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Ã山ǿ¼é Radiation License

Applicant:

Ã山ǿ¼é
8600 University Boulevard
Evansville, IN 47712

Ìý

5. Radioactive Material

Byproduct, source, and/orÌýÌýÌýÌýÌýspecial nuclear material

Chemical and/or physical form

Maximum amount of material requested for license

A.ÌýÌýÌýÌýÌýHydrogen 3

A.ÌýÌýAny

A.ÌýÌý20 millicuries

B.ÌýÌýÌýÌýÌýCarbon 14

B.ÌýÌýAny

B.ÌýÌý15 millicuries

C.ÌýÌýÌýÌýÌýPhosphorus 32

C.ÌýÌýAny

C.ÌýÌý30 millicuries

D.ÌýÌýÌýÌýÌýPhosphorus 35

D.ÌýÌýAny

D.ÌýÌý30 millicuries

E.ÌýÌýÌýÌýÌýSulfur 35

E.ÌýÌýAny

E.ÌýÌý15 millicuries

F.ÌýÌýÌýÌýÌýIodine 125

F.ÌýÌýAny

F.ÌýÌý10 millicuries

G.ÌýÌýÌýÌýÌýCesium 137

G.ÌýÌýSealed Source

G.ÌýÌý5 millicuries

H.ÌýÌýÌýÌýÌýCobalt 60

H.ÌýÌýSealed Source

H.ÌýÌý5 millicuries

I.ÌýÌýÌýÌýÌýSr 90

I.ÌýÌýSealed Source

I.ÌýÌý5 millicuries

J.ÌýÌýÌýÌýÌýAmericium 241

J.ÌýÌýSealed Source

J.ÌýÌý1 millicurie

K.ÌýÌýÌýÌýÌýNickel 63

K.ÌýÌýSealed Foil Sources
(Varian Detector Model
NBC/NEN 004)

K.ÌýÌýNo single source to exceed 15 millicuriesÌý

Comments:

Items A through F will be contained in bound form within the confines of proteins, nucleic acids, nucleotides and amino acids.Ìý

All sealed sources will be obtained from Amersham, Isotope Products Laboratory, or other licensedÌývendor.

6.ÌýÌýPurpose for which LicensedÌýMaterial will be used

Items A through F:ÌýÌýLaboratory research and teaching and training of biology students
Items G through J:ÌýÌýLaboratory research and radiation detector studies. Teaching and training of physics students.

7.ÌýÌýIndividuals responsible for radiation safety program

ÌýRSO:ÌýÌýDr Kent W. Scheller
Assistant Professor of Physics
Ph.D. 1994, University of Notre Dame
Nuclear Astrophysics
Currently RSO for Shamrock Technologies, Henderson, KY/Newark, NJ

Expertise:ÌýÌýα, β, γ detection in accelerator based nuclear reactions

Ìý

Ìý7.ÌýÌýIndividuals responsible for radiation safety program

AU:Ìý

Individual

Isotope(s)

Expertise

Kent W. Scheller, Ph.D.
Asst. Professor of Physics

ALL

See above

Marlene Shaw, Ph.D.
Professor of Biology

P32, P33, S35, I125

DNA/RNA labeling and sequencing.Ìý

Mark Krahling, Ph.D
Asst. Professor of Chemistry

Ni63

Gas Chromatography

Jeannie Collins, Ph.D.
Assoc. Professor of Biology

H3, P32, P33, S35

DNA replication and sequencing, Protein analysis

Gary TenEyck, Ph.D.
Asst. Professor of Biology

H3, S35, I125

in situÌýhybridization, autoradiography

Eric McCloud, Ph.D.
Asst. Professor of Biology

H3, C14, P32, S35, I125

DNA sequencing, nucleic acid probe construction, metabolic tracer studies

Resumes of all of the above individuals are on file.

8.ÌýÌýTraining for individuals

The RSO will be responsible for the approval of all new authorized users after a careful evaluation of their past raining and experience.ÌýÌýIf it is determined that additional training of the potential user is deemed necessary, such training will be completed before use of radioactive material will commence.Ìý

Training for those individuals responsible for the use of licensed material will take place once every two years, or individually with the addition of new AU’s.ÌýÌýTraining will be conducted in a classroom format and will include, but is not limited to:

  • α, β, γ Radiation and Sources
  • Naturally Occurring Radiation
  • Dose StandardsÌý
  • Permissible Limits
  • Biological Effects
  • Pre-Natal Dose Limit
  • Genetic Effects
  • Penetrating Power of RadiationÌý
  • Radiation Measurement
  • Waste Disposal
  • Radiation Half-lifeÌý
  • Personal Protection
  • Transportation of Sources
  • Emergency Procedures
  • Receiving Procedures

All training will be concluded with a short quiz to assess the retention of information necessary to be an authorized user.ÌýÌýAny deficiencies will be addressed with additional training until adequate proficiency is demonstrated by potential user.ÌýÌýAll training will be conducted by the RSO.

Any students that will be working in the presence of radioactive sources must first review a radiation safety video outlining safe handling procedures of radioactive materials.Ìý

9.ÌýÌýFacilities and Equipment

All radioactive sources will be stored in designated areas in the Science Center on the campus of the Ã山ǿ¼é. Isotopes listed above in Section 5 will be stored and used according to the following:

Items A through F:Ìý

Isotopes will be utilized by the Biology Department on the first floor of theÌýÌýScience Center (Diagram 1).ÌýÌýIsotopes will be safely stored in rooms mentioned below.ÌýÌýAll isotopes (A through F) may be transported in unbreakable containers by an AU for use in student laboratories pictured in Diagram 1.ÌýÌýAny such teaching laboratory will be posted as a potential area of radioactivity.ÌýÌýNo laboratory will be left by an AU, after use of a transported isotope, with an ambient radiation activity level above those specified by Appendix Q, NUREG-1556, Vol. 7.Ìý

ÌýSC 92:ÌýÌýDiagram 2 illustrates a restricted research lab in which aqueous forms of isotopesÌý3H,Ìý14C,Ìý32P,Ìý35S, andÌý125I may be stored and used for research and teaching purposes.ÌýÌýSC92 consists of a filtered exhaust hood and a refrigerator in which materials requiring such will be stored.ÌýÌýThe sink in SC92 will be designated for the appropriate disposal of aqueous waste.ÌýÌýBulk aqueousÌý3H waste will be stored in RSO-approved polypropylene/polystyrene containers.ÌýÌýA solid waste disposal can will be maintained in SC92 for disposal by a professional service authorized by NRC license to handle radioactive waste.ÌýÌýSC 92 is 20’ x 28’ in area.

SC 59A/91/91A/91C:ÌýÌýDiagram 3 illustrates a research area in which aqueous forms of isotopesÌý3H,Ìý32P,Ìý33P,Ìý35S, andÌý125I may be stored and used for research and teaching purposes.ÌýÌýSC 59A has a filtered, lockable exhaust hood for materials requiring room temperature storage.ÌýÌýA dedicated, lockable refrigerator located in 91C will be designated for storage of isotope materials requiring such.ÌýÌýThe lockable freezer located in 91A will be designated for isotopes requiring freezer storage.ÌýÌýThe sink in 59A will be designated for the appropriate disposal of aqueous waste.ÌýÌýBulk aqueousÌý3H waste will be stored in RSO-approved polypropylene/polystyrene containers.ÌýÌýA solid waste disposal can will be maintained in both rooms for disposal by a professional service authorized by NRC license to handle radioactive waste.ÌýÌýRoom 59A is 25’6â€� x 10’ in area.ÌýÌýRoom 91 is 24’ x 10’ in area.ÌýÌýRoom 91A is 24’ x 10’ in area.ÌýÌýRoom 91C is 10’ x 10’ in area.

SC 195:ÌýÌýOn the second floor (Diagram 4) is SC 195 which is a teaching and research laboratory in which the aqueous forms of isotopesÌý3H,Ìý32P,Ìý33P, andÌý35S may be stored for research and teaching purposes.ÌýÌýSC 195 (Diagram 5) has a filtered, lockable exhaust hood for materials requiring room temperature storage.ÌýÌýA lockable refrigerator and lockable freezer are available for storage of materials requiring lower temperatures.ÌýÌýAn additional, lockable freezer capable of –800F will be utilized for long term storage of refrigerated materials.ÌýÌýThe sink in the hood will be designated for the appropriate disposal of aqueous waste.ÌýÌýBulk aqueousÌý3H waste will be stored in RSO-approved polypropylene/polystyrene containers.ÌýÌýA solid waste disposal can will be maintained in both rooms for disposal by a professional service authorized by NRC license to handle radioactive waste.ÌýÌýSC 195 is 38’ x 28’ in area.Ìý

Items G through I:

These items will be utilized by the Physics department for instruction and research in the areas of radiation detector development.ÌýÌýSources will be stored in the below-mentioned area and occasionally transported by an AU to the adjacent Physics Laboratory SC256 for instructional purposes.ÌýÌýMajority of use will be for detector development in which simple counting procedures will be followed.Ìý

SC P256:ÌýÌýOn the third floor (Diagram 6) is a restricted Physics Laboratory Prep Room.ÌýÌýIn room SC P256 (Diagram 7) will be stored the sealed sourcesÌý137Cs,Ìý60Co, andÌý90Sr.ÌýÌýThe sources will be housed in a lead brick house on the back counter of the room.ÌýÌýVentilation for this room consists of a closed system involving an air conditioning unit with filters.ÌýÌýSC P256 is 15’ x 28’ in area.

10.ÌýÌýRadiation Safety Program

Radiation Monitoring Instruments

Required surveys will be conducted with a Victoreen Model 290 Geiger Monitor, whose certificate of calibration shall remain attached.ÌýÌýAll calibrations will be conducted by the manufacturer and will be done at intervals specified by the manufacturer on the calibration certificate.ÌýÌýWe will use instruments that meet the radiation monitoring instrument specifications published in Appendix M to final NUREG-1556, Vol. 7, ‘Program-Specific Guidance Ã山ǿ¼é Academic, Research and Development, and Other Licenses of Limited Scope,’ dated May 1998.ÌýÌýWe reserve the right to upgrade our survey instruments as necessary.Ìý

10.ÌýÌýRadiation Safety Program

Material Receipt and Accountability
All purchases of radioactive material will be initiated by an AU.ÌýÌýAny purchase request will be forwarded to the RSO, who will assure license compliance.ÌýÌýUpon determination of compliance, the RSO will approve/disapprove the request.

All radioactive material purchased is to be delivered to the department office of the AU who initiated the purchase.ÌýÌýThe AU is required to forward the pertinent information from the shipment to the RSO.ÌýÌýPhysical receipt of the material shall take place following the guidelines outlined in Appendix A.ÌýÌýUpon physical receipt of material, a Radioactive Shipment Receipt/Usage Report must be completed and forwarded to the RSO.

Authorized user is responsible to continually document the disposition of this material until it is completely utilized.ÌýÌýThe Usage portion of this form shall be completed during the use of material.ÌýÌýOnce material is consumed in full, the Usage portion shall be completed indicating as such and a signed copy shall be forwarded to RSO.

Physical inventories will be conducted in April and October, to account for all sources and received and possessed under the license.ÌýÌýInventory reports (Appendix E/F) shall be completed by each AU possessing licensed material and return form to RSO.

10.ÌýÌýRadiation Safety Program

Occupational Dose
We have done a prospective evaluation and determined that unmonitored individuals are not likely to receive, in one year, a radiation dose in excess of 10 percent of the allowable limits in 10 CFR Part 20.Ìý

Appendices G and H illustrate the isotopes in question and a table of calculations to demonstrate the dose rates expected from each item and the time required to reach a dose limit of 10% of the yearly allowable dose.Ìý

Appendix G contains information for the beta-emitters.ÌýÌýThe isotopes utilized in the Biology department,Ìý3H, C14,Ìý32P,Ìý33P, andÌý35S, will be handled in container quantities of 250μCuries (0.250 mCuries) at a time.ÌýÌýAny quantities in excess of this on hand would be in storage, not contributing to the exposure of individuals present.ÌýÌýA handling distance of 50 cm was assumed for calculations.ÌýÌýThe majority of time in the presence of these isotopes will be spent at distances which are much greater.ÌýÌýReferring to the Limit Time column of Appendix G, only one of the Biology isotopes,Ìý32P,ÌýÌýhas a Limit Time that could possibly be breached in a year.ÌýÌýInterviews of the potential users yielded the following use parameters.ÌýÌýAt a maximum, approximately 100 radioactive samples would be prepared, taking 10 minutes each (very conservative), in a year’s time by any one user usingÌý32P.ÌýÌýThe 10 minute preparation time is the only duration in which the distance approaches 50 cm.ÌýÌýWith this scenario, only 1000 minutes, or 16.7 hours, of handling exposure is accumulated by a user.ÌýÌýEven with the conservative estimates of time and use of this isotope, exposure time is comfortably below the 25.8 hours that would be necessary to reach the 10% level.ÌýÌýIn fact, if 16.7 hours were spent in front all of the isotopes at full activity (250 μCuries), the absorbed dose would be under the 10% threshold for monitoring.

The beta-emitter to be used in the Physics Department,Ìý90Sr, is a sealed source of 5 mCi, so no partial activity could be assumed.ÌýÌýAs the calculation shows, 355 hours of exposure at a distance of 1 m would be required to reach the 10% level.ÌýÌýThis value surpasses by an order of magnitude the time exposure expected.

Of the gamma-emitters, Appendix H, only theÌý60Co source has a potential Limit Time that could be breached in a year’s time.ÌýÌýSince the source will be used in counting experiments which are not individually attended to by the user, except for initial set-up, exposure time will be far less than the 36 hours required to accumulate 10% of the dose limit.ÌýÌýHandling ofÌý125I, will take place in container quantities of 250 μCuries, well below the threshold of 1 mCurie specified in Appendix P, NUREG-1556, Vol. 7.

Given the above discussion, it is concluded that no user will be exposed at a level of 10% of the yearly allowable dose, therefore no external monitoring shall be required.

10.ÌýÌýRadiation Safety Program

Safe Use of Radionuclides and Emergency Procedures
Operating Procedures for the safe use of isotopes is outlined in Appendix B.ÌýÌýThese operating procedures will be posted in all rooms utilizing radioactive materials and distributed to all users of radioactive material.

Emergency Procedures are outlined in Appendix C.

Procedures may be revised if:

  • The changes are reviewed and approved by licensee management and the RSO.
  • Licensee staff is trained in the revised procedures before they are implemented.
  • The changes are consistent with the procedures submitted with the license application.
  • The changes do not degrade the effectiveness of the program.

10.ÌýÌýRadiation Safety Program

Survey
We will survey our facility and maintain contamination levels in accordance with the survey frequencies and contamination levels published in Appendix Q to final NUREG-1556, Vol. 7, ‘Program-Specific Guidance Ã山ǿ¼é Academic, Research and Development, and Other Licenses of Limited Scope,’ dated May 1998.ÌýÌýLeak tests will be performed at the intervals approved by NRC or an Agreement State and specified in the SSD Registration Certificate.ÌýLeak tests will be performed by an organization authorized by NRC or an Agreement State to provide leak testing services to other licensees or using a leak test kit supplied by an organization authorized by NRC or an Agreement State to provide leak test kits to other licensees and according to the sealed source or plated foil manufacturer’s (distributor’s) and kit supplier’s instructions.

11.ÌýÌýWaste Management

We will use the model waste procedures published in Appendix T to final NUREG-1556, Vol. 7, ‘Program-Specific Guidance Ã山ǿ¼é Academic, Research and Development, and Other Licenses of Limited Scope,’ dated May 1998.

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