ML20235X197

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Application for Amend to License SNM-1635,authorizing Sc Sylvester as Radiation Safety Officer & Use of Licensed Matl in Experiments in Instructional Lab & Experiments Re Radioactive Activation of Silver & Indium by Neutrons
ML20235X197
Person / Time
Site: 07001994
Issue date: 01/21/1987
From: Sylvester S
STEVENS INSTITUTE OF TECHNOLOGY, HOBOKEN, NJ
To: Glenn J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20235X167 List:
References
106689, NUDOCS 8707240082
Download: ML20235X197 (32)
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{{#Wiki_filter:0: .o Stevens Institute of Technology c.su Po i,nosokeo,xe.;m.eyoro30 m Office for Academic Services 20l*420*5228 January 21, 1907 Dr. John Glenn U.S. Nuclear Regulatory Commission, Region 1 Nuclear Materials Safety Section B 631 Park Avenue King of Prussia, PA 19406 Re: Renewal of SNM 1635

Dear Dr. Glenn:

Stevens Institute of Technology, Hoboken, NJ, hereby makes a renewal application for its special nuclear materials license SNM 1635. 1. Stevens Institute of Technology, Hoboken, NJ 07030, is chartered in the State of New Jersey. Offices, classrooms, and laboratories are located on the campus in Hoboken, NJ. We principal officers of the Institute are: Kenneth C. Rogers, Ph.D., President (U.S. citizen) Richard G. Griskey, Ph.D., Provost (U.S. citizen) The individuals in charge of the special nuclear material will be: Steven C. Sylvester, Ph.D., Radiation Safety Officer (U.S. citizen) ) Milos Seidl, Ph.D., Professor associated with the course in which SNM is used (U.S. citizen) Control of the Institute is in the hands of the Administrative Officers who are responsive to the faculty but responsible to the Board of l Trustees; all of the latter are U.S. citizens. There is no control or ownership exercised over the applicant by any alien, foreign corporation i or foreign government. I i 2. The use of the SNM is in experiments in an instructional laboratory at the senior undergraduate and graduate level, under the guidance of Dr. Milos Seidl with the help of a graduate assistant assigned to the laboratory. The instructional laboratory is located in the Peirce building. The source will be used in experiments involving the radioactive activation of silver and indium by neutrons. 3. The source is a numec Type 1 sealed plutonium-beryllium neutron source manufactured by Nuclear Materials and Equipment Corporation. Thesoureg has an activity of 5 curies, a mass of 80 gm and a neutron flux of 8 x 10 neutrorVsec. The serial number of source is 800120. Mr. Grant La Pier of Babcock-Wilcox informed us that no information on the expected encapsulation lifetime was available. The source has been used and will only be used at room temperature and atmospheric pressure; leak tests which have been performed show no signs of leakage. 8707240082 870324 REG 1 LIC70 PDR SNM-1635 L ___ -

StGv ns In;titut W D 2 Renewal of SNM ik ) Technology d Ret l i ' 4. Information sheets on Milos Seidl and Steven C. Sylvester are enclosed (see attachments 1 and 2). 5. The Pu-Be source is contained within a Neutron Beam 7rradiation Facility described in a booklet supplied by Atomic Laboratories, Inc. (Catalog No. 71864, see attachment 3). This neutron howitzer has four parts each plugged with lucite and normally locked closed. The howitzer is 24" in i diameter, 24" high and is filled with paraffin. This shielding of about 30cm corresponds to 5 half-salue thicknesses for fast peutrons. At the 1 thefastneutronsareemjttedatarateof8x10 n/sec. Without source the paraffin, the flux in n/cm -sec at the surface of the howitzer would i be: i 8 x (10 710 2 4rt(30) em - see With the paraffin, the flux at the surface of the container is: l l 710 x 2 5 22 2 cm -sec j The source is used only in the howitzer and is " handled" by means of sttings attached to the source holder. The source is normally located 3" below the center line of the ports and is raised to the port height by the l strings (see Attachment 4). Tha howitzer is kept and used in a locked storege room under the control l of Dr. Seidl. Access to this room is by permission of Dr. Seidl, the i radiation safety officer, or campus security. ] We have a Geiger counter manufactured by William B. Johnson & Associates j 2 Inc., model GSM-15, with a GP-200 probe. The probe has a 1.4 m.,/cm window which is able todetect5mevalphapart{clessincethesealpha ) particles are capable of penetrating 3.4mg/cm. This cougger is I gglibrated every six months using two NBS traceable sources: Co and Co. The dose rate for each individual source in mrenVhr is measured as i a function of distance from the source and compared with a calculated dose rate using the following formula: rA dose rate - 2 r where r = Gamma Radiation level of the radionuclides (from the Radiological Health Handbook revised edition 1970). A= Activity of the source. r= The distance from the source to the detector. 6. Radiation Protection Program l A poster is located in a conspicuous place advising workers about our j licenses and Nuclear Regulatory Commission regulations (see attachment 5). l C____.______.__._

l RM =Stev:ns Institut g Technology 3 Renewal of SNM 163F ' le radiation safety officer is Dr. Steven C. Sylvester. His duties include: authorizing all purchases of radioactive material; overseeing the pick-up of radioactive waste; recording information received on exposures incurred by all personnel working with radioactive materials;' conducting two surveys per year; consulting with radiation personnel to keep radiation doses as low as possible; and maintaining records on surveys and inventories. l All personnel working with radioactive materials use thermoluminisent j dosimeters which detect gama and beta radiation. 7hese are used for whole-body monitoring and are " read" by a commere!.al service on a quarterly basis. To date a typical exposure for a perm ) working with the neutron source is.025 renVyear. Radiation surveys are performed by the radiation safety officer two times I J l per year. The GSM-15 Geiger counter is used to meeture the level of I radiation emanating from the neutron howitzer. We program using the Pu-Be source does not generate any radioactive waste. However, waste which is generated under our Byproduct license is picked up by Teledyne Isotopes, Westwood, New Jersey. The radiation safety officer keeps a record of all personnel exposures on New Jersey State Department of Environmental Protection form BRP-26 (see attachment 6). Copies of inventories and surveys are alEo maintained by the radiation safety officer. The license application covers the special nuclear material we already l have; we will not be ordering any additional material. j Leak tests are performed two times per year. These are done by wiping the source, particularly the welded seams. We test wipes are measured by Teledyne Isotopes, Westwood, New Jersey or in-house by Dr. Seidl. The in-house test wipes are placed in $ ead-shielded container in frgnt of a l c Geiger tube (Amperex Model 200 window thickness 1.2 mg/cm ). We l resulting countrate is compared against nomal background. To date no test sample has yielded a countrate significantly different from background. l A copy of the safety precautions to be employed when using the Pu-Be source is attached (see attachment #3) as well as our general instructions for personnel working with radioactive materials (see attachment #7). Also attached is our general policy on radioactive materials (see attachment #8). Very truly yours, f~- Steven C. Sylvester Radiation Safety' Officer SCS/mvb enc-8

7... attachment Il ......t p v) V( 6 i ] ~ Fo,m A E C-313 UNiflO $7Aff 5 ATCMsC ENERGY COMMO,SION q.73) M ***a=8 APPLICATION FOR BYPRODlKT MATERIAL LKENSE "a ' - 2 8 -== = w cn 3o INSTR 4UC*1CNS -Complete items 1 through 16 if this 85 an initial application or 29 application for renewal of a license. Information contained v$ous aconcations 1. ed eth the Commissson with respect to items 8 through.15 may t.e incorporated by reference provided re erences are c!eer and v spec,r. Use sap;de= ental sheets where t'ecessary item 16 must be comp!sted on all apphcat,ons. Mail two copees to: US Atomic Energy Crnmis. e s.on, v.as ng:on. C C. 005 5. Anent.cn. Materiais Branch. Directorate or ucest g. Uport acpre eal of this 30phcation, the 40pucant wdf receive ari AEC Bfprceurt Material Lee-se. An AEC C rp odact Ma.i.r at Ucense is issued in accor ance *.th the geaeral rec.,irements coniamed in T.t:e *C, Coae of Fes. erai bguncns. Part O. and the Uce9 tee is sutacct 'o Titie 10, Code of Fecera* T4.$u'2t:ces. Part 20. anc !he hcense fee prov'sions of Tit'e 10. Coce of - -' ~ federat Fe;u.ations. Part 170. The license fee cateaory shousd te s:ateo in item 10 ar c tt e a;erocr a:e fe.e enc.oset (See Note in instructc1 Ohe

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INFORJAATION TO EE SUDMITTED ON ADDITIONAL SHEETS IN DUPLICATE Descrit.. esbo, e,y we.i.n s ou reme e Wadi as ego.pm.a, wege ceano.ae,s. sh.eid.ag, f.m. hee is, est tipion.tery she.ch is. f ACitm 5 AND eOutrutNT. e of foc l.sy is epoched. (Cercle eruwer) Yes No 14, R ADI ATION Pf'OTECTION Proct AM. Cour.be the end.ehen protect.on peegrom mciud.ag ceaeral aseosures. If oppi. cohen co.ers seated soveces, subm.t seat sonhag proceduwe wher s appi.ceble, ew me, ere.a.ag, and espeeieue of person sa perform asek tests, oad erreage meats for pesformeag enit.el rod ohen suever, serw-scusg, me.ateacace sad repair of the sowrce. I5, wA5f t Di5POSAL. If e ce=menc.of wesee e.sposal service s empieved, specify nome of compoap. O* erw.se, s-bm.* deto. led desce pa.en of sae*ods wk.ch will be e, sed be e.spes.as of eed.aoci..e wonees and e.hme es of she type cad emount of echvier m.ol ed. C*nTiflCATE (TNs Itam must be cDmpleted by opplicant)

16. THE APPLIC ANT AND ANY OFFICI AL IItCUTING TH:5 Cit?!PICATE ON ${ 4LF Of f ME APrilCANT N Auf D IN iTf s 1, CitflFV THAT THIS APri,iCATION IS Ptf P At!D IN CONFOturty wtTH TITtt 10. CODE OF t!Dttal stGULAf10N5. P Att 3D. AP.D TH AT ALL INf otMAtlON CONTAiNID HEttlN, INC.' UDING ANY g

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d w ca 30 APPLICATION FOR BYPF00lKT MATERI AL LICENSE + - aa=" INSTRUCTIONS.--Complete items 1 through 16 if this is an enitial application or an application for renewal of a 16 cense * .,, nation contamed in pre-vious asciicat;cns falad with the Commasion with respect to items 8 thrNgh is may t,e mcosporated to <eference peceided re'erences are efear anct ca: M. Ute sep5emental sheets eere necessary item 16 m st te completed on a:1 appocations. Ma.4 tao copies to: U.S. Atomic Energy Comme-u s ca. %hinsic i. O C. 20s4s. At*ent<on-Mater'a's Branen. Directorate ci ucer. sang Ucon a:p'ovat of this c:pcataon. the acpacant w.a receive an AEC E crecsct Wieria* License. An AEC Evproduct M.iterial License is ssa s en accorcance w'tt :te general reWemerts contamed in Titia 10.Occe of Fod. e'at n paucr:5. Part 30. and the Licensee is sut ect to Tit e 10. Coco of receial Regulations. Part M. and fe e l e licensa fee provis' ors of Title 13 Code ct f ecera. Regulations. Fart 173. The lecense fee catocory shoulc t.o swed in ftem 16 and the accrcpriate fee enc;cseo (See Note in instructon r.heet). _ l.' :.* t. tui % AVE AND STREET A00RES S OF APPLICANT. (frist f.,f on. larrti hoshtJf Ow'. (be sTRf,t f AOC*t5hti) AI wMC1 trPROr,uCT mat!#3A6 wtLL SE UsED. Of sors, etc. mcouce Z;P Cace and to ear.one nuenter i d.Me.one trenne li.). Inciv.e Zi! Coao 4 Stevens institute of Technology .,.. j Castle Point Station Some os item #1 Hobcken, NoJ e 07030 =

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- _ ~ _ _ O On v ATCMIC NORATORIES, INC., sos e claremont Ave., Berkeley 5. calarernam. L mud.scit rr c noo zn.orum.nt. corper. tion i' \\ l j i 1. 1 EEL 2LLL 221121 3 1 i 1 The NElRRCN EEAM IRRADIATION FACILITY is designed to hold any of the E various Plutonium-Beryllium Neutron sources as well es other types of sources loaned out to educational institutions by the Atomic Energy Cmmission. Since different sources have different dimensions, the vertical tube which contains the source has an inner diameter of I 5/8", wide enough to hold the largest source. Some sources will necessarily t. have a smaller diameter and will have to be positioned inside the tube .hy wrapping cardboard or. some other sof t wrepping material around them. The weepping can be held in place by scotch tape. AII sources must be positioned vertically by means of e wire. The center of the source must be suspended at the center line of the horizontal tubes. Once the wire is marked the proper d istance, the source must then ' be lowered into the vertical tube and the long polystyrene cylinder - placed down the tube with the wire in milled groove. To hold the source i in the proper position, piece a large nait into the wax at some convenient distance f rom the top of the vertical tube and loop the wire around the na ! !. It is understood that the Lucite foil holders must be in place at all times in the four horizontal tubes. For en extra measure of safety, however, it would be a good idea to lower the source into the bottom part of the vertical tube ef ter each experiment. For this purpose, a'n extra 3" of tube has been provided below the center line. NOTE: At present 7 types of Plutonium-Seryllium sources are available to educational institutions by the Atomic Energy Commission. They are offered in ranges of 1,2,3,4,5,7, and 10 curies of Plutonium. The reallest source has a cylindrical diameter of slightly over 1" and a j cylindrical. length of siishtly over i I/2". The dimensions of the 10-curie source is I.6" x 3.45", respectively, it is advisable that the purchaser of the Neutron Beam Irradiation Fecility obtain the 5 curie source since the experiments in the experiment manual are based on a neutron yield of 8 x 100 neutrons /second*/m====. 'The #-curie source l \\ meets these specifications. i 1 < I i 1.

O O s Fadiation Precautions The Atomic Laboratories Neutron Beam Irradiation Facilit/ has been designed to serve two pur:oses: it allows safe, permanent s;crage of the Plutonium-Beryllium Source; and it serves many purpeces in neutron physics experiments (see experiments beginning on page 3). When using the f acility as a Neutron Source storage container, the four Lucite foil hoicers must be in place es well as the Polyethylene cylinder. The lid en each of the four beam ports must be locked. The key, which fits all locks, must remain in the possession of a trusted ind ividual, preferably the chai n n of the Physics Department.. Refer to Atcmic Energy Commission's Regulation IC-CFR, part 20, f or procedures involved in the safe stcrage o' the Neutron Source. No special maintenance is necessary in regard to the Neutron irradiation Fac i l ity. Extreme heat might cause the paraf fin wax to me lt, but even if it does, IT will not leak through the tentainer or get irto the foil holders, Polyethylene cylinder, or Neutron Source. Under no conditions must the wax be. removed since this will take eway the shielding and expose students to extremely dangerous doses of red iation. When the facility is full of wax, it f ully complies with all the standard limits in regard to radiation protection. Con.puted Flux at 30 cm. from 1.4 x 106 neutrons /sec source. ~ 6 Flux = 1.C x 10 -a = i23 x e.126(30) e 4c(303 =123x(.023)if3.0n/cm2 sec. (Casputed attenuation 2.3% compared to 45 given by Frank R. Jones, Rad iolog ical Health Handbook (1955), page 282.) Oeeration When the Neutron irradiation Facility arrives, it should be unpacked caref' lly u and the entire ypparatus inspected to see that there is no shipping damage. The wax shoufd be within 1 1/2" of the top of the container end should appear to be solid and well packed. The beam port locks should be tested and the battery in the lock en thrt lid checked. When the t id is open, a red l ight warning is visible. The Lucite foil holders must be examined, and it is wise even to check the Polyethylene cylincer to see if it is in one piece. Only after the facility and its accessories have been thoroughly checked should the Neutron Source be placed within the apparatus, i The special Ind' lum, Cadmium, and Rhodium Foils should be placed in the foil holders es described in the ind ividual experiments. t h@n

z_ --_-_- _; _ _ -_ _ ~~ ~ Is ."e () (d i l UNDER *NO CONDIT!CNS SHOULO AtM;NE STAND IN FRCttr CF AN CPEN EEAM PCRT WHEN THE LUCITE F0ll HCLDEES ARE CEVCVED CR WHEN TPE EEAM PCCT LCCK 15 CE90VED. Only a short exposure under such a cond ition will result in pcss ib le rad iat ion damage ' The same precautions should be taken against sitting en Top of The Radiation Facility if the Polyethylene cylinder is removed. I Plutonium-Perv i ! ium Scurce I l Due to the Atomic Energy Ccmmission's educational grants for nuclear physics l trainire, colleges purchasing the Neutron Ecem Irradiation Facility will be able to rent a standard Pluton ium-Eery ll ium Source f ree of charge. Such sources t l emit 1.4 x 106 neutrons /sec and have e 24,000 year ha l f-l if e. Less than 0.7 I gammas per neutrons are emitted. ) i Plutenium is a special nuclear material and its receipt, possession and use is licensed in accordance with Title 10, Code of Federa l Regulat ions, Part 70, "Speciel Nuclear Material". The application for a license for a plutonium- ) beryllium source should be submitted to the U.S. Atomic Energy Ccenission, Division of Licensing and Regulation, Washington 25, D. C. In letter form in ) quadruplicate and contain the infonnation required in Section 70.22 (attached), including your procedure for leak test ing the source, the f requency of these 4 tests, and the procedure for prevent ing exposure of individuals to rad iation. Application for renting a Plutonium-Beryllium Source f ree of charge can be obtained by writing: Mr. C. G. Manly, Assistant Director for Commercial 4ctivities; Division of Reactor Development; U.S. Atomic Energy Cumnission; Wash i ngton 25, D. C. l O n ay e 4 e e

O O attachment #4 SAFETY PRECAUTIONS FOR USE OF THE 5 CURIE j Pu-De NEUTRON HOWITZER (Strong Sources) .] In order to avoid the danger of overexposure to the neutron flow from the q Pu--Be Sources, please follow this rule: NEVER REMOVE OR INSERT A SAMPLE HOLDER WI'IH THE SOUPIE IN THE RAISED { j (ACTIVATION). POSITION. In order'to observe this rule:

1) Check to see that the string with the yellow tag is free from the stud, so that the source is at the bottom of the wall, out of line with the ports.

{ l

2) Open port, insert (or remove) sample holder.
3) Pull up on string -with blue tag and hold.

(This raises the.lueite moderator rod).

4) Pull up on yellow tag spring, and loop it.over stud.

(' Ibis raises source to estimation position, in-line.with ports).

5) Complete exposure of sample.
6) Lower source as directed above before removing sample holder.

D,c_~S Luc.te a L \\. j ' # vL - Moderotdr.N Y\\ - \\.\\ ' l < \\ '\\ \\' \\ \\ \\ s \\ re. s, ', 's Peroffin ~ .s w._,l . -- Port -^^ ia J. g, ,g \\ \\.' [ g \\\\' i s\\ \\. ' { s N Source ~ 'I') I ) \\ N ...! v'JI.\\ .\\ y. s j s w! g j i o' i o c. Activation Position Safe Position Source in line.with Ports for removal'or insertion of sample holders .j I

cttachm nt I5 d <...,. _.O. ~.% O ,6 6' 7 s-STEVENS INSTITUTE OF TECHNOLOGY CAUTION Work with sources of, radiation is being carried out in this area. -in accordance with United States Nuclear Regulatory. Commission Regulation 10 CFR' 19.11, the ' foilowing documents relating to ~ the work are available to you frcen the Researcher under whom the work - is being conducted or from the Radiation Safety.0f ficer, - Or, Steven C. Sylvester, on the 12th Floor of the Stevens Center ( (Ext. 5228).

1. 10 CFR 19 - which describes the Nuclear Regulatory Commission Regulations pertaining to notices, instructions, and reports to workers and inspections of radia-

) tion activities. j

2. 10 CFR 20 - which describes the U.S.

Nucleer-Regulatory Standards-for Radiation Protection which must be adhered to in the use of sources of radiation.

3. The Nucl ear-Regulatory Commission Licenses and application files:

NRC Byproduct Material License Number 29-05263-08 NRC SNM License 1635 New Jersey State Radiactive Materials License Number 80211 l which specify the special conditions under which radiation i work must be conducted at Stevens, j

4. The New Jersey Radiation Protection Code 1

which spect fles Institute l

5. Stevens Radlat lon Saf sty Polley Radiation Policies and Procedures.

a

wy summausm ms trtwa ssng ettach ent #6 m Q. Box 1390, Trenton, New Jersey 08Q CURRENT OCCUPATIONAL EXTERNAL RADIATION EXPO 5URE i Identificcfien

1. F 1 (Firiar Le ar, ferss sad misidle)

[ {.? .2. SOCIAL SECURIT Y 60. 3 QAT E OF BIR TH (Meath, day. yeen)

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e4 ele body; er hones and foreernia feet end enJoes. RESERVE AT BEGINNING CF PERICO Cov. F B; Pockee Chamber.PC; Calculations-C ERED BY THIS 5HEET. ggggg gg7A NEUTRONS X-R AY

8. E XPO5URE PERIOD (From - T.)
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13. TOT AL TAVE *EEK5 ~ l 1

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15. PP.EYlOUS TOT AL
16. TOT AL COSE THIS 5HEET
17. T OT AL ACCUM. OCCUP.
18. P E RM. A CC. CCC UP.
19. PERM.OCCUP.005E:

[., DO5E DO5E 5(M.18) REM CN RE S.

20. NAME AND ADDR E5S CF LICENSE E CR REGl5T R ANT.

e L_ (Coatinued en reveese)

STEVENS INSTITUTE OF TECHNOLOGY cttochment #7 CENERAL INSTRUCTION FOR PERSONNEL WORKING UITH RAD CTIVE MATERIALS APPENDIX B ) 1. No one may use radioactive materials without the express permission of. and without prior instruction from a member of the Radiation Safety Committee. Currently the members of the committee are Drs. Nardi, Kumbaraci, Chring, Rothberg, Seidi, Steinmann, Sylvester, and Wong. Once the instructor has determined that the-individual has had sufficient training in the safe use of radioactive materials, the individual may begin handling these materials. Personnel using. radioactive materialsL will receive refresher instructions on an annual basis. 2. Under no circumstances may liquid radioactive materials be pipetted by mouth. Since pipetting by mouth represents a severe health hazard, doing so will result in the cancellation of the individual's authorization to work with radioactive materials. 3. Eating, drinking, and smoking in areas where radioactive materials are used are prohibited. Storing of food, drink, cigarettes, etc. in areas where radioactive materials are used is also prchibited. 4. Wear your film badge. All personnel working with radioactive materials must have and wear a tilm badge. Film badges may be obtained from the Radiation Safety Officer (RS0), Ext. 5228. Radiation exposure records are kept by the RSO and will be given to the worker upon request. 5. It is the responsibility of all personnel working with radioactive materials or in an area where radioactive materials are used to be aware of the location of the radioactive materials and to insure that the surrounding area is adequately shielded. 6. When not in use, radioactive active materials should be placed in an appropriate container and stored in the storage area provided in the laboratory. 7. When it is necessary to handle radioactive materials by hand, disposable plastic gloves and a laboratory coat must be worn. A survey of fingers and hands should be conducted after handling any radioactive materials by hand. 8. a) When handling liquid radioactive material, always wear disposable plactic gloves and a laboratory coat. b) The work area should be covered with sufficient absorbent material to contain any spills. Use of disposable diapera is recommended as the i absorbent material although paper towels will suffice. l c) In the event of a spill, the area should be thoroughly cleaned and checked for contamination immediately. The Radiation Safety Of ficer snould also be notified as well as the person in charge of the laboratory. d) Contaminated waste should be disposed of in accordance with the instruction provided (see Appendix C). e) A survey of fingers and hands as well as the work ' area should be conducted after handling liquid radioactive materials. l l l l L

w O

General. Instructions for rsonnel Working with Radioactive Materials i Appendix B 9 9. Under no circumstances are radioactive materials-er radioactive waste-to be disUrded in the regular trash recepticals 'or flushed down. the city sewage system. Radioactive ~ waste - should. be placed in the ' radioactive waste container provided, following the instructions provided (see Appendix C). The isotope -and quantity 'of material should be ' recorded on .the card which is attached to the top of the drum. '10. Upon receipt of any radioactive material, - the procedures: outlined ~.in l -" Guide for Specific Procedures" should be used (see Appendix 3). l l l ~ 4 1 l 'j i l I i l 3/18/86-

~~ APPENDIX C ?TTELEDYNs 0-O GOTOPES 1 (hh,) l EXTERNAL PACKACING INSTRUCTIONS FOR RADIOACTIVE WASTE I I. Dctermine: l a. Isotope b. Activity (mci) c. Physica] state [ solid, 12 quid (bulk or vials), animal carcasses, i biological matter or gaseous) d. Concentration (mCilgram) e. Transport Group (I through VII) f: Form (Normal or Special) II. Determine the Proper Shipping Name NOTE: All LSA material which we pick up at your facility is shipped " Exclusive Use." l z. Radioactive Device, n.o.s. j b. Radioactive Material, Limited Quantity, n.o.s. ~ J l Radioactive Material, Low Specific Activity or LSA, n.o.s. c. d. Radioactive Material, n.o.s. j Radioactive Material, Special Fcre, n.o.s. e. ([f j l f. Radioactive Material, fissile, n.o.s. III. Use Guide to Det ermine: L a. What specification container is required. h. hhat labels are required. c. Whether a security seal is needed or not. d. mR/hr limits 4 contact. e. Add:tional requirements. l l 1 l l i l ho f( SAE

9 m i \\ (s./ i I E spirinri ty mAlte14 P a r L AC D.f.I.r_} h.t ~'*l k! AL Pl.%rKiriach Cosiar%tt Langt $rctraits $LAL 3 r;;s k% At ra 6 ACIL*. eA/hr LIM!i$ # CDhiACT COFelrhT5 T\\ ?L Rf ot'1ELV RI. QUI RI O kLJut KI D < esso tri 50L;t) aan 1414L 0-200.0 Unspet a fied 4 A&d icar t i s e w. t re s s!. D-spe.sfsed Sadi oac t iv e-LS A no LIA. n.o.s. ( e sc lua i ve - ae) 0-0.5 mAlte 1:e ns e t AsJa cart.' c e st er; ni. W

  • pec;fs ed Eaoscactioe no Un sprs t f a ed coe t a : t 0-i.0 :(

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d. Radicatt a te Slateriel.

D07 ).7 74 4 &adics: ate yes B rac ed 0 0.5 keouire.eiret 7 praetes cp nota n.o.s. [37g) shave ; $see of park.tre Eadicactive yes treced 0.5 50.0 ,,,n 3, I'lI'* II of 120 Its. Rasseartase yes Braced SC.0-200.0 1ello. 111

e. Radioac ti ve lute rna!.

DUT 7A irpe A Ra ci ca r t s ve yes Brac ed 0-0.5 Acousre me2re.t spec;al t'o r g, n.e.s. (17H) anste 1 prant ed or out-Basicartsve yes f rac ed 0 $-50.; sace of Dackere on ce. se escess telle. !! $0.0-200.0 of 130 lbs. Radioactive yes B rac ed tellow !!! (??L1 j 56%LL VC1.it'5 LIOL'!O! l

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  • Lee Instruction 0-200.0 l

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l n.e.s. DOT 7A Type A Lad 3cacithe yes

  • $ee Instructions 0-0.5 keguare mes5 !

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  • 5ee !rstructions wr.ee so earess cf 110 lbs.

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e (twiVLi LAACE VCLUM! L:0L' IDS

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DC7 17h Eadscactate LSa no "See In s t r uc t i on s 0-700.0 L5 8 n.e.s. (es:!usare use} l L. Lad cart s we >Jt ersal. DOT 7A 1ype A Lads cac t a t e yes "See Instruct ens 0-0.5 accusre ves rht n,c a. !!?P hhtte i granted or cu' l Ladioactas* ves "See Instructions 0.5 50.0 ssee of par sar* wnen se estess l g,3,o. 3; Ead aoac u ve ves

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A O T TELEDYNE U V ISOTOPES { PACKAGING PROCED'JRES FOR RADI0 ACTIVE WASTE I.0 CENERAL j I.1 Categories of Radioactive Waste: Dry Solid Material (DSM) Dry solids Bulk Scintillation fluids for Reprocessing (BLK) a Small Volume Liquids (SVL-5) Scintillation vials only Small Volume Liquids (SVL-A) Vial waste for burial Large Vclume Liquids (DWLVL-A) 50 ml or greater of aqueous liquid waste Animal Carcasses (DWAC) or biological waste Dry Solid Compatibles (DSC) Dry solid and compactible waste only I.2 Items in different categories cannot be mixed. I.3 The packaging procedure that is used is to be marked on the drum (e.g. { DSM-1/86). i I.4 Transuranic waste in excess of 10 nanocuries per gram is not accept-able. I.5 Gaseous tritium waste must meet certain provisions., Please see the burial site's license for details or call the Radiological Services Department Office. I.6 Special Nuclear Material requires specific approsal and will be accepted only upon special request to the Radiological Services Department Office. 1.7 DO NOT EXCEED THE FOLLOWING WE IGHTS UNLESS SPECIFICALLY AUTHORIZED: 5 gallon container - 100 lbs. 30 gallon container - 280 lbs. 55 gallon container - 480 lbs. I.8 Chemical Toxicity: The chemical composition of the materials disposed must be compatible with t he procedures which follow. Any addit ional hazards of the mat erial must be es aluat ed t o det ermine if addit ional packaging is required. If mat erials are list ed in N. Irving Sax's " Dangerous Propert ies of Indus-trial Mat erials", Fi f t h Edition. Van Nostrand Reinhold, as hasing a THR=HICH sia any route, except IP or IV, specific approv al must be ob-t ained from t he St at e of Washington Radiat ion Cont rol Progran. Cont act the Radiological Sersites Department for details. 1/86 (1)

TTELEDYNE O O ISOTOPES I.9 Prohibitions Alt hough Toluene and Xylene wastes are not acceptable for burial, they may be acceptable for reprocessing. Contact the Radiological Sersices Department for details and see Section IV for the proper packaging procedures. I.10 Special Notes Two 2 ml liners may be used in place of a single 4 m1 liner. Instead of lining the whole drum, individual 4 ml (or double 2-ml) bags may be substituted, provided each bag is layered as above. Approved absorbants: Diatomaceous Earth (Medium Grade) Super Fine (Diatomite) Speedi Dry Hi-Dry I Celatom (M-P79) Floor Dry 85 Superfine Instant-Dri Safe-T-Sorb (Petrasorb) Vermiculite - Industrial Grade 4 (Zonolite #4) l 1 ) When layering, the absorbant must be the first layer on the bottom and the last layer on the top. Proper solume ratios must be determined by ) the generator to be used for the different absorbants. The amount of absorbant must be capable of absorbing twice the amount of liquid present. I.11 VOIDS - All voids in the containers must be filled to the extent practi-cable. 11.0 DRY SOLID MATERI AL (DSM-1/86) 11.1 Select a 5, 30 or 55-gallon drum. 11.2 Fill to capacity with only dry solid materials. 11.3 Secure drum coser. II.4 Label drum DSM-1/86, to designate that the drum has been p a c k m;ea d according to these directions. 1/86 (2) l

TTELEDYNE V .Or~ n ISOTOPES ) 111.0 DRY SOLID COMPATIBLES (DSC-1/86) ~ ' " III.1 Select a 5, 30 or 55 gallon container. i III.? Place waste into double 4 mil plastic liners. (Note: For 55 gallon -] drums, use two sets of double 4 mil bags, each set approximately 27 i gallons. If heasy materials are used, please use additional double a mil liners and decrease the quantity put into each.) 1 III.3 Twist arid seal liners. j i III.A Place double 4 mil bags into the selected container. ) i III.5 Replace lid and ring. ) I 111.6 Secure ring. 00 NOT BOLT. III.7 L abel crum DSC-1/86 to indicate it was packaged in accordance with these inst ructions. NOTE: DO NOT DISPOSE OF UNPROTECTED SHARP OBJECTS._ NOTE: DO NOT DISPOSE OF NON-COMPACTIBLE ITEMS SUCH AS LEAD PIGS OR OTHER METAL l l l OBJECTS IN THESE TYPES OF CONTAINERS. IV.0 SMALL VOLUME LIQUID WASTE FOR BURI AL (SVL-A-1/86) i These drums can contain vials which contain liquids which are acceptable for burial, and each vial must contain less than 50 ml of liquid. Liquid should not be absorbed directly onto the absorption media (e.i. do not open slals). Any tool or device which contains any amount of liquid ( e.g. syringes or test tubes) must be considered small s olume liquid waste. IV.1 Select only a 30 or 55-gallon drum; 5-gallon pails are not allowed. IV.2 Line the drum with 4 m1 thick poly liner. (See special notes follow-ing this sect lon.) IV.3 Using an approsed absorbant, alternat e layers of absorbant with layers of waste. (See special notes at the beginning of this section.) IV.4 Twist and seal liner. IV.5 Secure drum coser. 1/86 (3) lL

1 (3 C "WTELEDYNE V ISOTOPES }' j IV.6 Label drum SVL-A-1/86, to designate that the drum has been packaged' according to these instructions. IV.7 Special Note: Toluene, Xylene and other flammable scintillation media in scintillation vials will not be accepted for burial. They must be packaged for reprocessing and meet the reprocessor's license criteria. V.0 SMALL VOLUME L IQUID WASTE FOR REPROCESSING (SVL-X, SVL-M, SVL-R-1/86) These drums may contain scintillation vials which contain Toluene or Xylene or any other flammable scintillation media acceptable cecording to Quadrex's License No. 1354-1 (State of Florida, Department of Health & Rehabilitative Services). 4 V.1 Select only a 30 or 55-gallon drum. l i V.2 Line the drum with 4 m1 thick poly liner. V.3 Add 12 inches of an approved absorbant. V.4 Line drum again with another 4 m1 thick poly liner. V.5 Fill with vials to capacity. V.6 Twist and seal liners. V.7 Secure drum cover. V.8 Label drum SVL-X (1/86) or SVL-R (1/86) or SVL-M (1/86) to designate that i the drum has been packaged according to these instructions and contains either' exempt, R_egulated, or M_ixed scintillation vials. VI.0 LARGE VOLUME LIQUID WASTE (DWLVL-A-1/86) All it ems containing 50 ml or more of liquid may not be disposed in an SVL drum. The liquid must be packaged as follows while the con-tainer itself must be either (1) dried and placed in a OSM drum or (2) placed in an SVL drum once the bulk of the liquid is removed. i VI.1 Select only the 55-gallon double-walled container for liquid waste. VI.2 Remove the SS-gallon drum cover. VI.3 Loosen and remove the bung from the 30-gallon drum which has been j filled with Zonolite #4. 1/86 (4)

T TELEDYNE O O ISOTOPES l } 1 VI.4 Pour up to 10 gallons of liquid (pH-6.0 - 9.0) into the absorbant in ' the 30-gallon drum through the 2-1/2" opening. i VI.5 Replace bung and tighten. VI.6 Twist and seal poly liner. VI.7 Secure cover of 55-gallon drum. VI.8 Label drum DWLVL-A (1/86) to designate that the drum has been packaged according to these instructions. VI.9 SPECIAL NOTE: 1 Toluene or Xylene and other liquids unacceptable at the burial site cannot be absorbed. VII.0 ANIMAL CARCASSES OR BIOLOGICAL WASTE (DWAC-1/86) Animal carcasses or biological waste must be disposed using a double-walled container. Be sure when ordering to specify a 55-gallon double-walled container for animal carcasses. VII.1 Select only a 55-gallon double-walled drum. i VII.2 Remove inner 30-gallon container and absorbant. VII.3 Line 30-gallon drum with 4 ml poly liner. See Section I.10. VII.4 Package waste into liner using at least one part slaked lime for esery I 10 parts of absorbant. See approsed absorbant list in I.10. Fill completely. VII.5 Twist and seal liner. VII.6 Seal 30-gallon drum. VII.7 Place 30-gallon drum into 55-gallon drum, i VII.8 Place absorbant around and cosering 30-gallon drum. VII.9 Secure 55-gallon drum coser. VII.10 Label drum DWAC-1c'86 to designate that drum has been packaged accord-ing to these instructions. 1/86 (5) a_-__ _

'WTELEDYNE b, b,~ ISOTOPES 3 VIII.0 BULK SCINTILL ATION FLUIDS FOR REPROCESSING (30-BLK-1/86 or 55-BLK-1/86)- j VIII.1 Select only a 30-gallon or 55-gallon container. VIII.2 Line drum with 4-m1 thick poly liner. VIII.3 Add 4 inches of an approved absorbant. VIII.4 Place 5 one-gallon bottles in the bottom of the container. VIII.5 Add absorbant to cover bottles. VIII.6 Place a cardboard disk into the container to provide stability for the next row of bottles. VIII.7 Repeat steps 3, 4, 5 and 6 two more times, and top off container with i absorbant. VIII.8 Twist and seal liner. VIII.9 Secure drum cover. l VIII.10 Label drum 30-BLK-1/86 or 55-BLK-1/86 to designate that the drum has been packaged according to these instructions. I 1 i 1/86 (6)

Stevens. Ins titu te of T<echnology Byprodue t Ma terialsdense #29-05263-05 bm Appendix 3 } STEVENS INSTITUTE OF TECHNOLOGY E GUIDE FOR SPECIFIC PROCEDURES j l Ihe procedures con tained in this appendix are acceptable to the NRC for use by medical licensees engaged in routine diagnostic and therapeutic precedures. 1 Any applicant who wishes to adopt these procedures may simply reference them in his applica tions. The reference should include the date of issue of this guide. I. INSTRUCTIONS FOR SAFELY OPEN1NG PACKAGES TO COMPLY WITH SECTION 20.205, 10 CFR 20 Cer tain packages recuire monitoring of radia tion levels and of external j surfaces for con tamina tion within a specified time af ter receipt [see 10 CFR 20.205 (b), (c)]. No te tha t prac tically everything received by a hospital with { few exceptions (example: liquid tritia ted compounds grea ter than 10 mC1) is exempted from this. However, 20.205 (d) requires tha t procedures be - l 1 established for " Safely Opening Packages" of all licensed material with no ex cep tion s. The outline given below is provided as a model and is one method of fulfillmen t of 20.205. l h General Se t-up l

1) Packages should be delivered to one specific loca tion in the ins titution (e.g. Radia tion Safe ty Cfrice or Nuclear Medicine j

Labora tory) where personnel are knowledgeable in safe handling. Establish a specific loca tion within the lab for receipt and inspec tion. Trea t as con tamina ted un til proven o therwise, especially if damaged. Place package on surface with absorben t ma terial during survey.

2) Arrange to open and inspec t packages as soon as possible af ter l

receipt. Ite=s B-4 and 5 will aler t personnel to the in tensi ty of j the radia tion field in which they are working; B-6 and 8 will warn of any con tamina tion. Page 11, 2/22/83 j l

e S tevens Ins titu te of,7'chnology gs Byproduc t Ma terials ( janse #29-05263-05 (,) Appendix 3 =

3) Plan to make a record of results and pass on to final user to alert

} him to condition of the shipmen t. This record is also useful in communication with the vender in case of problems.

4) Plastic or o ther pro tec tive gloves and lab coa ts should be worn for opening packages for the pro tec tion of the surveyor.

l 1 5) If the manufac turer's direc tions for opening or unpacking radioac tive l ma terial are provided, follow these direc tions in addition to those l below. i l l

6) Packages con taining radicac tive materials with associa ted high exposure levels may require some or all of the following s teps to be l

performed behind a radia tion shield and/or using o ther appropria te l safe ty measures. j 1 B. Procedure for Packages Inspec tion (See NOTE #1) ] l

1) Receive in prepared, pro tec ted place.

~ l

2) Observe for mechanical damage--record condi tion.
3) De termine if exempt from reauired inspection--record.

a. if exemp t--con tinue when prac tical (no t required by NRC) b. if not exemp t--con tinue wi thin 1. 3 hrs if received during normal work hours 11. 12 hrs if received af ter nor=al work hours l l NOTE #1 - In institutions with separa te Radia tion Pro tec tion Offices (RPO) and user labora tories, the RPO may only do ex ternal measuremen ts on the package (i.e. B-1 thru B-6). The remainder of the procedures may be performed by the user labora tory. Page 12, 2/22/83 ) l

q \\ Stevens Ins titu te f', Technology k] I Byprodue t Ma teriali,- icense #29-05263-05 Appendix 3 1 l 1

4) Measure exposure ra te at 3 fee t from package surface--record.

a. if >10 mR/hr-proceed with caution-expedite notifica tion. l

5) Measure surface expcsure ra *x and record, i

i if >200 mR/hr-proceed wi th cau tion-expedite no tifica tion.2 j a. i

6) Observe outer package for leakage stains--record condition a.

if s tains present--wipe 100 Cm area with dry wiipe and, 2 3 assay -record. l b. if wipe has >0.01 uti (22,000 DPM)--proceed with caution. Expedi te no tifica tien.2 1 I

7) Open the outer package and remove packing slip.

Open inner package l l to verify con ten ts (co= pare requisition packing slips, label on bo ttle) and in tegrity of final source con tainer (inspec t for break-age cf seals or vials, less of liquid, discolora tion of packing ma terial). Check also ' hat shipmen t does no t exceed possession limi ts. i

8) Wipe ex ternal surfacI of final source container with moistened 3

co tton swab or fil ter paper held with forcepts, assay and record. 3

9) Moni tor the packing n:aterial and packages for con tamina tion before discarding:

a. if con tamina ted, trea t as radioac tive was te, b. if no t, oblitera te radia tion labels before discarding in regular trash. 1 Use thin window de tee tor (if the outside is con tamina ted, it will de tee t be ta par ticles tha t could be en ex ternal radia tion ha:.ard).

  1. No tify immedla tely:

a. The public carr ier tha t delivered the package, b. The NRC Regional Office of Inspec tion and Enforcemen t (by the phone and telegra ph. ) An end wjndow GM or gas flow propor tional coun ter (with window thickness _ 1.5 mg/cm normally may be used for assaying be ta emitters a t or above C-14 energies; low energy be ta emitters will require liquid scin tilla tion coun ting. A gamma-scin tillation coun ter should be used for pure gamma emitters. 1 l l Page 13, 2/22/83

S tevens Ins ti tu te c'"']echnology ()' .e : Byproduc t Ma terials Cicense #29-05263-05 1 ) RADI0 ACTIVE SHIPMENT RECEIPT REPOR4 l 1. P.O. # SURVEY DATE TIME I i SURVEYOR 2. CCNDITION CF PACKAGE: OK PUNCTURED STAINS WET 1 l CRUSHED OTHER ] I 3. RADIATION UNITS OF LABEL: UNITS (mR/hr) 4 MEASURED RADIATION LEVELS: a) Package surface mR/hr b) 3' from surface mR/hr 5. DO PACKINO SLIP AND VIAL CONTENTS AGREE? ~ a) Radionuclides yes no difference b) Amoun t yes no difference } c) Chem Forr. yes no difference i 6. WIPE RESULTS FROM: a) O'u ter CPM = DPM eff=( ) i b) Final source con tainer CPM = DPM eff = ( ) 1 7. SURVEY RESULTS CF PACKING MATERIAL AND CARTONS mR/hr, CPM l above Ekg. 8. IF PACKAGE WAS SHIPPED WITH DRY ICE, WAS DRY ICE PRESENT IN PACKAGE AT TIME OF RECEIPT? yes no n/a 9. DISPOSITION OF PACKAGE AFTER INSPECTION: 10. IF NRC/ CARRIER NOTIFICATION REOUIRED, GIVE TIME, DATE, PERSONS NOTIFIED. Page 14, 2/22/83 i s

y 8' ottochment 8 [] ENS INSTITUTE OF TECHNOLOGY POLICY ON RADIOACTIVE MATERIALS-APPENDIX 2 i y

1) - The Stevens Institute c4 Technology'Radiatice Safety Committee shall con-sist of all the indiv. duals listed in item 6 of the Byproduct Material License and the Radia'. ion Safety Officer (RS0).

These individuals shall supervise and instrucc anyone using radioactive materials. I l

2) 'No one at Stevens Tascicute of Technology shall acquire e.ny radioactive l

material without prfor authorizt;. tion by the RSO. The purchasing agent is L instructed to get t te approval of the RSO before processing a purchase l order for any radioactive material. No donations of radioactive materi-l als or equipment cont.cining radioactive materials are to ' be accepted without the prior written u nent of the RSO.

3) Persons who wish to dispose of radioactive materials should notify a mem-l ber of the Radiation Safety Committee who will handle and be responsible for the disposal.
4) The RSO will appoint one or more persons to be responsible for.the radio-l active materials used at Stevens Institute of Technology.

Twice 'a year -) it is the responsibility of the designated persons to make a complete list of the radioactive materials. This list will include the name and isotopic number, the date of acquisition, the original activity and the present activity of each source. One copy of the list signed by the designated person must be sent to the RSO.

5) Twice a year the persons designated by the RSO will conduct a wipe test of all sealed sources.

The test should be capable of detecting the presence of.005 microcuries. If more than.005 microcuries is detected, the RSO must be notified immediately. The test results for each source must be sent to the RSO. The results must be entered in microcuries not counts /sec.

6) Upon receipt of any radioactive material, the procedures outlined in

" Guide for Specific Procedures" should be used (see Appendix 3). 7) In areas where unsealed sources are in active use, wipe tests should be conducted weekly. Areas where it is reasonable to assume that contam-ination might occur should be tested. The test should be capable of de-tecting the presence of.005 microcuries. If more than.005 microcuries is detected, the RSO must be notified immediately. The test results must be recorded in a log book in units of microcuries not counts /sec.

8) The persons designated by the RSO must measure radiation levels.in those areas where radioactive materials are used. The results of these surveys should be used to estimate the radiation dose received by persons who work in these areas.
9) The RSO will conduct surveys in addition to those in item 8.

The results will be raccrded in the log book kept by the RSO.

Re: Stevens Institute o echnology /'~~)$ Policy on Radioactis Materisis ~ Appendix,2 l /

10) It is the responsibility of the persons designated by the RSO to af fect are added to or i

the appropriate changes when radioactive materials recoved from a license. Questions concerning licenses should be directed l l to the RSO. 11) It is the responsibility of the persons listed in item 6 of the byproduct license to insure that all requirements of a license are adhered to. 1

12) The RSO is available to answer questions regarding radiation and radia-tion safety.

I i I i 1 I l I l l ) l 3/18/86

o O 4 d ? " Mfgf i BETWEEN: William O. Miller, Chief 7w/vo 4,,* License Fee Management Branch Office of Administration 3[FJ John E. Glenn, Chief Nuclear Materials Section B . Division of Engineering and Technical Programs LICENSE FEE TRANSMITTAL \\ A. REGION 4 \\ 1. APPLICATION ATTACHED A k Applicant / Licensee: hWWOh'~ThNh1MP r$N&hndOCp i Application Dated: ) On V1 i Control No.: 106689 i License No.: Sh@- \\( 'M l 2. FEE ATTACHED Amount: O Check No.: n 3. COMMENTS 1 Signed Synk6 hhtde. Date } a% W/ B. LICENSE FEE MANAGEMENT BRANCH 1. Fee Category and Amount: sy /P F/9O /kf 2. Correct Fee Paid. Application may be processed for: Amendment Renewal \\, License Signed &f f 7 Date I / REGION I FORM 213 j (MARCH 1983) i ..}}

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