd edai1: durzing the w~orkr weak,.

to thoeiiio,. ni t otwk sampling 0qzipmez~tconsistis of a

vacaun sytw -vn apTztt I eft pa filter ass~embly. Air

zwnlwýar colotOQd w~ag snIltu f±ilter holdorro coat~a1in filter

pme whllo to greater thzia 95%,6 1i(ot~ for *ojleeting air p-t

tculatea~ greater th- Go.K z~aran in diameter.

Air sameple ftIlters are eofanted and analyzed employing g~a flow

proportiona~l detect-e-aler assemblies. This pro~.du'o can

-19-

&dafqatoly doter'mbnr& lovei~a as o oz 1~ x. 10 -lp ue/21Q

1, wipe Testing Encar~ulateo sanrco

Ea.ch ne~aled~ light oaur-cc wY2-i' be surveyd, tra verify sorco

integrity prior~ to .iozove1 fro the. glove boxo 'herefer, the

cors w~11 be inzpecteri freqtinly to ezlr .continued cap~uent

tase~t will bezde m- at laeat 6 month inerveIG

If tho reve a1m tile precoc of OCO05, microcurle or zwer

ofre~onavbli (,omitrmination upi a 1W ~ ~ v~oxt wpe O~eat1

tbhe vo vra.ý wiLll bo rpair~ed and/or. d ovantiu ted, aind ireteste~p

If racpal? of. a votrce is 1i.pra-0t~ic01,; the source will be dlieoaxded

Us radioaetia vast~e

JSource Rc pe i p pection

Af tqr reýýCipt ýZkt~ o i. the ship~n Container abn~tair-

in ~ P i I1Aa '31 be u yod for external radation

C atami.& top, 2.;V'V~el and r'11vVO&~ rk~on th!A dalivery vehi)oleq Tho

delive-_y vohi~cU will. be isevy4d prior 'G releane from M4artin

The shipping container wi-3l be traaf errod to a head ventilated

thrugha high OfJ~ic~enicy fitez', The otter container will be

opened i. the hood to expeae the inner, prpzary container. This

container' will bo vieually inspected for. dmaffa aad thela Caral -Ully

removed fror. the outetr contataner. Kxteadbd handlizg toolasil wi

erMyloyed rep~dias on Ourvey daa The prinary container wi2ll be

bi~rveye d ?or external rad:LUAlo and coatamdhatioa, amd decontaminated

rhon necessar7- The contain~er will tanbe transferred and stored

beh-ind the ahield in tho glaov box. If the promethiuam is not

~Imediately r'equired., it will1 be atored in a shielded area within a

filterod, vntil~.ted anclosuro.

-20-

•II o Per ande i,.oaitoring.

Porecsz.ei ozpowwo survcillanco is perwformed to meaare the amCunt

o f ezteraal and izternal radiation erproscwre received by indiviAdas.

vshcoo morI; involves expoetc~re tc;ioisn radiation.

a. Film Badges'

All p cannel pvx'anontly aaaiwgocd o wrk in areac wherne ex.

Dnro-rr to ionnisiutt; rctdiatior.-is l~l are required to weamr film,

tadges0 Additiowzl monitolAnsg evicee are iasned as dictated by

the typo Cf rworo: Derr-me 1z-il. haedges are currently supplied anO

pIo*nesaed by Uealth Phyaico Services B 3altimore, Maryland,

Botaokgazia film io used in all CaGoD Whon Dertionnel monitoring,• "is r•quir-oi whe'eas neutron fifM is used onml when personnel are

expooEd to nevtron radiation 0a Film pac,--eta are peoceoso$ and evaluated

qust~ly, fter any smarcvct orý Unue-nal eSXposure an in-~

dicated by ppeu't wysnitoniný 4evicos0 Vrisitore are manitored

in accordance with 100F200 2020

C., Bicascay

422 poraeonneel whosa w4rk involves the handlinig, of radioactive

materials ar pyeziod!ially ochodaleO to mbmnit bicasay samples for

analysia to aid in- deterzmiining ex-anroe to concentrations of radloc

acti're materialsb In the case 0f c•puooted bedy ±ntate of radio.

active M•r-tials" special sawpýIca are vollected from tge personnel

Inv-olved and anam-yned0

0 o Recordes

Results of all personnel exposures are posted in the ind.ividual's

expoeure file whore a cumulative exposure record is maintained.

-21-

A0 nltroduction

All.rdais oe' inis'rz t arca calibratetR employing

radatia tandarda Swtz orde-r tv aessure proper cpera~tion anad

Bz Portable PRndiat•.oa Detection latrwae at

Al.2. pes rw.l mtetreRa are cviibrated at least once every

tthOe Month-- Qr affareah, P-arvcwo.g 0

leta-ganM detection istaeots ar•e calbrated utiltimig a one

cnart C srso rate" rat Varyinga is

de!rminad emplcodag-i a Reatgon "Rll raeter calibrateed e by M-1 eo The

ei t --rum G r, t ca•.in. ay Placed, eat P0ge- dista! ho from the i ounco

wea adZaoe to -ead the ra i ta t tc

Tead e -Iaio Uox"oin d~e%- z ucistance.hok

. lers Vonible eeayh inethnJ Cs checked at two yoiatn Thi each

V1 "alai or- rangoe spttir,& SUA2ier sources are vized to calibrate low

rangc (O~O nu/s) :tr'acata Thes V--e 1acludv a 1 mg 11.1m ~

5 a CO s ,ce b

£~amavarvoy inatrunentB aecalibr'ateg a-ingC PP2Z*6 BDo: (25 me)

or, " (10C) SOUTces of hu-&Own k Calibratiom is pe~kr=ormd

okut of doora to r-educe scattering from bn~ig al~ etc, The

inaraeloi adjumted to re&Ad the calcukated5 ne~jtronc dose rate

af ter adjsuztIg the bias agatnat g~ardain

Alpha surveQy metra are calibrated employing reference sources of

oranirum and, plutonium amd, adJuasted. to- read the known value in Counts

pT1% Miz te baced tap-ou.14z Crek'uf~acta ereorndaic concerning

counter- etficienc'yF&

O,- Area Radiation Monjitoring System

The area. radiation. monitoring detectore are functionally checked

at least Once evrOy 3 months or, after each servicing. This check

:z;e x ic-so o-N' GOIt-ReO a I a R SOrve placd a" Varyin~g

tbo erace4lb 'Mdo AX.'2Z in orde to chav" thO reOponase of 'Sh

detecta,-. ~FI i;o notor roading vao 1oyond 20% from th tM

reaiý,,tlao equipmn io a~jitz-td andr/cor vopairasl

All eo1u.tirag ",vr i~v~untte ian is chce daily' foa, back-~

reeec se2reas are~ Tlced in ea-ch.dotootor and couinte for

weac __ tiao, 1 cg-aixed talcutis recordeed in~ a

10g If IVŽe k-eaiage war get~e than flhe ctilculateid

st"ZU0 ex-ror it~ to .- nibrated by plotting 3aure counts

-5eats igh ve-Iageiott~ing to etablih the proper vounide

vot-e z The Conater afft.ciatvy is them detrmined by conparing

thne counter coutat ratc- xrlh that ok the ztwanrard soaawee

Mr2or repal't and~ UZqtrent calibration mro.xeperformaed by Health

Pbhycic poaraam-ao1ý Ne~Joi repairr, ar prforwied by the facility*

ir~~ow.1 ýb;ia Y~l~ i~ M& tM~nM porW.Zont record;

of al-- intrmtt c2Thratians and ropalr reeo.-dt arc. maintained

bytile ianýýrumvt technicnn' Each isstrureat iz tagFe ~Actu

the talibraition end recallrtion dtate.

-23-

RADIATION DETE-7CTION INSTRWIPTS AND RETATED EQ.*ff1R-.W

TYPE OF INSTRUMENT RWADiATIO S-NIITIVIT WINDOW 'AUCKMAKE AND MODEL NO, AVAITLABI DETECTED RANG (MTR' !R) W8S s1G/Omm2)

vietoreen 592 Ion chmbezn 4 0-1000

Bbez'1im E-00, 5A BoO- .000 3o ;mvIoýM

vieý%Orem GD '?00 0ýN 6 &Ift 30 m0 3 0Gamm

Eberlino FAC-7,P3C 2'k 0-2 z In rm o"ta 1~ mil08-0 iga~o mll myl=-

lator?

A"& C 10odo Pc1 ca Prop-. 2 Alpha I' to I0 6 'pm Lso than 1/4oationa1 Soaliag Aosem- mil mylar-blies

Eberl1ig PC4-4 Gas Pro opo I Aipka I to 106 dym Lena tbm 1./4Data-tor" with MD. PGC•6 Beta-(kamma mil a-VlaV

SUSE

loaitO-imu

'IlemuXf:ing

Scalizg Auzsmbi

-24-

TYPE OF INSTRUMENTMAKE AND MODEL NO.

W1JMERAVAILABLE

RADIATIONDETECTED

Eberlino 14d SAC-2 Sciu-tillation detector ivitiiITAC Eborline or Tracer-lab soalor

End Window Ge1,c Tubeswith Tr ~acela HD 2.000

and11fc S02AA sealro3

Tera~rlab Area Rdiation

17MIC Model 9N-20 AM-'3

1 Alpha

Bet~a-

SENSITIVITYRANGE (NMVR)

10 to 10 6 dpm

10 to 106 dpm

WINDOW THICK-NESS (M/cMa)

Less than 1/4mll mylar

Less than i14

USE

M~easur ing

Ci~A~nn~le0,011 to 104 or/

Area Monitori.ngKj Bldg.

Air arti ulateMonitori in

Etta-Gaiuma

I A Ilp.a)ota I Less"ham1M I nito'71A XJ Blde0

euAat Aig,'ý;t_-MYN and IScp-iatvAFilter Eoldovs

pilm Radsýývo OSoTviý*a aurTtttlyzltlrpllýnd býn. rissith phyriost, Inc.)

Air &~ample filtero Couterid for

Upper limit Of f ilm roaponst:0. a T-v 600 Rom

Reta -400 RomNeutron - 10 Rom

conoit~ion of air semifram rft2.ýoelr work areeaaf ipXhoxe and otack

d~.acharge to the anvronsý

Filmn bad gas tdre worm2 in2accordane with applicakleaections of IOCFR20 aspart at the ParsounaI ielon-~itoring Program.

-25-

SECTION' C

RESUMAES OF USERS

NAM"E:

POSITION :

EDUCATION:

FRED NORMAN IUFFHAN

Staff Engineer-. Engineering Departmsent

Ph .i hYis, Johns Hopkins University~~j~

U,,.EC Ad~vanced Health Pbtvgics Fellow 1959-64.

Courses in Biophysics? Modern Pkysics and Advanced

Laboratory gave formal training in the priniciples

and practices of radiation protection~, bi.ological

effects of radiation, radioactivity meascrements

and radioactivity calcuiations.

ORSORT Graduate f~ Formal cowrge work and

laboratory experimaents involving princicpies of

~'aiat.onprotect-ion, biological. eff'ects of

radiation, radioactivity mesde m:'ernets and calcula~-

tione'0

MSin Phyio Vanderbilt Universityb)6

U~SAA.C Radiological Physice Fellow 1954-56.

Formal course -in Radioloiesica Physics. Seve~ral

mon'ths exeln~~in ORNL htealth physics offices

durins sumuer, of 10-55,, Mastez--s thesia research

perrw'c~ In )RC1.N Hiealth PhysiCs Divtzlon; 19~55-56.

Resume ofFred Norman fluff man (cont' d,)

EXPERIENCE WVITHRADIATION:

PROFE'SSIONALSiOCIETIESi

Johns IhopkinsUniversity. Experience with a

variety of X-ray machines and Mossbauer sources

as a Research Assistant in JHU X-ray Laboratory

(1961-64).

The Martin ComnMX Supervised loading of

thermoelectric generators (approximately 1500

curies of Po-210• sealed sources) as Assistant

Project, Engineer in charge of SNAP Ill (1958-59),

Performed shield design calculations for Aircraft

Nuclear Propulsion studies (1957-58)o

Oak Rid,ý.ze National Laborat.o. Performed ORSORT

lab~ratory experiments (1956-57). Thezis work

done in ONL Heal-th Physice Division .953•56) ],eoured ONL health phyzics offices dLring aummrof I951, as prt of training program for UoSoA.E.C,

adlo..o~icia Physics Fellows,, Encountered wide

range of production and research radiation

problems.o

Health PhyjAcs Secijey

AmeP•icaa Physican1 Society

NAME.a

P~OSITPION:

ED1UCATION:

'AMElS C,~ NEACE

Senior Erngineer-, Dave.16p~ent -Section,Nuclear Division

I3ýS. Cherniatr-y -- Morehiead State College-

Magna Cuwa L~aude -ý)6

Grdu~ate Couwres in Radloehemislt.ry, University

of M!aryland - 1960-61.

Februarv 161 to vrsenlt: Mart in Allm-ietta

Corpc~rat-ion Nuclear Divi1sion, Senior E'ngineer,

Mater'jalz Developmen~t Section., Development of

Puxriticaton ,iethods and radiocheinical research

~i~operat~ing n~uclear- 7reactors and develop -r~tt

o." apa-layses n support of nuclear reactor

proggrz., Rheyz.arcii or, prreparation arnd purification

ofi -h-ia1:oipoirntsi utilized LD, reat-tor programs.,

" 1o96(:; The Martin CI'ompany, Nuclear

nIyl-i.calI Cheini6"ry Grwup' Re-ponsibl f or

6ýat-t-,g up a 1aoaoyand trainin~g personnel

forl- the c $ea nialysis, ox nuclear reactor

cnmnnenlts De~veloped new wiethods and techniqueic

1952to 1956,- CGeneral I~cr Company,; Aircraf~t

~e:~'~ ~Developed ana:lytica.l t-2ch-iue,1

Resnume oC'Jamnes C.Neace (Cont'd")

PUBLYC AT IONS z

AFFLXATIONS:

PRZOGRAM RLSS1(N0S-,I~~T IES;

Did researtch work on matho'is of pl-oWuc.-ina

spherical particles of U02 0. Studied e-ethods

of salwagin~g uranium fromn scrap fuel elem~ents.

Studied production and p~urification of rare

earth compounds.

t Produotion of Spherical P1articles of UO"2USAEC, (1954)

"eThe Analysis of B~oron by Mercury CathodeEjeetrolysial, Chemist Analys (1959)

"1P Spat Test. for the Identification ol.~'Molybdernun Metal," Chms nls (1960)

Amuericzan Chemilýal Society

Develoe.i,,mnt of analytical procedures for the

Sr-90 *P1uel Devrelopment Progvaw; supervision

of routin-e poescontro). anatayses ov; non-

radioaý-tivc, a.irtsuatcd fuel materials~.

'. ,9 -