ML20217E528

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Registry of Radioactive Sealed Sources & Devices,Safety Evaluation of Sealed Source for Model Am. Certificate:NR-8099-S-802-S
ML20217E528
Person / Time
Site:
(NR-8099-S-802-S, SSD-97-70)
Issue date: 04/17/1998
From:
NRC
To:
Shared Package
ML20217E532 List:
References
SSD, NUDOCS 9804270317
Download: ML20217E528 (7)


Text

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR-8099-S-802-S DATE:

Apg ) 7 jggg PAGE 1 OF 4 SOURCE TYPE:

Density and Moisture Gauge Source MODEL:

AM MANUFACTURER / DISTRIBUTOR:

Parkwell Laboratories, Inc.

429 North High Street Croton, OH 43013 ISOTOPE:

MAXIMUM ACTIVITY:

Americium-241 300 millicuries (11.1 GBq)

LEAK TEST FREOUENCY:

6 Months PRINCIPAL USE:

(H) General Neutron Source Applications l

CUSTOM SOURCE:

YES X

NO 9804270317 980417 PDR RC SSD PDR

REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.: NR-8099-S-802-S DATE:

APR 171998 PAGE 2 OF 4 SOURCE TYPE:

Density and Moisture Gauge Source DESCRIPTION:

The Model AM is a 304 stainless steel, fusion welded, double encapsulated source containing a maximum of 300 millicuries of americium as an oxide.

The wall thickness of both the inner and outer capsule is 0.025 inch (0. 64 mm).

Be and AmO in powder 2

form are pressed together into the inner capsule using a stainless steel plug under a 1000 pound (453.6 kg) load to consolidate the active material.

The plug is then fusion welded into the primary capsule.

The finished source is a 0.5 inch (12.7 mm) cube and has a neutron yield of about 7. 5 x 10s neutrons per second.

LABELING:

The serial and model numbers of the source are stamped or engraved on the outer capsule of the source.

DIAGRAM:

See attachment 1.

PROTOTYPE TESTING:

The following is a description of tests performed on prototype sources:

1.

A dummy source was sectioned and etched, to determine the depth of penetration of the weld.

The welds in both the inner and outer capsules had greater penetration than the 0.025 inch (0.64 mm) wall thickness.

2.

Prototype sources were heated to 180 C (356 F) for two hours without any failures as demonstrated by helium pressurization bubble tests.

3.

Prototype sources were subjected to 300 psi (2.1 MPa) water pressure for four periods of 15 minutes each without any failures as demonstrated by helium pressurization bubble tests.

REGISTRY OF RADlC.^CTIVE SEALED SOURCES AND DEVICES SAFETY EVAL 24 TION OF SEALED SOURCE NO.-

NR-8099-S-802-S DATE:

ANY 17199g PAGE 3 OF 4 SOURCE TYPE:

Density and Moisture Gauge Source EXTERNAL RADIATION LEVELS:

The manufacturer reported a minimum neutron yield of 6

7.5 x 10 neutrons /sec.

OUALITY ASSURANCE AND CONTROL:

Each source was checked for leakage by wipe and helium pressurization tests of 100 psi (0.69 MPa) for 15 minutes.

LIMITATIONS AND/OR OTHER CONSIDERATIONS OF USE:

The source shall only be used by specific licensees of NRC or Agreement States.

The source shall be leak tested at intervals not to exceed 6 months using techniques capable of detecting 0.005 microcurie (185 Bq) of removable contamination.

  • Handling, storage, use, transfer, and disposal: To be determined by the licensing authority.
  • This registration sheet and the information contained within the references shall not be changed without the written consent of the NRC.

l SAFETY ANALYSIS

SUMMARY

i The AM Density and Moisture Gauge source was originally approved for licensing purposes by the Atomic Energy Coramission (AEC) on l

September 16, 1970.

This source is no longer manufactured and

{

distributed by Parkwell Laboratories.

The company is out of business.

There is insufficient information on file for this source to have performed a complete safety evaluation.

Therefore, this registration certificate has been transferred to inactive status without further review based on the original review and approval

{

issued by the AEC.

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REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES SAFETY EVALUATION OF SEALED SOURCE NO.-

NR-8099-S-802-S DATE:

APR I 71$$8 PAGE 4 OF 4 SOURCE TYPE:

Density and Moisture Gauge Source

REFERENCES:

The following supporting document for the Model AM Density and Moisture gauge source is hereby incorporated by reference and is made a part of this registry document.

  • Parkwell Laboratories' letter dated August 26, 1970.

ISSUING AGENCY:

U.S.

Nuclear Regulatory Commission i

(

l i

i REGISTRY OF RADIOACTIVE SEALED SOURCES AND DEVICES l

SAFETY EVALUATION OF SEALED SOURCE NO.-

NR-8099-S-802-S DATE:

AER l 7 1998 ATTACHMENT 1 l

l ACTIVE MATERIAL Q

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4 Ml SERIAL NUMBER'

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t FUSION WELD

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INERT GAS l

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.400 REF.

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PAGE1 NRC FORM 567 U. S. NUCLEAR REGULATORY COMMISSION REQUEST FOR A SEALED SOURCE OR DEVICE EVALUATION INSTRUCDONS: Send tNo request AND a copy of a# related letters /apphcabone and drawings to: The Sealed Source Safety Section, ATTN: CNef, OWFN Med Stop 6 H3. Change the Ucense Tracidng System rnilestone to 19 and assign to reviewer code I-5.

NOTE: Retain a copy of tNo request with the applicahon and background flies.

REQUEeWR REGION / LOCATION:

IAkk[OC(l

[Ab 1AE.

~l l RH Rm R IV RV R HQ R LFDCB ELEPHONE NUMeER DATE TYPE OF ACTION REQUESTED (Check as ;; m ^

APPUCANM NAME SOURCE REVIEW AMENDMENT OF REGISTRATION SHEET

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MAIL coNmOL NUMeERN DEVICE REVIEW

  1. - 5'M -

/- A

/o L LETER/APPUCATM DATE UCENoE NUMeERN CUSTOM REVIEW fa ?

/t //1/97 my ir fil(U'#M t/

4AV3, cSc CAo M M V308 FOR SSSS USE ONLY pg _, y,/

!NUMeER ASomED REMER MODEL NUMeERS PL -A ou. Ain a c. A - m mTEroFEEs mE REcEuEo oATE AsemEo I\\h9l99

//h h1 TYPE OF ACDON (Indicate the nietter of each type l COMMERCIAL DISTRIBUTION (FORMAL) l USE BY A SINGLE APPUCANT (CUSTOM)

SOURCE (9C)

DEVICE (9A)

SOURCE (90)

DEVICE (98)

N)MI NEW NEW NEW V AMENDMENT AMENDMENT AMENDMENT AMENDMENT d NO SAFETY EVALUATION REQUIRED j UCENSING ACTION REQUIRED IF KNOWN NO NO FEES REQUIRED j OTHER (Speary)

TOTAL NUMBER OF NOTES g ygaM REVIEW HOURS NUMBER OF DEFICIENCY LETTERS NUMBER OF DEFICIENCY CALLS FOR SILL 94G PURPOSES ONLY NEW MMAN -

d NNM NAME CHANGE ADDRESS CHANGE ADD TO BILUNG REMOVE FROM BILUNG FOR PEE USE OfLY TYPE OF FEE FEE CATEGORY

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9C U 90 lSA 98

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- AS REQUIRED CHEG NUMeER MATANN UPDATED AMOUNT REENED yy7

% qy ssno 4;yggna

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C00MNTS NRC FONM 9e7 M

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UNITED STATES l

j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20! % 4001 o,

%, 1 -* * * * *,o/

M 171998' DATE:

April 17,1998 NOTE TO:

Parkwell Laboratories Files (SSD-97-70)

/

THROUGH:

John W. Lubinski, Mechanical Engineer /

FROM:

Eric Compton, Engineering Aide Materials Safety Branch

/~ bA The following registration certificates have been transfer to inactive status:

FROM TQ MODEL NUMBER NR-532-S-101-U NR-8099-S-801-S PL-AmBe NR-532-S-102-U NR-8099-S-802-S AM NR-532-S-103-U NR-8099-S-803-S AC NR-532-S-104-U NR-8099-S-804-S PL-200 NR-532-S-105-U NR-8099-S-805-S PL-104 These sources were originally approved for licensing purposes by the Atomic Energy Commission (AEC) during the late 1960's and early 1970's. These sources are no longer manufactured and distributed by Parkwell Laboratories. Parkwell Laboratories' was purchased i

by the General Nuclear Company around February or March 1967. The company has been out of business since at least 1980.

The background files only contained the registration certificate. I contacted Oak Ridge and had the AEC archive files sent to me. These files contained some additionalinformation, including drawings, which I have included in the inactive registration certificates. In addition, I copied all the documents from these AEC archive files to be included with the NRC background files for these new certificates. However, there is insufficient information on file for these sources to have performed safety evaluations. Therefore, these registration certificates have been taken to inactive status without further review based on the original review and approval issued by the AEC. This action is necessary for administrative purposes.

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^ .sp %.x k+j@g ~p%s.%p',@Q e ';;{ w ^ Report No. - ?tif . @Q.; ;, s.'E . License No.:34-13517-01 !A$.g.t0t.;.? s,.;, m :-. ;,.:. O n. r Docket No.[030-05868l(terminated) % ~ @' ' '. T s' s - W.;g: %gy n e:, Associated Licenses No.;*34-ll105-01, SNM-1347, and SNM-909 (terminated) 1

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n Facility: General Nuclear,'Inc. 'and ~ ' S Parkwell Laboratories, Inc. V 429 North High Street. Croton, Ohio '.4. p. :o ~ M .\\,. Inspection At: Private residence of Mrs. Nancy Wells (a former General Nucicar and.Parkwell Laboratories facility) 429 North High Street.. Croton, OH ~43013 Inspection Conducted-Jan ary 2,-1993 o w.. Inspector: . /,e d u " ~~'N d i ,_. Wiedeman Date Senior Health Physicist' l' j Approved By: O-td b D .m o n A. Grobe V DateI f el Facilities and Decommissioning Inspection Summary Insocction on January 21. 1993 (Report No. 030-05868/9300lf0RSSH ~ Areas Inspected: This was a special closcout inspection which included a e review of the licensee's former activities associated with the decontaminatio and remediation of their formerly used office, manufacturing, and laboratory 7 areas located at 429 North High Street, Croton, Ohio. This inspection was in response to an NRC project:.in which an evaluation of approximately 17,000 retired licenses was conducted by an NRC contractor, Oak Ridge National Laboratories (0RNL). On the basis of the ir. formation in the ' retired license files, sites havtr.' a potential for significant residual contamination in their former facilities were to be investigated further. Due to the lack of documentation in the General Nuclear, Inc. and Parkwell Laboratories, Inc. retired license file, the NRC contractor concluded that the former facilities .n.i ~ used by these companies during the period of 1965-1980 could have significant amounts of residual contamination. Results: The NRC inspector did not identify any radiation levels above l' naturai background within the facilities or surrounding environment. Based i 1. __ goo 6e W 930611 %.' [ {DR ADOCK0300gGg ' %uf f jNg

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' (1 N yp.,'.f., '! ( ~.... .;, s, f . + a g J ":s $1./ upon this inspection and a review of previous' Atomic Energy Commission (AEC '. Q. inspection reports', it is concluded that'the facility was successfully i decontaminated to levels below the NRC release criteria, h.* J/ . t:3 v. e.. - h...,l :.. < :4.. n $. ' i,f.' s. ' N{.i;'.. (d

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  • Steven Ott, Esq., Attorney for Nancy,Wel,lsy@N ;g.

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  • Contacted by telephone'on January.21,'1993.',

4. v,..a.. :. y y [ f.%.. /,'k W %.. 2. Backaround p. s? AEC Licenses No. SNM-1347, SNM-909, 34-11105-01,'and 34-13517-01 were '3.y; c issued to General Nuclear,JInc.cand Parkwell Laboratories, Inc., fl respectively, for development,3 manufacturing,'and distribution of sealed i sources in their former. manufacturing facility at 429 North High Street, ,p, Croton, Ohio, during the period.1965-1979.'" On October 17, 1968,. License A lb. 34-11105-01 sealed sources ofwas amended to include. irradiation of, gem stones with mer um q,g.j9 1 he The work was conducted in an 800 ft' single story Butler building at the High Street address., The former facility l consisted of a business $M, office, machine shop, assembly and test areas, shower, restroom, and Ni' small utility room ~ License No? 34-ll105-01,was issued on June 24, h/4 1965, and was terminated on February 361970?r In two letters to the . g.(t Commission dated February 24, 1967, and March 1, 1967, the licensee informed the Commission that all-assets and materials possessed by ggf Parkwell Laboratories have been assigned to General Nuclear, Inc. (see p i Attachment A). 1969, the licensee stated.that all radioactive materials wereIn another letter 9 h. transferred to their Texas License No. 4-734 and the only material that d' remained was contaminated hoods and glove boxes'hich was possessed w under License No. 34-13517-01 (see Attachment B). Subsequent telephone -f, </, conversations were made between NRC Region'III: staff and Mr. Charles Wells (now deceased) in the early 1980's prior to the termination of p License No. 34-13517-01, in which Mr. Wells indicated that these . t/ contaminated items were buried in'two burials in accordance with i.f 10 CFR 20.304 sometime in early 1980. lThese burlais consisted of less 7 than 20.0 microcuries of americium-241 as contaminated equipment, metal, and concrete (see Attachment C). During this inspection, Mrs. Nancy $t: Wells (wife of the deceased), informed the inspector that she was not A*gi. ', aware of any burials of radioactive material on the property. Assuming that the contaminated items were actually buried, the NRC staff '? performed a hypothetical dose assessment and pathway analysis using the ye computer modeling program RESRAD hypothetical assessment was based (upon the following assumptions: version ,N., M

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(1) Buried material consisted of 20 microcuries of americium-241 in i C.i the form of contaminated equipment, metal,.and concrete; ^ d,g q gg .s

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6: (2) Total volume of waste was contained in.two 55-gallon drums ? amounting to 15 ft':(7.5 cubic' feet /55 ' gallon drum); and w ,:. b :.9,p mppg;:p. y G:', 7.' W T (3) All waste was buried 'atia'minimui The NRC staff concluded that,1f this&of;six" feet.9!; .. ' Y' . '..L:QQ:*& G@WD

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N occurred, the long-term effect to members'of the public andhypothetical; burial,actua h

7-h., environmental would be negligible.xTherefore,t.if the burial of this' quantity of, radioactive material;actuallyl; occurred it would not pose a i ([ hazard. g .y%lj{ Dy The address changes'and transfer of. radioactive materials ~ to' the t %"r above-referenced licenses were subsequently made; however, a~ review off the expired license files did not show!any. documentation of a closecut; E f MrsWellswas'~positivelthat'a7finalisurveywasconducted;o g"U survey. 6 however,'she was not:able to: locate lanyidocumentation that would i y,. indicate that a radiologic' survey was conducted at the'High Street v address prior to the termination of the licenses.. A review of the [ Region III files show that on August 6-9,V,1979, an inspection and close-out survey was conducted (Report No P79-02). The inspection y report issued on October 23,'1979, shows 'that"at the time of this R inspection, there was no residual contamination, except for waste ?- waiting to be shipped to'an authorized recipient (see Attachment D). Information regarding past ' activities and locations of the former tg, equipment was provided to,the NRCL. inspector,by.Mrs. Nancy Wells. ?.;,yg @km yMgipp :;'w. v 4 During the license file' review' by'ORHL,Ntheiconclusion that extensive ,7 contamination may be present at the formerly used facility was based W' upon the fact that the licensee. worked with. hazardous loose material and x..N the files did not indicate that the AEC/NRC conducted 'a ' final survey of i i$:, the facilities prior to the' license termination. However, as stated above, the NRC conducted a close-out.surve.ofxthe' facility on August 6-W bl 9, 1979.

7. ~, 4 * '

@@f 6@ AM ' ' ' 4 ( d. .. y. 2W m o 3. Facility Status 7 M : $.Wh, W l3'"2 ES f &l%.s3 p The current resident of 429 High' Street',' Cioton, Ohio, is Mrs. Nancy .O Wells and she has. lived in the facility since the early 1980's with her &h' now deceased husband, who was the former owner.of Parkwell Laboratories, Inc. Hr. Wells passed awayrin November 1988.' { from review of the drawings;and specifications $The inspector determined found in the. terminated Q,;, license file that extensive remodeling;hasetaken place-in the facility W k;yl during the past 13 years.': n,:ff 'Wk % ::. ^, jff dih.ly % W' ' U. y, 4. Indeoendent Measurements '; %.;, fu{y

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2 p q., G. z,' y g' The inspector conducted radiologic ' surveys in and around the areas where

c manufacturing and testing of radioactive sources were conducted.

? .'k(, inspector did not identify any' radiation. levels above natural The l background. k i y a,

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i y A pW.L 3, jf .g. .,93 n. Q7. b'{ ' [', W$)l,%,g^%.. z qtp j S. W f W .s gr,:- MF 7 ' . ;g,$ F , The' inspector.. ciatedith. itelan a'djacen property' and ; conducted. L}T - './inde' endent1radiationisdrveis"with"a!;Ludium Model 3 ' survey instrument p U 'with a Modelf " on August ~18 h,,44-9 pandake' probe}ficasul Tag.HoQ O37301 which was HRC

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1992GiBackground rements t'aken in the middle of town Q f: Cro 9$((cpm) ton,f 0hio):with[the!Ludlum~ Modelh3 showed 50 M y -showedil;600.' cpm"andfat1Fpti K11,000^cim.'Q'r licensediactivitiegwo[%stum-13 }f Random" measurements (of thelfloorshwalls, and ceilings .. c. 'where forme retconductedshowedno. radiation r -levels above : natural.: background.'?Smeara +ests',~for removable v . gl,

con tamination 'did. no tishow., an 1cor nal,iha'l$ beta," or gamma. radiatlon.

e I ~ The NRC inspector'inetewith';Mrs. f j, ' [: inspection.5The Weilsea~nd summarized the findings of the p radiologicisurvey?inspectori<infdrmed.Mrsf: Wells l:that the independent indicatedtthatithel.former buildin ..e 9,4 by General Huclea,r.,MIncMan'd;Parkwel.l.. Labor'latories,g facilities occupied Inc. did not show any radiation levelsf above!natuialibackground.*Mrs." Wells was also ft. informed that the levelsYo'f&adiation were below the release criteria ,y described in the NRCldocumeht? Termin a t i on o f Lic en s e si fo r,ior]MGuidel ines ' for W 7{6 Facilities and Equipment 4Pr to' Release'for Unrestricted Use or ,By reduct,HSource,;7er Special Nuclear

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4 ( W N h 3$ d @khh N ' %.j A close-ou@t survey waa $$N,(edtatgthe,.licensaets "M g ggg j p i Eonduct ?.E. ' y S'. through '9,.1979MYisuallinspectio on Augus t 6 - N.'.h evaluation of.virias9 sad deview!cf(Qdirecthadiation : 1 =ve1 L=e = = u remen ts, essed bylth'ellicenseef5xeyti5iraste,9 haa,been ' dispos 'C % previously poss dQT' of in an' authorised==rMr;addJ k( thatBtherd /@h[. cone==fn= tion in sic'idfofiliaita"11PfAc'e{vas'no"evidance of residualk '- e dure %, nod 3895B,h' Attachment I, '. Tabi e.1.' 0,F.% I $~. v.; - ' &bYk... [. U ~ 1$f f MOQ;].y d Q M s. W f?l'hh' i ne licensee 'statediin , J n/ radioactive'vas'te76uly(atphene contact 1onjoctober,15k1979p'on 't a113'M +.m h tha b efa h'ip p edl, tio(th a 1 Richla'ni,9,Shi y[,j site operated. by;%cledr}Zdgidee)tofthal Nuclear { Re Washingt ,lburialf ' ~ ,12g*Coffdlic(%nd'. ~ t, copies l.cf s the l' ' shipping papers;vouldiba r.a11ed k Wr., Based on the' s"and.on[tihelE' idance of}AF f thiI11Procedurer838903 andf8 u t .t,. RIII.has' no obj ec'tloi2 1 tEldutihorizing rel'e'a, e,p. ~. for. unres tric use{r ; Mg ~ ' censee's ' facilities o y>(;,$. (7 %gh , @s Dk.,x e, .e.r g .t

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l,'f l,. _ k:. k, Approved.By: 'J'. .}Pagliaio Chief) .k h$' Jia t e rihls',(RadI,l'og'idal ,E El o //3 5./ 5 g f '.<;, A,..',;. # [' ?.g! 4: Protection Section 2 ' ?.;)W ')' T;\\, MQ;.i:<;w. ? i. '.v ;pg,& ~' i p 2 ha b. Inspection Summdh. [gyfGM.:xl,' g y:9 ~ hhhbEM.2.N E.h,* cf~: ( - W%.,>:mH C.. R.. 6ws Arcas Inspected:f, Visual inspection /' radiation (measur,e - i jg ' . Inspection 'n August ~ 6-9,",19 7 9 '- ( Re p o r t'Wo.. 02) .. q @, ggfkq, n. o @f;' 6 ' :f Wl p j ," air.sampics, tX nnd evalua tionsf.of J.'sme'a9s'takeif.itp'd]E i' ialiEtiklo~c'a't i 5nsYa t i t jf.".. f acili ty. to ' verify,'thhE?dijlihEn2c ' a c ial h51 becn.* disposed ofJ 6 T -l[j) thatthereOas'no'rcsidUa1IconfamiEntidif.$Ml ~ and' 2 _Results: 'A11711Ecnsed M l@ Vf ' ' 25 authorized mannericxcep[ mite'rikl[ksMiYp[o%cd,'o,,, ypheQ[l'ich@nsce 'in f. L. L$[4:f t *for%as tcbliichYist to7 bat (shipped i'tcOthe. T! Richland, k'ashingted.bu$1a1 isite}i % MNcyeia~tck y' 3'NUc1'carlEnginccrin ~ M Inc. The licensec"is"E hisend7cN cs f o ship';singT apers to NRC-RIII. t M. k . No residual contamin N ibnN Es7detcc S & i ~ '*'N Si.W #Mn!. e. kU h m.Mf C MMM I my[s' k M mu.fkh. Q;,.p ';, y % e f 2 ; &,hl M. e

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I f 4 8 r ELLIEIAk gSE QEh1 SEALED SOURCE l MANUFACTURER & DISTRIBUTOR MODEL NO. Parkwell Laboratories, Inc. AM Croton, Ohio ISOTOPE USE Americium 241 (300 mil 11 curies Source used in moisture maximum) and density gauges DESCRIPTION The Model AM is a 304 stainless steel, fusion welded, double encapsulated source containing a maximum of 300 mil 11 curies of americium as an oxide. The wall thickness of both the inner and outer caps _ule is 0.025". Be and Am0 in Powder form are pressed into the inner capsule using a stainless 2 steel plug under a 1000 pound load to consolidate the active material. The plug is then fusion welded into the primary capsule. Thefgnished source is a 0.5" cube and has a neutron yield of about 7.5 x 10 neutrons per second. PROTOTYPE TESTS The following is a description of tests performed on prototype sources: A. A dummy source was sectioned and etched, to determine the deoth of penetretion of the weld. The welds in both the inner and outer capsulas had greater penetration than the 0.025" wall thickness. B. Prototype sources were heated to 180 degrees centigrade for two hours without any failures as demonstrated by helium pressurization bubble tests. C. Prototype sources were subjected to 300 psi water pressure for four periods of 15 minutes each without any failures as demonstrated by helium pressurization bubble tests. l QUALITY CONTROL s Each source is checked for leakage by vice and helium pressurization tests. LABELING The serial and model number of the source is stamned or engraved on the outer capsule of the source. September 16, 1970 U. S. ATOMIC ENERGY C0KKISSION OFFICIAL USE ONLY i}}