UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Protocol for Use of Radioactive Materials
1. AUTHORIZED USER
Name
Thomas Hartmann
Phone
2. PROJECT NAME
895-1934, Cell: (208) 346-0273
3. FACILITY
Glove-box based preparation of Tc-99 based powders
for subsequent Sintering or ASTM based leaching
experiments
Building
Lab
MSM
234/236
4. PROJECT DESCRIPTION
Glove-box based preparation of Tc-99 based powders for subsequent sintering (HUP) or ASTM-based leaching
experiments.
The maximum total activity will not exceed 3000 μCi for Tc-99 or 177 mg Tc-99 which translates to 0.75 ALI by
ingestion and 4.3 ALI for inhalation for Tc-99. The sample preparation will be performed in an atmosphere
controlled negative pressure glove box which is connected to a HEPA filtered exhaust stack. Therefore no airborne
contamination for laboratory MSM 234/236 is expected. Hereby the maximum activity of one individual powder
sample is less than 350 μCi corresponding to approximately 0.09 ALI for ingestion and 0.5 ALI by inhalation.
Contamination control/monitoring protocols developed for the radiochemistry laboratories will be used for this work.
Appropriate PPE will be used at all times.
1. Source material of 177 mg Tc-99 or less, mainly as solid Tc(IV)-based oxide powder will be introduced
to an atmosphere controlled glove box in MSM 234/236 together with other chemicals (ethanol, nonradioactive metal oxides, standards) using glass vials and secondary containment.
2. Samples will be placed on a tray (covered with disposable absorbent mat and moistened paper towel)
in the glove box.
3. Pre-grinding: For each sample about 10 to 30 mg Tc-99(IV)-based oxide powder, or mixtures of Tcbased and non-radioactive metal oxide powders will be transferred to an agate mortar, suspended
with few mL of ethanol and the mortar will be covered with Parafilm.
4. Grinding: The agate pestle will be introduced through an opening on the Parafilm and the sample
ground with slow movements with the aid of ethanol to a particle size of about 150-20 m.
5. Sieving: For subsequent leaching experiments particles with size fractions between 100 and 200
mesh (149 m – 74 m) will be separated using a sealed 4 inch sieve set and a vortex in the glove
box. The 100-200 mesh size fractions will be transferred to a glass vial and the weight will be
recorded.
6. Loading of digestion vessels: 20 mL or 50 mL digestion vessels will be loaded with Tc-99 based
powder in the glove box using a funnel over a on a tray (covered with disposable absorbent mat and
moistened paper towel).
7. Samples for HUP-based sintering: Metal oxide mixtures will be prepared an agate mortar, suspended
with few drops of ethanol and homogenized. The powder mixtures will be scooped into glass vials.
8. Decontamination: The outside of the digestion vessels or the scintillation vials will be cleaned using
ethanol-moistened Kimwipes. The residual powder in the sieve will be transferred to the mortar and
stored in glass vials. The sieves will be cleaned by moistened paper towels.
9. Survey of sample vials: Smears from the sample vials and the digestion vessels will be taken and
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
analyzed for /β contamination.
10. Sample discharge: The sample vials/digestion vessels will be discharged from the glove box. The
sample vials will be transferred to the hot uniaxial press (HUP) which is hosted in a separated glove
box. The digestion vessels will be transferred to the dry furnace (fume hood) for subsequent leaching
and corrosion experiments.
11. Survey of the work area: After the experiment is completed, the work area will be decontaminated if
necessary and complete end-of-day/experiment surveys using a handheld detector (α/β probe) and
swipe surveys will be performed.
5. AUTHORIZED RESEARCHERS
Name
NSHE1000028041
Name
DOE-trained RadWorker for 15+ years continuously, 22 years on handling of powder, 15 + years
handling radioactive powders and ceramics at KIT-INE (Germany), LANL, UNLV and INL
Employee/
Ariana J. Alaniz
Student ID E000133840/NSHE1000158964
Experience
2 years in fabrication of Tc waste forms, handling of mg quantities ofTcO2 powder
Name
Izua J. Alaniz
Experience
2 years of RMS chemical inventory experience, and an additional 1.5 years in biochemistry and
biology lab work.
Experience
I
Employee/
Student ID
Thomas Hartmann
Employee/
Student ID
NSHE 1000133887
insert rows as needed.
6. RADIOACTIVE MATERIALS USED: List each radionuclide used and the maximum amount used in any single procedure.
Indicate if there is a potential for airborne contamination. * Attachment 2, UNLV Risk Assessment and Control Guideline for
Unsealed-Radioactive Materials. Note: If nuclide not listed, refer to 10 CFR20, Appendix B, Table 1.
Nuclide
Maximum
Activity per
Use
(µCi)
ALIInhalation
(µCi)
Tc-99
3000
700
ALIIngestion
(µCi)
4000
ALI-Limiting
(µCi)
700
Potential
Airborne*
(Y/N)
Y
Risk
Level**
(1-4)
3
Physical
Form /
Chemical
Name
Solid as
oxide
7. RADIATION SAFETY MATERIALS & EQUIPMENT: Check all items available to workers handling radioactive material.
X Protective gloves
X Lab coat
X Safety glasses
Face shield
Shoe covers
Respirator
X
X
X
Warning signs/tags/tape
Absorbent paper
Trays
Secondary containers
Handling tongs
Shielding
8. ENGINEERING CONTROLS: Check all items that are required.
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X
X
X
Personal dosimeters
Survey meter
Swipe counter
Other (list):
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Fume hood - unfiltered
Fume hood –
filtered exhaust
X
Glove box – positive/negative pressur
condary containment
9. EVALUATION OF AIRBORNE RADIOACTIVE MATERIALS: Indicate how radioactive materials could become airborne.
Check all that apply.
Production or use of radioactive gas (e.g. methane, 14CO2)
Grinding, pulverizing and associated handling of dry dispersible unsealed radioactive material
Volatile compound (e.g. Na125I, 3H2O, labeled solvents, Na-Borohydride)
Aerosols (e.g. evaporation of liquids)
Use of powders and other finely divided solids
X
Other (list): Grinding, homogenization and associated handling of wet/suspended dispersible X
unsealed radioactive material
Other (list):
10. AIR MONITORING: Check all items that are required. [Routine air monitoring required if > 0.01 ALI of dry, dispersible material.
Continuous air monitoring required if >0.1 ALI of dry, dispersible material. Breathing Zone Air sampling (BZA) is required when
working with ≥ 1 ALI dry, dispersible materials (airborne)]. (Note: For limits, see Attachment 1. If nuclide not listed, refer to 10
CFR20, Appendix B, Table 1).
None
Routine
X CAM
X
BZA
11. BIOASSAY: Check all items that are required. [Baseline bioassay and quarterly bioassay required >5 ALI dispersible (airborne).
X Baseline
X
Quarterly
Special
Other
12. FACILITIES: List ALL rooms where ANY radioactive material will be used or stored. Briefly describe the use of each location.
Insert rows as needed.
Building
MSM
MSM
Room #
236
236
Use
Glove Box (manipulating mg amounts of TcO2 for subsequent experiment)
Desiccator central bench-top (storage of mg amounts TcO2)
13. RISK ASSESSMENT: Describe the expected radiation dose associated with this protocol. Describe the likelihood and
seriousness of unexpected, but realistic, problems or accidents. (Consultation is available from Radiation Safety.)
Normal Conditions
During normal conditions there is no realistic inhalation risk. Tc-99 samples are not volatile at room temperature.
The oxide powders will be prepared in an atmosphere controlled negative pressure glove box and discharged from
the box in scintillation vials or digestion vessels for subsequent experiments (e.g. HUP-based sintering, Tc-99
leaching). An annual uptake of 5,000 mrem radiation dose associated with this protocol is highly unlikely. The total
Tc-99 content of the solid samples will be less than 177 mg or 3000 μCi corresponding to an activity of
approximately 0.75 ALI by ingestion and 4.3 ALI for inhalation for Tc-99. The material is stored in glass vials and
secondary containment and the unsealed source material is handled in a glove box.
Off-Normal Conditions / Accident Scenarios
The likely accident scenario would be a potential powder spill of 10 to 30 mg TcO2 (6.9-20.6 mg Tc-99) during
sample preparation in the glove box. This worst case scenario would be associated with an estimate activity of 117
μCi to 350 μCi Tc-99 or 0.03-0.09 ALI for ingestion and 0.17-0.50 ALI for inhalation. For Tc-99 the NRC lists for
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
injection an ALI of 4000 μCi (236 mg Tc-99) and an ALI for inhalation of 700 μCi (41 mg Tc-99). Using the
inhalation ALI’s as binding values, an accidental inhalation of 10-30 mg TcO2 would be far lower than 1 ALI. This
worst case inhalation scenario is very unlikely due to engineering controls (atmosphere controlled glove box
connected to a HEPA filtered exhaust stack). In terms of contamination, the likely accident to happen would be a
powder spill of an entire sample. Sample masses are <30 mg TcO2 total. Assuming all of the material actually
escaped the mortar, this would correspond to an activity of <350 μCi for Tc-99. To mitigate the potential for powder
spills during sample preparation a pre-moistened paper towel cloth will be used on top of the absorbed pads and
the glove box bottom, the back wall, and the side-walls will be covered with sticky mats.
There is no potential for airborne/inhalation exposure in the room MSM 234/236 from the samples under normal
conditions.
14. CONTROL MEASURES: Describe the procedures and equipment used to limit external dose and/or contamination.
All of the unsealed source work will be performed in a glove box of the radioactive materials laboratories. Standard
contamination controls will be used, which include smear surveys at the end of the experiment (transfer), personnel
monitoring (frisker, portal monitor), and hand-held detectors. The laboratory is also surveyed weekly, in addition to
the end of experiment testing.
15. MONITORING: Describe the procedures and equipment used to assess external dose and/or contamination.
Contamination control/monitoring protocols developed for the radiochemistry laboratories will be used for this work.
Handheld survey equipment (A/B probes, GM pancake). Smear Surveys (A/B Scintillator or gas proportional
counter).
16. RADIOACTIVE WASTE DISPOSAL: Describe the radioactive waste that will be produced and how it will be managed.
Potentially contaminated PPE (gloves, etc.) and associated materials (disposable pads, paper towels, Kimwipes)
will be generated from the transfer, loading, and handling of materials in this experiment. This waste material will
also be discharged from the box and disposed with other wastes from the radiochemistry laboratory
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
17. EMERGENCY PROCEDURES: Describe or reference.
For a powder spill during the sample preparation, the spilled powder will be scooped up if easily achievable using
paper strips and transferred into a glass vial in a secondary containment. Remaining loose powder will be fixed and
removed using sticky tape. Absorbent material will be used to absorb any residual radioactive material. A premoistened cloth will be used as a protection layer on top of the absorption pads and also to decontaminate the area.
Smear surveys will be taken from the antechamber and the surroundings to check for residual contamination. The
user will be notified of the incident. For any spills involving more than 20 mg Tc-99 the RSO will also be notified
18. RSO Conditions/Comments: Describe or reference.
Conditions:
Comments:
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
DECLARATION by RESEARCHER(S)
I have read and understood the UNLV Radiation Safety Manual. I agree to read any additional rules or guidelines
issued by UNLV or external regulatory agencies. I agree to abide by these rules or to discontinue working with
radioactive material.
Date
Insert additional boxes as needed.
Date
PROTOCOL REVIEW AND WALKTHROUGH
Authorized User
Print Name
Thomas Hartmann
Date
Sign
Exp. Date
PROTOCOL APPROVAL
Radiation Safety Officer (if required)
Print Name
Date
Sign
Exp. Date
RAM Protocol v8
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 1
ACTIVITY LIMITS FOR UNLV RADIATION SAFETY LEVELS FOR RADIOACITVE MATERIALS
Limiting Values - Radiological Health*
Nuclide
Am-241
Am-242m
Am-243
Ba-133
C-14
Cd-109
Cl-36
Cm-244
Cm-248
Co-57
Co-60
Cs-137
Eu-152
Eu-154
Eu-155
Gd-148
H-3
Hf-175
I-125
I-131
Mn-54
Na-22
Np-237
P-32
P-33
Pb-210
Po-210
Pu-236
Pu-238
Pu-239
Pu-240
Pu-241
Pu-242
Ra-226
Sb-125
Sm-147
Sr-85
Sr-90
Tc-99
Tc-99m
Th-229
Th-230
Th-232
Tl-204
U-232
U-233
U-235
U-238
Zn-65
Zr-95
ALI
Ingestion
(µCi)
0.8
0.8
ALI
Inhalation
(µCi)
0.006
0.006
Ratio
Ingestion
/Inhalation
0.8
2,000
2,000
300
2,000
1.0
0.2
4,000
200
100
800
500
4,000
10
80,000
3,000
40
30
2,000
400
0.5
600
6,000
1.0
3.0
2.0
0.9
0.8
0.8
40
0.8
2.0
2,000
20
3,000
30
4,000
80,000
0.6
4.0
0.7
2,000
2.0
10
10
10
400
1,000
0.006
700
2,000
40
2,000
0.010
0.002
700
30
200
20
20
90
0.008
80,000
900
60
50
800
600
0.004
400
3,000
20
0.60
0.020
0.007
0.006
0.006
0.30
0.007
0.60
500
0.070
2,000
4.00
700
200,000
0.001
0.006
0.001
2,000
0.008
0.040
0.040
0.040
300
100
RAM Protocol v8
Rad Level
1**
133
133
Limiting ALI
(µCi)
0.01
0.01
Less Than
(µCi)
0.000060
0.000060
133
2.86
1.00
7.50
1.00
100
100
5.71
6.67
0.50
40
25
44
1,250
1.00
3.33
0.67
0.60
2.50
0.67
125
1.50
2
0.05
5.00
100
129
133
133
133
114
3.33
4.00
286
1.50
7.50
5.71
0.40
667
667
700
1.00
250
250
250
250
1.33
10
0.01
700
2,000
40
2,000
0.01
0.002
700
30
100
20
20
90
0.01
80,000
900
40
30
800
400
0.004
400
3,000
1.00
0.60
0.02
0.01
0.01
0.01
0.30
0.01
0.60
500
0.07
2,000
4.00
700
80,000
0.001
0.01
0.001
2,000
0.01
0.04
0.04
0.04
300
100
0.000060
7.00
20
0.400
20
0.00010
0.000020
7.00
0.300
1.00
0.200
0.200
0.900
0.000080
50
9.00
0.400
0.300
8.00
4.00
0.000040
4.00
50
0.010
0.0060
0.00020
0.000070
0.000060
0.000060
0.0030
0.000070
0.0060
5.00
0.00070
20
0.040
7.00
50
0.000009
0.000060
0.000010
20
0.000080
0.00040
0.00040
0.00040
3.00
1.00
Page 7 of 12
Rad Level
2
Rad Level 3
Rad Level 4
Not Airborne
& Less Than
(µCi)
If NOT
Airborne Less
Than (µCi)
If Airborne
Less Than
(µCi)
If NOT
Airborne Less
Than (µCi)
If Airborne
Less Than
(µCi)
0.80
0.80
40
40
0.30
0.30
800
800
6.00
6.00
0.80
2,000
2,000
300
2,000
1.00
0.20
4,000
200
100
800
500
4,000
10
5,000
3,000
40
30
2,000
400
0.50
600
5,000
1.00
3.00
2.00
0.90
0.80
0.80
40
0.80
2.00
2,000
20
3,000
30
4,000
5,000
0.60
4.00
0.70
2,000
2.00
10
10
10
400
1,000
40
50,000
50,000
50,000
50,000
50
10
50,000
50,000
50,000
50,000
50,000
50,000
500
50,000
50,000
2,000
1,500
50,000
50,000
25
50,000
50,000
50
150
100
45
40
40
2,000
40
100
50,000
1,000
50,000
1,500
50,000
50,000
30
200
35
50,000
100
500
500
500
50,000
50,000
0.30
35,000
50,000
2,000
50,000
0.50
0.10
35,000
1,500
5,000
1,000
1,000
4,500
0.40
50,000
45,000
2,000
1,500
40,000
20,000
0.20
20,000
50,000
50
30
1.00
0.35
0.30
0.30
15
0.35
30
25,000
3.50
50,000
200
35,000
50,000
0.05
0.30
0.05
50,000
0.40
2.00
2.00
2.00
15,000
5,000
800
1,000,000
1,000,000
300,000
1,000,000
1,000
200
1,000,000
200,000
100,000
800,000
500,000
1,000,000
10,000
1,000,000
1,000,000
40,000
30,000
1,000,000
400,000
500
600,000
1,000,000
1,000
3,000
2,000
900
800
800
40,000
800
2,000
1,000,000
20,000
1,000,000
30,000
1,000,000
1,000,000
600
4,000
700
1,000,000
2,000
10,000
10,000
10,000
400,000
1,000,000
6.00
700,000
1,000,000
40,000
1,000,000
10
2.00
700,000
30,000
100,000
20,000
20,000
90,000
8.00
1,000,000
900,000
40,000
30,000
800,000
400,000
4.00
400,000
1,000,000
1,000
600
20
7.00
6.00
6.00
300
7.00
600
500,000
70
1,000,000
4,000
700,000
1,000,000
0.90
6.00
1.00
1,000,000
8.00
40
40
40
300,000
100,000
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
* USNRC 10 CFR20 Appendix B Table 1. Revised Aug 11 2010.
** See "UNLV Guideline for Risk Assessment and Control of Radioactive Materials" for details on derivation of risk level limits.
Note: If nuclide is not listed, refer to 10 CFR 20, Appendix B, Table 1
Note: Green indicates limit is set to control the potential for FACILITY contamination.
RAM Protocol v8
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UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
Rad Safety
Level
Risk Level
MINIMAL RISK: Unlikely to produce a
dose to a Worker greater than 100
mrem.
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS
Activity per Experiment *
Control Measures
(all apply)
Bioassay
Requirement and
Periodicity
≤ .01 ALI-Ingestion
None
 General supervision by the
Authorized User
Max. = 50 µCi
None
 Instruction to Workers on rad risks
and proper handling procedures
(1 ALI intake = 5000 mrem, 0.01 ALI
intake = 50 mrem)
1
Air Monitoring
 In procedures and post use survey
by Worker
 Monthly inspection and quarterly
survey by Radiation Safety Office
LOW RISK: Possible to receive an
annual dose in excess of 5 rem.
Mitigated by the Worker:

2

understanding, and applying
good health physics work
practices and procedures
use of engineering and
contamination control
measures
Non Airborne
>.01 to ≤ 1.0
ALI-Ingestion
Airborne
≤ .01 ALI-Limiting
All
Max. = 5 mCi
(1 ALI intake = 5000 merm)
RAM Protocol v8
 Instruction to Worker on rad risks
and proper handling procedures
None
.
 Review, understand and apply
research protocol
 Lab specific training by Authorized
User followed by routine
supervision
 In-procedure monitoring and post
use surveys by Worker
 Monthly inspection and quarterly
survey by Radiation Safety Office
Page 9 of 12
None
None
None
.
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS (cont.)
Rad
Safety
Level
Risk Level
MODERATE RISK: Likely to receive an annual
dose in excess of 5 rem. Mitigated by:


3
the Worker has thorough knowledge
of radiation safety principles and
practices, plus task specific training
use of engineering and
contamination control measures

consistent use of task specific
control measures

demonstrating ability to effectively
control radiation hazards
Activity per Experiment *
(all apply)
Control Measures
Non-Airborne
Bioassay
Requirement and
Periodicity
 Protocol approval by Authorized User
and RSO
> 1.0 to ≤50 ALI-Ingestion
 Lab specific training of Worker by
Authorized User followed by routine
supervision
Airborne
> .01 to ≤50 ALI-Limiting
All
 In-procedure monitoring and post use
surveys by Worker
Max. = 50 mCi
 Monthly inspection and survey by
Radiation Safety Office
Non-airborne
> 10 ALI (ingestion) requires fume
hood
Airborne

≥ 0.01 ALI (limiting), requires fume
hood

≥ 10 ALI (limiting), requires
negative pressure glove box
Baseline bioassay
and quarterly
bioassay required:
>5 ALI (limiting)
dispersible material
(potential airborne)
>100ALI (ingestion)
dispersible material.
Or unescorted
access to RAD Level
3 or 4 labs.
RAM Protocol v8
Air Monitoring
Page 10 of 12
Routine air
monitoring required
if > 0.01 ALI of dry,
dispersible material
(potential airborne).
Continuous air
monitoring required
if >0.1 ALI of dry,
dispersible material
(potential airborne).
Breathing Zone
Air-sampling (BZA)
is required when
working with ≥ 1 ALI
of dry, dispersible
material (potential
airborne).
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS (cont.)
Rad
Safety
Level
Risk Level
HIGH RISK: Very likely to receive an annual
dose in excess of 5 rem. Mitigated by:



4
the Worker has advanced
knowledge in radiation safety
principles and practices, plus task
specific training and procedures
consistently using task specific
control measures
Activity per Experiment *
(all apply)
Non-Airborne
>50 to ≤ 1,000
ALI-Ingestion
Airborne
> 50 to ≤1,000 ALI-Limiting
All
Max. = 1000 mCi
demonstrating the ability to
effectively control radiation
hazards
Control Measures
Air Monitoring
 Protocol approval by Authorized User
and RSO
 Authorized User MUST be present in lab
 Initial applied training of Worker by
Authorized User followed by routine
supervision
 In-procedure monitoring and post use
surveys by Worker
 Weekly survey by Authorized User/Staff
 Monthly inspection and survey by
Radiation Safety
Non-Airborne
≥100 ALI-(limiting), requires negative
pressure glove box
Airborne
≥ 10 ALI (limiting), requires negative
pressure glove box - 1,000 ALI
(limiting) maximum
RAM Protocol v8
Bioassay
Requirement and
Periodicity
Page 11 of 12
Baseline bioassay
and quarterly
bioassay required.
Work activity review
by the Radiation
Safety Office may
increase bioassay
frequency.
Continuous air
monitoring required
Breathing Zone
Air-sampling (BZA)
required
.
UNLV RM&S
RSO FORM 22
University of Nevada Las Vegas
ATTACHMENT 2
UNLV RISK ASSESSMENT and CONTROL GUIDELINE for
UNSEALED-RADIOACTIVE MATERIALS (cont.)
NOTE:
* See Attachment 1, Activity Limits for UNLV Radiation Safety Levels for Radioactive Materials, for listing of activity levels by individual nuclide.
Abbreviations:
ALI
Annual limit on intake.
ALI-Limiting
Lowest ALI for either ingestion or inhalation for a given nuclide.
Assumed Protection Factors:
- Airborne:
Open Bench
1X
Fume Hood
1,000X
Negative Pressure Glove Box
100,000X
- Non-Airborne:
Open Bench
1X
Fume Hood
10X
Negative Pressure Glove Box
1,000X
Definitions –
Annual limit on intake (ALI): As defined in Title 10, Section 20.1003, of the Code of Federal Regulations (10 CFR 20.1003), ALI is “the derived limit for the amount
of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by
the reference man that would result in a committed effective dose equivalent of 5 rems (0.05 Sv) or a committed dose equivalent of 50 rems (0.5 Sv) to any individual
organ or tissue. (ALI values for intake by ingestion and by inhalation of selected radionuclides are given in Table 1, Columns 1 and 2, of appendix B to §§ 20.1001`20.2401)."
RAM Protocol v8
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