Applicant:
University of Southern Indiana
8600 University Boulevard
Evansville, IN 47712
5. Radioactive Material
|
Byproduct, source, and/or special nuclear material |
Chemical and/or physical form |
Maximum amount of material requested for license |
|
A. Hydrogen 3 |
A. Any |
A. 20 millicuries |
|
B. Carbon 14 |
B. Any |
B. 15 millicuries |
|
C. Phosphorus 32 |
C. Any |
C. 30 millicuries |
|
D. Phosphorus 35 |
D. Any |
D. 30 millicuries |
|
E. Sulfur 35 |
E. Any |
E. 15 millicuries |
|
F. Iodine 125 |
F. Any |
F. 10 millicuries |
|
G. Cesium 137 |
G. Sealed Source |
G. 5 millicuries |
|
H. Cobalt 60 |
H. Sealed Source |
H. 5 millicuries |
|
I. Sr 90 |
I. Sealed Source |
I. 5 millicuries |
|
J. Americium 241 |
J. Sealed Source |
J. 1 millicurie |
|
K. Nickel 63 |
K. Sealed
Foil Sources |
K. No single source to exceed 15 millicuries |
Comments:
Items A through F will be contained in bound form within the confines of
proteins, nucleic acids,
nucleotides and amino acids.
All sealed sources will be obtained from Amersham, Isotope Producst Laboratory, or other licensced vendor.
6. Purpose for which Licenced Material will be used
Items A through F: Laboratory
research and teaching and training of biology students
Items G through J: Laboratory
research and radiation detector studies. Teaching
and training
of phyics students.
7. Individuals responsible for radiation safety program
RSO: Dr Kent W. Scheller
Assistant Professor of Phyics
Ph.D. 1994, University of Notre Dame
Nuclear Astrophysics
Currently RSO for Shamrock Technologies, Henderson, KY/Newark, NJ
Expertise: α, β, γ detection in accelerator based nuclear reactions
7. Individuals responsible for radiation safety program
AU:
|
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. |
|
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 situ hybridization, 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. Training 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. If 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.
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. Training will be conducted in a classroom format and will include, but is not limited to:
α, β, γ Radiation and Sources
Naturally Occuring Radiation
Dose Standards
Permissible
Limits
Biological Effects
Pre-Natal Dose Limits
Genetic Effects
Penetrating Power of Radiation
Radiation
Measurement
Waste Disposal
Radiation Halflife
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. Any deficiencies will be addressed with additional training until adequate proficiency is demonstrated by potential user. All 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.
9. Facilities and Equipment
All radioactive sources will be stored in designated areas in the Science Center on the campus of the University of Southern Indiana. Isotopes listed above in Section 5 will be stored and used according to the following:
Items A through F:
Isotopes will be utilized by the Biology Department on the first floor of the Science Center (Diagram 1). Isotopes will be safely stored in rooms mentioned below. All isotopes (A through F) may be transported in unbreakable containers by an AU for use in student laboratories pictured in Diagram 1. Any such teaching laboratory will be posted as a potential area of radioactivity. No 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.
SC 92: Diagram 2 illustrates a restricted research lab in which aqueous forms of isotopes 3H, 14C, 32P, 35S, and 125I may be stored and used for research and teaching purposes. SC92 consists of a filtered exhaust hood and a refrigerator in which materials requiring such will be stored. The sink in SC92 will be designated for the appropriate disposal of aqueous waste. Bulk aqueous 3H waste will be stored in RSO-approved polypropylene/polystyrene containers. A solid waste disposal can will be maintained in SC92 for disposal by a professional service authorized by NRC license to handle radioactive waste. SC 92 is 20’ x 28’ in area.
SC
59A/91/91A/91C: Diagram 3
illustrates a research area in which aqueous forms of isotopes 3H, 32P,
33P, 35S, and 125I may be stored and used for
research and teaching purposes. SC
59A has a filtered, lockable exhaust hood for materials requiring room
temperature storage. A dedicated,
lockable refrigerator located in 91C will be designated for storage of isotope
materials requiring such. The
lockable freezer located in 91A will be designated for isotopes requiring
freezer storage. The sink in 59A will be designated for the appropriate
disposal of aqueous waste. Bulk
aqueous 3H waste will be stored in RSO-approved
polypropylene/polystyrene containers. A
solid waste disposal can will be maintained in both rooms for disposal by a
professional service authorized by NRC license to handle radioactive waste.
Room 59A is 25’6” x 10’ in area.
Room 91 is 24’ x 10’ in area. Room
91A is 24’ x 10’ in area. Room
91C is 10’ x 10’ in area.
SC 195:
On the second floor (Diagram 4) is SC 195 which is a teaching and
research laboratory in which the aqueous forms of isotopes 3H, 32P,
33P, and 35S may be stored for research and teaching purposes.
SC 195 (Diagram 5) has a filtered, lockable exhaust hood for materials
requiring room temperature storage. A
lockable refrigerator and lockable freezer are available for storage of
materials requiring lower temperatures. An
additional, lockable freezer capable of –800F will be utilized for
long term storage of refrigerated materials.
The sink in the hood will be designated for the appropriate disposal of
aqueous waste. Bulk aqueous 3H
waste will be stored in RSO-approved polypropylene/polystyrene containers.
A solid waste disposal can will be maintained in both rooms for disposal
by a professional service authorized by NRC license to handle radioactive waste.
SC 195 is 38’ x 28’ in area.
Items G through I:
These items will be utilized by the Physics department for instruction and
research in the areas of radiation detector development.
Sources will be stored in the below-mentioned area and occasionally
transported by an AU to the adjacent Physics Laboratory SC256 for instructional
purposes. Majority of use will be
for detector development in which simple counting procedures will be followed.
SC P256: On the third floor (Diagram 6) is a restricted Physics
Laboratory Prep Room. In room SC
P256 (Diagram 7) will be stored the sealed sources 137Cs, 60Co,
and 90Sr. The sources
will be housed in a lead brick house on the back counter of the room.
Ventilation for this room consists of a closed system involving an air
conditioning unit with filters. SC
P256 is 15’ x 28’ in area.
10. Radiation Safety Program
Radiation Monitoring Instruments
Required surveys will be conducted with a Victoreen Model 290 Geiger Monitor, whose certificate of calibration shall remain attached. All calibrations will be conducted by the manufacturer and will be done at intervals specified by the manufacturer on the calibration certificate. We will use instruments that meet the radiation monitoring instrument specifications published in Appendix M to final NUREG-1556, Vol. 7, ‘Program-Specific Guidance About Academic, Research and Development, and Other Licenses of Limited Scope,’ dated May 1998. We reserve the right to upgrade our survey instruments as necessary.
10. Radiation Safety Program
Material
Receipt and Accountability
All
purchases of radioactive material will be initiated by an AU. Any purchase request will be forwarded to the RSO, who will
assure license
compliance.
Upon 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. The AU is required to forward the pertinent information from the shipment to the RSO. Physical receipt of the material shall take place following the guidelines outlined in Appendix A. Upon 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. The Usage portion of this form shall be completed during the use of material. Once 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.
Inventory reports (Appendix E/F) shall be completed by each AU possessing
licensed material and return form to RSO.
10. Radiation 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.
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.
Appendix G contains information for the beta-emitters. The isotopes utilized in the Biology department, 3H, C14, 32P, 33P, and 35S, will be handled in container quantities of 250μCuries (0.250 mCuries) at a time. Any quantities in excess of this on hand would be in storage, not contributing to the exposure of individuals present. A handling distance of 50 cm was assumed for calculations. The majority of time in the presence of these isotopes will be spent at distances which are much greater. Referring to the Limit Time column of Appendix G, only one of the Biology isotopes, 32P, has a Limit Time that could possibly be breached in a year. Interviews of the potential users yielded the following use parameters. At a maximum, approximately 100 radioactive samples would be prepared, taking 10 minutes each (very conservative), in a year’s time by any one user using 32P. The 10 minute preparation time is the only duration in which the distance approaches 50 cm. With this scenario, only 1000 minutes, or 16.7 hours, of handling exposure is accumulated by a user. Even 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. In 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, 90Sr, is a sealed source of 5 mCi, so no partial activity could be assumed. As the calculation shows, 355 hours of exposure at a distance of 1 m would be required to reach the 10% level. This value surpasses by an order of magnitude the time exposure expected.
Of the gamma-emitters, Appendix H, only the 60Co source has a potential Limit Time that could be breached in a year’s time. Since 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. Handling of 125I, 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. Radiation Safety Program
Safe
Use of Radionuclides and Emergency Procedures
Operating Procedures for the safe use of isotopes is outlined in
Appendix B. These 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. Radiation 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 About Academic, Research and Development, and Other
Licenses of Limited Scope,’ dated May 1998.
Leak tests will be performed at the intervals approved by NRC or an
Agreement State and specified in the SSD Registration Certificate.
Leak 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. Waste Management
We
will use the model waste procedures published in Appendix T to final NUREG-1556,
Vol. 7, ‘Program-Specific Guidance About Academic, Research and Development,
and Other Licenses of Limited Scope,’ dated May 1998.
Appendix
A
Procedures
for Safely Opening Packages
Containing Radioactive Material
1. Packages will be monitored for surface contamination and external radiation levels within 3 hours after receipt if received during working hours or within 18 hours if received after working hours. All shipments of liquids greater than exempt quantities will be tested for leakage. Action limits for package monitoring will be as follows:
Radioactive Material Packages Label Criteria
Label |
At any point on accessible
|
At three feet from external surface of package
|
|
“Radioactive-White I” |
0.5 mR/hr |
0 |
|
“Radioactive-Yellow II” |
50 mR/hr |
1.0 mR/hr |
|
“Radioactive-Yellow III” |
200 mR/hr |
10 mR/hr |
2.
For all packages, the following procedures for opening packages will be
carried out:
a.
Put on gloves to prevent hand contamination
b.
Visually inspect package for any sign of damage (e.g. wetness, crushed).
If damage is noted, stop procedure and notify RSO.
c.
Open the package with the following precautionary steps:
1) Open the outer package (following manufacturer’s directions, if supplied) and remove packing slip.
2) Open inner package and verify that contents agree with those on packing slip. Compare requisition, packing slip and label on bottle.
3) Check integrity of final source container (i.e. inspect for breakage of seals or vials, loss of liquid and discoloration of packaging material).
4) Check also that shipment does not exceed possession limits.
d. Monitor the packing material and packages for contamination before discarding.
1) If contaminated, treat as radioactive waste.
2) If not contaminated, obliterate radiation labels before discarding in regular trash.
3.
Maintain records of the results of checking each package, using
“Radioactive Shipment Receipt/Usage Report” (See next page).
1. ISOTOPE__________ ACTIVITY__________(mCi, μCi) Volume________(L, mL)
2. P.O. No.______________________ Survey Date_________________ Time_________
Surveyor___________________________ Signature____________________________
3. Condition of Package
Comment_______________________________________________________________
4. Radiation Units of Label ______________________________Units (mR/hr)
Label: White I______ Yellow II______ Yellow III______
5. Measured Radiation Levels
a. Package Surface _____________mR/hr
b. Three feet from surface ____________mR/hr
6. Do Packing Slip and Contents Agree?
a. Radionuclide _____yes _____no, Difference_____________________
b. Amount _____yes _____no, Difference_____________________
c. Chemical Form _____yes _____no, Difference_____________________
7. IF NRC/CARRIER NOTIFICATION REQUIRED, GIVE TIME, DATE AND PERSONS NOTIFIED.
MATERIAL USAGE
|
|
|
Disposal Method/Place |
||||
|
User |
Date |
Quantity |
Quantity |
Experiment |
Solid |
Liquid |
APPENDIX
B
Operating Procedures
for the
Safe Use of Radioactive Isotopes
1)
All use of radioisotope material shall be conducted under the supervision
of a faculty member certified as an Authorized User (AU).
2) The AU shall limit the quantity of radioactive material used by students under his supervision so as not to exceed the maximum dose allowed by regulation.
3) Adequate personal protection equipment must be worn or used by all individuals using radioactive material. This shall include, but is not limited to, rubber gloves and a laboratory coat.
4) Active participation in laboratory exercises during which radioactive isotopes are utilized by students that are known to be pregnant is strictly prohibited.
5) Eating, drinking or smoking in the laboratory is not permitted.
6) When liquid sources are used, the worker will conduct a body scan and a survey of the work area when the work is completed. Pipetting, or the performance of any similar operation, will be done by remote pipetting. If contamination is found, the radiation safety officer will be notified, and the contained area will be cleaned before the worker leaves the radiation laboratory. If spillage occurs, the radiation safety officer will supervise the decontamination of the area. Rubber gloves and lab coats will be worn, the spillage will be blotted up in an absorbing material, the area will be washed with soap and water and the contaminated materials will be stored in designated containers. Disposal will be in accordance with regulations governing the disposal of ionizing radiation.
7) If, in the course of work, personal contamination is suspected, a survey with a suitable instrument will be made immediately. This will be followed by the required cleansing and a further survey.
8) No person shall work with liquid radioactive materials if he has any breaks in the skin without first covering the break with some form of protective equipment All such breaks shall be reported to the instructor in charge before work begins.
9) Active liquid wastes shall be poured into labeled containers or into approved “hot” sinks in concentrations conforming to state guidelines. They shall never be poured into a standard drain.
10) Active solid wastes and contaminated materials should be placed in trash cans labeled “contaminated” or in designated containers.
11) Active materials and contaminated materials are to be retained within the radioisotope laboratory and at specific points within the laboratory.
12) All wounds, spills and other emergencies shall be reported to an approved user immediately.
13) Before leaving the laboratory, all written records of isotope usage, clean-up, surveys and emergencies (if any) must be completed by an Authorized User.
14)
No ancillary personnel will be allowed in a radiation area without direct
supervision.
APPENDIX C
Emergency Procedures
In emergency or accident situations involving radioactive materials, the following steps should be taken:
1) RESTRICT ACCESS: Persons in the immediate area not contaminated in the incident should be asked to leave the area. Establish a restricted area boundary, limiting access to the area to authorized personnel only.
2) MAINTAIN SURVEILLANCE: The restricted area must be kept under constant, direct supervision by an Authorized User (AU) or the Radiation Safety Officer (RSO) until area is deemed safe for occupancy.
3) NOTIFY: The Authorized User directly supervising the use of material involved in the accident should be notified immediately. In the case of spills, assessment of the accident should be made to determine if accident is minor or major and the proper procedures for which should be followed.
Minor Spills of Liquids and Solids
--Notify persons in the area that a spill has occurred.
--Prevent the spread of contamination by covering the spill with absorbent paper. (Paper should be dampened if solids are spilled).
--Clean up the spill, wearing disposable gloves and using absorbent paper.
--Carefully fold the absorbent paper with the clean side out and place in a plastic bag for transfer to a radioactive waste container. Put contaminated gloves and any other contaminated disposable material in the bag.
--Survey the area with an appropriate low-range radiation detector survey meter or other appropriate technique. Check the area around the spill for contamination. Also check hands, clothing and shoes for contamination.
--Report the incident to the RSO promptly.
--Allow no one to return to work in the area unless approved by the RSO.
--Cooperate with the RSO and AU (e.g., investigation of root cause, provision of requested bioassay samples).
--Follow the instructions of the RSO/AU (e.g., decontamination techniques, surveys, provision of bioassay samples, requested documentation).
Major Spills of Liquids and Solids
--Clear the area. If appropriate, survey all persons not involved in the spill and vacate the room.
--Prevent the spread of contamination by covering the spill with absorbent paper (paper should be dampened if solids are spilled), but do not attempt to clean it up. To prevent the spread of contamination, limit the movement of all individuals who may be contaminated.
--Shield the source only if it can be done without further contamination or significant increase in radiation exposure.
--Close the room and lock or otherwise secure the area to prevent entry. Post the room with a sign to warn anyone trying to enter that a spill of radioactive material has occurred.
--Notify the RSO immediately.
--Survey all personnel who could possibly have been contaminated. Decontaminate personnel by removing contaminated clothing and flushing contaminated skin with lukewarm water and then washing with a mild soap.
--Allow no one to return to work in the area unless approved by the RSO.
--Cooperate with the RSO and AU (e.g., investigation of root cause, provision of requested bioassay samples).
--Follow the instructions of the RSO/AU (e.g., decontamination techniques, surveys, provision of bioassay samples, requested documentation).
Note: Do not handle unattached or unshielded sources of radioactive material. Decontamination and recovery operations should only be attempted by properly trained individuals, under the direct supervision of the Radiation Safety Officer and using proper handling tools.
Minor Fires
--Immediately attempt to put out the fire by approved methods(i.e., fire extinguishers) if other fire hazards or radiation hazards are not present.
--Notify all persons present to vacate the area and have one individual immediately call the RSO and fire department (as instructed by the RSO).
--Once the fire is out, isolate the area to prevent the spread of possible contamination.
--Survey all persons involved in combating the fire for possible contamination.
--Decontaminate personnel by removing contaminated clothing and flushing contaminated skin with lukewarm water, then washing with a mild soap.
--In consultation with the RSO, determine a plan of decontamination and the types of protective devices and survey equipment that will be necessary to decontaminate the area.
--Allow no one to return to work in the area unless approved by the RSO.
--Cooperate with RSO/RSO staff (e.g., investigation of root cause, provision of requested bioassay samples).
--Follow the instructions of the RSO/RSO staff (e.g., decontamination techniques, surveys, provision of bioassay samples, requested documentation.).
Fires, Explosions, or Major Emergencies
--Notify all persons in the area to leave immediately.
--Notify the fire department.
--Notify the RSO and other facility safety personnel
--Upon arrival of firefighters, inform them where radioactive materials are stored or where radioisotopes were being used; inform them of the present location of the licensed material and the best possible entrance route to the radiation area, as well as any precautions to avoid exposure or risk of creating radioactive contamination by use of high pressure water, etc.
--Cooperate with RSO/RSO staff (e.g., investigation of root cause, provision of requested bioassay samples).
--Allow no one to return to work in the area unless approved by the RSO.
--Follow the instructions of the RSO/RSO staff (e.g., decontamination techniques, surveys, provision of bioassay samples, requested documentation.).
APPENDIX
D
Student Training Certification
and
Disposition to Safely Handle Radioactive Material
Name:______________________________
Age:____ Gender:
__M __F
Address:____________________________________________________
Phone:___________
Class for which certification is required:_______________________Semester/Year_______
Isotopes to be used:_________________________________
Instructor:_____________________________________
By signing below I affirm that I have received training on the safe handling and use of radioactive isotopes. I understand that my participation in exercises utilizing radioactive material requires the highest levels of safety and that any breach of safe operating procedures on my part will result in my dismissal from said exercises. I affirm that I am not pregnant at this time and that if this disposition changes I am obliged to inform my instructor before further participation in exercises using radioactive materials.
Signature:_________________________________________________Date:_______________
APPENDIX
E
Semi-Annual Radioisotope Inventory
Authorized
User:____________________________________
I have the following isotopes on hand as of April 15th, ______
|
Licensed Material |
Volume(L, ml,...) |
Activity(uCi, mCi...) |
|
Hydrogen-3 |
||
|
Carbon-14 |
||
|
Phosphorus-32 |
||
|
Phosphorus-33 |
||
|
Sulfur-35 |
||
|
Iodine-125 |
||
|
Cesium-137 |
||
|
Cobalt-60 |
||
|
Strontium-90 |
Please
complete and return to the Radiation Safety Officer.
APPENDIX
F
Semi-Annual
Radioisotope Inventory
Authorized User:____________________________________
I have the following isotopes on hand as of October 15th, ______
|
Licen |