ML20128F587

Matls Licensing Package for Amend 7 to License SNM-0114 for Univ of PA.Control:116935

ML20128F587
Person / Time
Site:	07000123
Issue date:	10/28/1992
From:	Johansen J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
References
116935, NUDOCS 9302110467
Download: ML20128F587 (21)

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I M ATERIALS LICENSE Amendment No. 07 h

Pursvant to the Atomic 1:nergy Act of 1954, as amended, the Enctgy Rentganit.dion Act of 1974 (PuhHe Law 93-1381, anxi16 tie 10.

[ Cale of Federal Regulatkms, Chapter I, rans 30, 31, 32, 33, 34, 33,39. 40 ard 70, and in trhatwe on s.tatem<r t4 aid reprewmatkan here4ofoic l

r li ennde by the hccmce, a hcenw n hereby iuued authottring the igensee to rettive, a

! nuttect material designated telow; to usc swh material for the purpnets) and at 0.e plue(s) desigtuint bekm; u dehver or teander such rnaterial h

to perums authoritni to rucive it in accordne m ah the reguistiom of une appucabte rac(ih This th eme shall be deemed io tuntain 0>e condition. f sprined in serthin 18) of the Atonac l'.ncrgy Act of 1954, e anwreed, ard is subjett to all appik able teles, regulations and orders of the Nx! car y

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Regulatory Commlukm now or hercahcr in cHect und u py corditam specined below.

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3. Ucena number Stim-114 is amerded in

[J Radiation Safety Office its entirety to read as follows:

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( A. Plutonium (Principal #

' ANSealed neutron sources' A. 50 grams contained in 3 [

lsotope Pu-239) c b(Mound Laboratories)-

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To be used for laboratory studles,41ristrument calibration and student instruction.

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Scaled in a fission' counter. tube for educational, purposes or in storage.

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Licensed material may be used only at the licensee's-facilities at the University of. f n

Pennsylvania, Philadelphia, Penrisylvania.

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Licensed material shall be used by, or under the supervision of, Individuals N

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The Radiation. Safety Officer for this license is Mark II. Solikson, Ph.D.

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Scaled sources or detector cells containing licensed material shall not be opened or

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Scaled sources and detector. cells shall be tested for leakage and/or contamination at intervals not to exceed 6 months or a;' such other intervals as are specified by the certificate of registration referred to in 10 CFR;32.210, Q -

not to exceed 3 years.

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Notwithstanding Paragraph A of this Condition, sealed sources designed to emit eE en alpha particles shall be tested for leakage and/or cantam nation at intervals

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CONDITIONS I

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In the absence of a certificate from a transforor indicating that a test has been p j

made within six months prior to the transfer, a sualed source or detector cell received from another person shall not be put into use until tested,

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Each sealed source fabricated by the licensee shall be inspected and tested for construction defects, leakage, and contamination prior to any use or transfer as 9

a sealed source.

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Sealed sources and detector cells need nut be leak tested if:

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4 (i) they contain only hydrogen 3; or h-h'

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l (iv) they contain not more than 100 microcuries of beta and/or gamma emitting I

material or not more than 10 microcuries of alpha emitting material; or p

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(v) they are not designed to emit alpha particles,-are in storage, and are not' b

However,whentheyareremovedfromstorageforusenrtran J

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to another aerson, and have not been tested within the required leak test interval, t1ey shall bo tested before use or transfer.. No sealed source or ej

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being tested for leakage and/or contamination.

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The test shall be capable of detecting the presence of 0.005 microcurie of di k,i radioactive material on the test sample.

Records of leak test results shall be kept in units-of microcuries and shall be maintained for. inspection by the f4 Commission.

If the test reveals the presence of 0.005 microcurie or more of y

removable contamination, a report shall be. filed with the U.S.- Nuclear Regulatory M;

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4 Commission and the source shall be removed from service and decontaminated,

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4{i repaired, or disposed of in accordance with Commission regulations.

The report shall be filed within 5 days of the date the leak test result is known with the h

U.S. Nuclear Regulatory Commission, Region I, ATTN:

Chief, Nuclear Materials y

jl Safety Branch, 475 Allendale Road, King of Prussia, Pennsylvania 19406.

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F report shall specify the source involved, the test results, and corrective taken.

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The licensee is authorized to colle" leak test samples for analysis by the I

licensee. ' Alternatively, tests for leakage _and/or contamination may be performed g El by persons specifically licensed by-the Commission or.an: Agreement State to.

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CONDITIONS i>

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License No. SNM 114 Docket No. 070-00123 Control No. 116935 University of Pennsylvania ATTN: Mark II. Selikson, Ph.D.

Radiation Safety Office 1412 Illockley IIall 418 Service Drive Philadelphia, Pennsylvania 19104-6021

Dear Dr. Selikson:

Please Dnd enclosed the renewal of your NRC Material License.

Please review the enclosed document carefully and be sure that you understand all conditions, If there are any errors or questions, please notify the Region I Material Licensing Section, (215) 337 5093, so that vec can provide appropriate corrections and unswers.

Please he advised that you must conduct your progmm involving licensed radioactive m9terials in accoidance with the conditions of your NRC license, repivsentations made in your license application, and NRC regulations, in particular, please note the items in the enclosed, " Requirements for Materials Licensees,"

Since serious consequences to employees and the public can nsult from failure to comply-E with NRC requirements, the NRC cxpects licensees to pay meticulous attention to detail and to achieve the high standard of compliance which the NRC expects of its licensecs, You will be peliodically ins.nected by NRC. A fee may be charged for inspections in I

accordaec with 10 CFR Par 6 i rc Failurc to conduct your program saicly and in acconiance with NRC regulallons, license conditions, and representations made in your license application and supplemeatal correspond:nce whh NRC will result in prompt and vigorous enforcement action against you. This could include issuance of_a notice of violation, or in can of serious violations, an imposition of a civil penaky or an order L

suspending, modifying or revoldng your license as specified h the. General Policy rmd -

3 Procedures for NRC Enforcement Actions 10 CFR Past 2,' Appendix C.

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i University o'f Pennsylvania 2-l We wish you success in operating a safe and effective licensed prognun.

Sincerely, L. J : t.

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Jenny M. Johanson Jenny hi. Johansen, Chief hiedical Licensing Section.

Division of Radiation Safety'-

and Safeguards-

Enclosures:

l. Amendment No. 07

2. Requirements for hinterials Licensecs

3. NRC Forms 3 and 313 I

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DRSS:RI DRSS:RI Stamba gh/cmm Johansen 10/t4 92 10r) /9 OFFICIAL RECORD COPY - G:\\WPS\\hiLTR\\LSNhil14 '- 10/07/92:

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AUG 201992 l

Docket No. 070-00123 License No. SNM 114 Control No. I16935 University of Pennsylvania NITN: llarry Coopeerman, M.D.

Radiation Safety Office 14th Floor Illockley liall/6021 418 Service Drive Philadelphia, Pennsylvania 19104

Subject:

LICENSE RENEWAL APPLICATION This is to acknowledge receipt of your application for renewal of material (s) license identified above. Your application is deemed timely filed, and accordingly, the license will not expire until linal action has been taken by this office.

Any correspondence regarding the renewal application should reference the control number specified above.

Sincerely, ewyd F31gned By:

Oncry! R. Earaher Sheryl Villar, Chief Licensing Assistance Section Division of Radiation Safety k @/.

and Safeguards

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118 Sen 6tv lhiw l'hilailt ipW. l'A 19101Mul 215 s9%.7167 l'au 215.s9s-ol to July 29,1992 U.S. Nuclear Regulatory Commission Nuclear Materials Safety Section A 475 Al!ondale Road King Of Prussia, PA 19406 Subject :

Application for Ronowal SNM 114 Prograrn Codo 22120 Gentlemen:

In accordance with your lotter of May 1,1992, the onclosed maiorial la submittod in support of our request to renew Special Nuclear Material Licenso SNM 114.

No licenso ronowal foo is enclosed pursuant to 10 CFR 170,11(a) 4.

Please send the tonowal license or direct any inquires to the attention of :

Mark H. Solikson, Ph. D.

University of Pennsylvania Radiation Safety Offico 1412 Blockley Hall 6021 Philadelphia, PA 19104

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o Pr gr:m Cods 22120 Univ:tsity of P:nr.sylv:nla CNM.114 l.icense Renewel P ge 1 cf 4 REQUEST FOR RENEWAL OF SPECIAL NUCLEAR MATERIAL LICENSE SNM-114 The application format follows the format statectin REGULATORY GUIDE f 0.3 4.1 Snedfkation of Aoghcant The Trustees of the University of Pennsylvania, Philadelphia, Pa.19104, 4.2 Specification of Activities to be Performed The material will be used as a source of neutrons for calibrating instruments and devices or for investigating the effects of neutrons on materials and systems as part of the University's undergraduate, graduate and professional teaching programs.

4.3 Sacdfication of Soecial Nucigar Material Three PuBo neutron sources manufactured by Mound Laboratories Manufacturer's Total Plutonium Pu 239 plus Pu 241 S.ttial.NQ, Wt Grams W1. Grams M 119 14.85 13.82 M-143 14.91 13.87 M-14 G 14.74 13.70 One Westinghouse Model W1. 6376 fission counter tube containing 1.68 grams of Uranium enriched in U 235 (20%)

4.4 Technical Qualifications of Personnel Mark H. Solikson directs the radiation safety program and is the Radiation Safety Otlicer for all the University's licenses. He is certiflod by The American Board of Radiology in Medical Physics and has over 15 years' experience in University Radiation Safety. His CV is on file with the University's NRC license 37-00118 07.

The use of those materials will be directly supervised by personnel approved by the Radiation Safety Committeo. These personnel will, at a minimum, have training and experienco in the following:

i) principles and practicos of radiation protection, li) radioactivity measurements, standardization, mnnitoring techniques and instruments lii) biological effects of radiation, and Iv) math and calculations basic to the use of radioactivity 4.5 Qcactlption of Eaulomont Facilities andlagtrumentation 1.

Remoto handling tools are available. Those tools are from one to two meters in length.

2.

Metal paraliin lilled storago containers are available. Also blocks of paraffin. lucito and conctole are available for additional shielding. All sources are stored and used in locked or attended areas.

3 The sources are normally mounted at the end of a 1 meter metal rod or wire and local shielding is used if the source is removed from the storago container for any length of time. The sources will be placed in a shielded storage container whenever they are transferred between laboratory buildings, 4.

Standard university laboratory Iacilities are available. Sealed source uso only.

5.

Radiation Detection Instruments The following is a partiallist of the current instrumcnts available for use;

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Pr:gr:m C:de 22120~ Univ:rsity cf Pennsylv:nia SNM 114 License H;newal Page 2cf 4 Four tonization chamber survey meters, two Victorcon Model 470A and three Klethley units, Model 36100, Model 36150 and Model 36tSS.

Seven Ludlum survey meters; two Model 16, four Model 3 and one V dal 12-4 Neutron counter. Soveral GM tubo detectors Modei 44-2 and 443 mma probes, and a Model 43-1 alpha probe are used with the Ludlum surycy meters.

One Nuclear Measurements Corporation Model PC 5 Das how proportional couMor with associated Ngh voltage scalar and timer.

One multi channel analyzer Tracor Model NT7200 system with a variety of phototube-scintillation crystal detector assemblics.

One 1.udium Model 15 neutron counter.

One LKB Model 1214 liquid scintillation system.

One Harshaw Thermoluminescence dosimetry system with over 100 dostmeters.

We reserva tha right to replace theso instrumonts provided our overall measurement capabilities remain unchanged.

Instrument Calibration The neutron detecting instruments are calibrated annually. Either the PuSe sources are used for this calibration or the instruments are returnod to the manufacturer (Ludlum )

ior calibiation.

The gamma survey meters are calibrated annually using a J. L. Sirepherd, Model 28-6 Calibrator SN# 10235, Ceslum 137, 600 mC! on 6/9/89.

The alpia beta and gamma laboratory instruments are calibrated annually using standard 3rence sources with calibrations traceable to National Institute of Standards and Technology (NIST).

All calibrations, & ^ I at the University are done or supervised by individuals 4

approved by th, 5

.R Radiation Safety Committee and who meet the training 4

requirements of iten 4.4 abcve.

We have e?tablished the model procedure for calibratin0 instruments that was published in Appendix B to Regulatory Guide 10.8 Revision 2. The Cs-137 source and other alpha, b~ ta and gamma sources used in calibrations performed at the university are licensed under the NRC hcense 37 00118-7 which is under timely renewal.

4.6.1 Smifications of RadiationMfety Resconsibilities and Duties The Radiation Safety Committee (RSC}of the University of Pennsylvania has established policies concerning the use of radioactive materials in all departments of the University.

The Composition of the RSC, its responsibilities, duties and current Chairman along with inforrnation on the University's Radiation Safety pr: gram are detaihd in the University's NRC license 37-00118-07. The current Chairman of the RSC is Rc5ert Roosa. Ph. D.

Full authority and responsibibty for the p ogram is vested in the Radiation Safety Committee. TNs Committee meets at least cuarterly to review the conduct of the -

radiation safety program. A fully stafled Radiation Safety Offico under the direction of Dr. Mark H Sekkson, carriee out the radiation cafety program, The current staff of the

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Progr6m Code 22120 Univ:rsity of Pennsylvania SNM-114 Lic:n s Hin:wal '

' Page 3 cf 4 Radiation Safety Offico consists of seven heaith physicists seven technicians.

two secretarles, an information management specialist and an office manager.

All prospective users and new uses of radionuclides must be applied for in a manner analogous to application for a specific byproduct materiallicense. Upon rece3pt of an application. the Radiation Safety Office prolossional staff evaluates precautions, -

discusses precautionary measures with applicant (s) and prepares comments upon the application. The application and comments ar Wated to a review Committee cotr. posed of selected members of the Radia*

v sy Comtr.# tee. The designated review Committee may approve, disapprove or g sy the need for additional informahon or evaluation of the application. All actions upon applications are reviewed as part of the agenda at the next regular meeting of the Radiation Safety Committee.

4.6.2 Personnel Monitodna Personnel monitoring will be provided pursuant to 10 CFR 20: 202 and the exposure from all sources of ionizing radiation at the Unborsity is considered. All authorized users register their radiation workers with the Radiation Safety Office. The Radiation Safety Office maintains a computertzed listing of all radiation workers that is cross indexed to the I

list of authortzed users which identifies the sources of ionizing radiatton to which their personnel may be exposed. NVLAP approved commercial service will be used, Currently R. S. Landauer Jr and Company provides our service.

t i-4.6.3

.Radwion Survev Progf am The neutron and gamma radiation levela are measured and/or evaluated for all new configurations of use and storage. Surveys are repeated annually or whenever there is a change in the source shielding or use.

4.6.4

. ne Discosal No wastes are expected. Should there be a need to dispose of the materia'ts 't will be transferred to a licensee specifically authorized to receive it.

4.6.5 Record Manacement All required records will be reviewed by and kept in the University Radiation Safety Office.

4.5.6 Material Control Provisions No additional materialwill be procured (without license amendment).

4.6.7 Sealed Source Leak-Tostina Provisions 1.

The sources will be leak tested at intervals not exceeding six months. The test sample will be taken from the source or from an appropriate surface of the device in wHch the source is installed or mounted. The test wTil be capable of detecting 0.005 microcuries of alpha contamination on the test sample.

2.

a) The test will be performed by personnel approved by the Radialon Safety Committee per item 4.4 above.

b) Time distance and shielding considerations will be used to minimize personnel exposure. Remote handling tools will be used to handle the source, the time the source is removed form its storage container will be minimized during leak testing.

=

a

m-o:

o Program Cods 22120 - University cf Pennsylv:nb CNM.114 Ucense Ren wal Page 4cf 4 e

c) The test procedure involves either wiping the source with moistened fitter paper or washing the source in a mild detergent or solvent solution.

The wipe sample is dded and counted and the liquid sample is evaporated and

counted, d) A windowless proportional detector or a liquid scintillation system will be used to assay the test samples.

The windowless proportional counter is a Nuclear Measurements Model PC-

5. The Ilquid scintillation system is a LKB Model 1214.

4.68 AgperalSatety Instmeijans See enclosure (1). Radiation Safety Users Guide" 4.6.9 Emeroency and Decontamination ProcedyIgg All campus Emergency phone numbers connect individuals with campus Security who activate the Emergency response per the Emergency Response Personnel Listing. Enclosure (11).. This listing is updated at Mast yearly, Also see enclosure (l) Radiation Safety Users Guide. "

4.6.10 Procedures for Trainina Personnel See enclosure (I) Radiation Safety Users Guide."

i

" We reserve the right to revise and update the Radiatbn Safety Users Guide provided tha changes do -

not diminish the radiation safety practices as related to the use of the Special Nuclear Material authorized by this license.

The following information is provided as a supplement to NRC Form 313 (3 92) in -

support of our request to renew SNM 114.

Item 5 See item 4.3 above lism 6 -

See item 4.2 above L

L ltem 7 See item 4.4 above i

Item 8 See item 4.6.1 and 4.6.10 above n

item 9 See item 4.5 above g

^

Itsm 10-See item 4.6.1 through 4.6.10 above item 11 See item 4.6.4 above I

Pj

o o

ENCLOSURE 11 MEMORANDUM TO.

Authorind Users

. title.

. campus add.

FROM:

Mark H. Selikson, Ph. D.

Director DATE:

June 30,1992 SUBJ:

EMERGr.NCY-RESPONSE PERSONNEL LISTING j

Following is a listing of numbers to call when there are emergeachs involving radioactive nuterials.

During wgular University hours (Monday to Friday,8 AM *o 5 PM except University holidays), please phone 898-7187.

Af ter hours and on weekends, please phone our beeper at 215-960-8754. When you hear the tone,

enter your phone number; please include your area code.

If there is no response to your page, call the following individuals,in the order in which the names are presented, until contact is made:

Sunita Kurian 215 533-1030 Marc Felice 215-594-8723 Winnie Zhu 215-259 5815 Joseph Kane 215-626 8709 Lily Lodhi 609-424-8895 George MacDurmon 609-778-8132 Joseph McCue 609-468-0521 Mark Selikson 215 293-1365 If you have questions or comments, please contact Louise Chaney at 898-8550 during regislar office hours, Monday to Friday,8 AM to 5 PM.

924103 LC/d

..o; o

$NCLOSURE.1 Revised August 31,1990 UNIVERSITY OF PENNSYLVANIA RADIATION SAFETY USERS' GUIDE This Guide has been prepared as an. information manual for University personnel concerned with.the use of radioisotopes or other sources of ionizing radiation.

ONE COPY OF THIS GUIDE SHOULD llE READILY AVAILABLE IN EACH LICENSED LABORATORY.

P l

L_--__.---._.-_---_-_--_.__.__-__----._--____.------______-_-_.____--_.-_-__..---__-_-_-_.---_-_____--.--__-_------_----a

.o; o

TABLE OF CONTENTSL

- PAGE NO./

I.

AUTHORIZATION TO USE RADIOACTIVE MATERIALS 1

(LICENSING)

II.

ALARA-1 III.

TRAINING 1

IV.

ORDERING / RECEIVING RADIOACTIVE MATERIAL-2 V.

RAM INVENTORY

'3

-j VI.

GENERAL RADIATION SAFETY PRACTICES

.3 VII. LABORATORY MONITORING E4 VIII. PERSONNEL MONITORING PROGRAM 4~

IX.

POSTING ANDLABELLING

6 f

X-RADIOACTIVE WASTE DISPOS AL L7 IX.

RADIATION SAFETY INSPECTIONS

10 4

~ XII. PREGNANT PERSONNEL-

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I.,

AUTIIORIZATION TO USE RADIOACTIVE MATERIALS (LICENSING)

A.

Initial application and amendments 1.

Licenses to use radioactive materials (RAM), and amendments to existing-licenses, are granted by the Radiation Safety Committee (RSC). Application forms are avalable at the Radiation Safety Office (RSO).

2.

Faculty members who are princiaal investigators are those individuals typically _

approved for radioactive materia;5 licenses.

3.

The review and approval process for a license or amendment application typically takes 4 to 8 weeks.

B.

Annuallicense review 1.

The RSO will send annual license review forms to licensees requesting the following infonnation:

a.

Current RAM inventog b.

Cturent list of radiation workers c.

Current protocols involving the use of any licensed RAM '

d, Cur:em list of survey metera j

e.

Current list of sealed sources 2.

Completed fonus must be retumed to the RSO within two weeks.

1 II.

ALARA A.

He acronym ALARA; As Low As Reasonably Achievable,means that persons using sources ofionizing radiation should make every reasonable effort to keep expo::ures e individuals and releases of radioactive materials to umestricted areas as far below regulatory limits as is practicable. As a general rule, exposures and releases should be kept below 10% of the regulatoy limits.

B.

Licenseen together with lab' oratory personnel shall review their experimental.

protocols, work habits, and available safety equipment for adherence to the ALARA panaple.

C, ne RSO will rocify licensees of individuals receiving personnel doseneter exposures a

exceeding ALARA levels. Exposures will be investigated und reviewed by the RSC.

o III.

TRAINING A.

Persons working in labs where RAM or enerpzed equipment is used or stored are reqsed to aneed RSO training prior to beginmng work with the souren of radiation. -

d B.

A licensee must hold an annual ALARA training session and record the topics covered, the date, and names of attendees. An outline for this training shall include, but is not limited 10. the following:

1 4

e

9

.O g

t RAM ~ INVENTORY d l RAM stock vial Each laboratory must maimain a permanent record of indiv V.-

di receipts / dispositions which includes the followint,: ra onu A.

of receipt, transfers, and date of final disposal.

h hipment vial be It is recommended that a running tog of all withdrawals from B.

i d (the activity on maintained.

A quarterly record of current RAM stock vial j

h di nuclide).

C.

A sewer disposallog must be used to summarize RAM disp i

-l each sink designated for such disposal, s: Total H-3, total D.

I f ll The sewer disposallogs shallbe summarized quarterly as o o l

C-14, total for all other radionuclides.

E.

GENERAL RADIATION SAFETY PRACTICES handling radioactive ln Lab coats or other protective clothing shall VL l

A.

Disposable gloves shall be worn when handling RAM.

h pipette in areas where 1

I B.

Personnel shall not eat, drink, smoke, store food, or mout C.

RAM is used or stored.

d itoring shat! he.

Careful experimenta} planning, dry mas, shielding, dist

^

l' required for rmmmmng exposure.

D.

i RAM shall be used, stored, and transported in appropr s-RAM shall be secured against use or access by unauth E.

i ation tnonitoring, Smooth work surfaces, protective bench coverings, cont F.

pmper equipment, and segregated work areas shall be us i ers and disposed of' G.

Radioactive wnte shall be collected in. appropriate coma according to the RADIOACTIVEWASTE AND D uired in licensin'g-H.

Approved fume hoods ur glove boxer, shall be used a

[

conditions to control possible airborne contamination.

the POSTING u I.

L Facilities'and RAM containers must be labeled accord LABELJNG sectionof this guide.

J.

AM.

K. Hands shouH be thoroughly washed after working with sonnel within the '.ab',

A carrent copy of the "Useis Guide" mus. be available to l '.

- L.

The RSO must b-nonfied pmmptly in the event of:

L

. M.

personnelcontamination-1.

3

V(m.

g).

L B.

Personnel dosimeter prograrn personnel desimeters is paid by the licensee.

The ecst cf the Current cests can be obtained by centacting the RSO.

1.

devices wem by persens 2.

Descriptient Personnel dr.simeters areThese dcai=eters can censist of i-to measure thei tadiatien dose.

chambers, or integrating film, thermelu:ninescent crystals, pccket desimeters with settable alarms.

Who gets personnel desi=eters?

3.

All irdividuals, unless specified otherwise i a.

should wear both whole body and extremity dosimeters.

Activity Badianuclid; 5 mci I-125 & Cr 51 1 mci P-32 & Rb-86 500 pCi 1-131, Se 75, & Co-57 250 Ci Zn-65 50 Ci Fe-59, Co-60, Na-22, & Nb-95 For beta emitters exceeding 250 kev, Consult the RSO or other gamma or x-ray emitters required when working ' ociy are not (e.g.,

Personnel dosimeters with radionuclides which are low energy beta. emitters b,

H-3, C-14, & S-35).

It is the responsibility of the licensee to notify the RSO o Personnel dosimeters individuals requiring personnel dosimeters. issued c.

will be Worker Registration form is received-It is the responsibility of individuals receiving dosime to pick them up in the Radiation Safety Office.

d.

Monitoring periods: Workers will be assigned dosimet i

d' depending upon the expected radiation dose. New d 3

d dosimeters are on tte Wednesday before the last day of the month, and ol 8

picked up on the Wednesday after.

Obtaining a dosimeter: To get a dosimeter, bring a co 4.

Registation fann to the RSO.

5

9

,a i

X.-- RADIOACTIVE WASTE DISPOSAL l

The cost of radioactive waste disposalis paid by the licensee. C bi d by contacting-along with radioactive waste collection hours and locations can be o ta ne a

the RSO.

t Common waste types and their approved disposal methods are

(

toxic and -

material is not included in this list, or is a mixed hazardous waste; e.g.,

radioactive) other than scintination fluid, consult the RSO.

Dry Waste il A.

Definition Dry waste materials potentially contaminated with p

No free standing liquid or biological mar thi is pennissible in this was Non-commercial Disposal [This option is only for waste gene i

with gamma or hard (> 250 kev) beta emitters.]

1.

Survey the waste with a suitably sensitive meter (able 4

mR/hr at contact) in a low background area.

a.

Readings shall be made at a distance of 1 inch or less b.

I the material.

If no rending distinguishable from background on conta F

material is found, obliterate radioactive labels and dispose c.

radioactive waste.

If readings exceed background, dispose of waste comm d.

describedin the next section).

Commen:ialDisposal Place waste in a five gallon pail which is lined with a 2.

and bags are provided by the RSO)<

a.

Complete a waste transfer memo form for each pail of waste b.

Transfer waste' to thd RSO designated waste collec

'i :

c.

specified waste hours.

Animal Cr.rcasses/ Biological Material :

4 05 Place waste in transparent bags. (Keep _ waste.con B.

pCi/gm of 3H or 14Cin a separate bag.)

1.

Complete a waste transfer form for each bag of waste.

Transfer refrigerated (not frozen) carcasses to the RS 2.

conection a*ea during specified waste hours.

3.

T m

9

.o 3.

Shcrt-lived (T 1/2 $ 15 days), non-hazardocs waste for storage for decay 1.

Centralized storage (stcred by Radiatic Safery) a.

? lace waste (segregated into short-lived rad!cnuclides) in a-five gallen pall which is lined with a clear plastic bag (pail and bags are provided by the RSC).

b.

Cc=plete a waste transfer memo fe:= fer each pail of waste.

Transfer waste to.the RSO designated waste collection area c.

during specified waste hours.

d.

The following restricticns apply:

1)

Remove er oblitente all radicactive materials labels.

2)

No hazardous materials (i.e., lead, organic solvents) may be included.

3)

No concrete may be included -(small volumes of liquid are acceptable).

2.

Local storage.(stored by licensee)

Stored waste must be properly shielded. 32P must be stcred a.

behind plexiglass shielding with a minimum thickness of 3/8 inch.

b.

All radioactive materials labels must be removed or obliterated prior to disposal.

All waste must be stored for 2.10 half-lives, AND at -the time c.

of disposal radiation levels frem the unshielded waste j

container must be indiscemible from background when measured at the ' surface of _ the waste with a' G-M survey mete r.

j L

d.

A suitably sensitive survey meter must be available within the lab, and have been labeled with the reading from a

' dedicated check source by the Radiation Safety Office annually. This source must be mounted to the meter.

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