ML12159A217
| ML12159A217 | |
| Person / Time | |
|---|---|
| Issue date: | 06/07/2012 |
| From: | Office of the Chief Human Capital Officer |
| To: | |
| References | |
| Download: ML12159A217 (129) | |
Text
April 2011 - Slide 1 of 133 Seminar for ASLBP (G-114)
H R T D Human Resources Training & Development Materials Overview
April 2011 - Slide 2 of 133 Seminar for ASLBP (G-114)
The NRCs Mission Statement The mission of the U.S. Nuclear Regulatory Commission is to ensure adequate protection of the public health and safety, the common defense and security, and the environment in the use of nuclear materials in the United States.
April 2011 - Slide 4 of 133 Seminar for ASLBP (G-114)
NRC Jurisdiction NRC NOT Responsible for:
NORM** (Naturally Occurring Radioactive Material) x-ray machines non-ionizing radiation (lasers, microwaves etc)
- non-discrete sources NRC Responsible for:
byproduct material*
source material special nuclear material
April 2011 - Slide 5 of 133 Seminar for ASLBP (G-114)
NRC is Not Alone in Regulating Radioactive Material Environmental Protection Agency (EPA)
Department of Transportation (DOT)
Department of Labor (DOL) - Occupational Safety and Health Administration (OSHA)
Department of Health and Human Services (HHS) - Food and Drug Administration (FDA) - National Center for Devices and Radiological Health (NCDRH)
Department of Energy (DOE)
Agreement States (regulate all radiation sources except Nuclear Power Plants and Federal Facilities)
Non-Agreement States (regulate non-NRC radiation sources)
Agreement States (37)
States with letters of intent to become Agreement States (1)
Non-Agreement States (NRC Jurisdiction) (12+DC+PR+USVI+Guam)
April 2011 - Slide 7 of 133 Seminar for ASLBP (G-114)
Topics Overview Licensing (G-109)
Inspection (G-108)
Medical Applications Nuclear Medicine (H-304)
Brachytherapy, etc (H-313)
Industrial Applications Radiography (H-305)
Irradiators (H-315)
Well Logging (H-314)
Gauges (fixed & portable)
April 2011 - Slide 8 of 133 Seminar for ASLBP (G-114)
MATERIALS LICENSING INSPECTION
April 2011 - Slide 9 of 133 Seminar for ASLBP (G-114)
Exempt - no license (e.g., smoke detector)
General License - license comes with device (e.g., EXIT signs)
Specific License - application and approval process Limited Broad Scope (e.g., Universities & Medical Centers)
Master Materials (USAF, USN and VA)
NUREG-1556 Consolidated Licensing Guidance (21 vol)
Types of Licenses
April 2011 - Slide 10 of 133 Seminar for ASLBP (G-114) limit access and use of radioactive material permit use of RAM by qualified individuals assure an adequate level of safety provide flexibility Goals of Licensing
GAO Sting
April 2011 - Slide 12 of 133 Seminar for ASLBP (G-114)
Performance - to determine if licensed activities are being conducted in a manner that will protect the health and safety of workers and the general public
Compliance - to determine if licensed programs are being conducted in accordance with U.S. Nuclear Regulatory Commission requirements
The inspectors job is to identify problems, not violations Inspections
surveys interviews demonstration of activities observation of activities records review
April 2011 - Slide 14 of 133 Seminar for ASLBP (G-114) security and control of licensed material shielding of licensed material comprehensive safety measures radiation dosimetry program radiation instrumentation and surveys radiation safety training and practices management oversight Performance Based Inspection Focus Elements
MEDICAL APPLICATIONS
April 2011 - Slide 16 of 133 Seminar for ASLBP (G-114)
Medical Uses of Radiation Diagnostic Radiology (X-rays)
Nuclear Medicine (Liquids and Gases Inside the Body)
Radiation Therapy (Sealed Sources of Radiation Either Inside or Outside the Body)
April 2011 - Slide 17 of 133 Seminar for ASLBP (G-114)
Nuclear Medicine Concepts Forms Liquid (injected or swallowed)
Gas (inhaled)
Labeled Radiopharmaceutical = Organ Specific Drug Uses Diagnostic (gamma) - obtain information (uptake/imaging/function)
Therapeutic (beta) - destroy tissue
April 2011 - Slide 18 of 133 Seminar for ASLBP (G-114)
Cardiac Stress Test
April 2011 - Slide 19 of 133 Seminar for ASLBP (G-114)
Isotope Generator vs Unit Dose Molybdenum Technetium
April 2011 - Slide 20 of 133 Seminar for ASLBP (G-114)
Tc-99m - Shielding
April 2011 - Slide 21 of 133 Seminar for ASLBP (G-114)
Positron Emission Tomography (PET) - Shielding
April 2011 - Slide 22 of 133 Seminar for ASLBP (G-114)
Thyroid Ablation 100 mCi - 200 mCi of Iodine-131 (mostly use capsules now)
April 2011 - Slide 23 of 133 Seminar for ASLBP (G-114)
Some Nuclear Medicine Issues
Pregnancy
Breastfeeding
Patient Release
Wrong Patient
April 2011 - Slide 24 of 133 Seminar for ASLBP (G-114)
Pregnancy During thyroid ablation therapy, a woman received a dose of 150 millicuries of I-131 in accordance with approved hospital procedures.
The woman insisted multiple times that she was not pregnant. Later, it was determined that she was 12-14 weeks pregnant with twins.
Each fetus received an estimated dose of:
38 rem to the whole body and 200,000 rad to the thyroid
April 2011 - Slide 25 of 133 Seminar for ASLBP (G-114)
Breastfeeding A 43 year old female patient was to undergo thyroid ablation therapy.
The patient denied breast feeding her 4 year old son. She was given 3 mCi of I-131 for a whole body scan.
During the scan (3 days later), she was advised of the precautions surrounding the impending ablation therapy. The patient admitted breast feeding her son during the previous three days. She was told to immediately discontinue breast feeding.
She returned the following week with her son to have his uptake assessed. His estimated doses were thyroid - 184 rad, whole body -
5.5 rad. She revealed that she had continued to breast feed her son.
The hospital canceled the thyroid ablation procedure
April 2011 - Slide 26 of 133 Seminar for ASLBP (G-114)
Patient Release Criteria (10 CFR 35.75)
Patients administered radiopharmaceuticals or permanent implants may be released if dose to any other individual is not likely to exceed 500 mrem 10 CFR 20.1301 (public)
(a) Each licensee shall conduct operations so that--
(1) The dose to a member of the public does not exceed 100 mrem, excluding the dose from individuals administered radioactive material and released IAW
April 2011 - Slide 27 of 133 Seminar for ASLBP (G-114)
Patient Release Criteria RIS 2006-18 (August 2006)
For hospitalized patients, caregivers allowed up to 2 rem maximum May be increased on a case-by-case basis.
RIS 2011-01 (January 2011)
NRC Policy on Release of Iodine-131 Therapy Patients Under 10 CFR 35.75 to Locations Other Than Private Residences
April 2011 - Slide 28 of 133 Seminar for ASLBP (G-114)
Dose exceeds 5 rem when:
wrong radioactive drug wrong route wrong individual wrong mode leaking sealed source Note: This assumes no patient intervention caused the event.
Medical Event (10 CFR 35.3045)
April 2011 - Slide 29 of 133 Seminar for ASLBP (G-114)
A patient received 10 millicuries of Technetium-99m Time for a Quiz WOULD YOU CONSIDER THIS A REPORTABLE MEDICAL EVENT?
It was later discovered that the patient was only there for a routine stress test involving NO radioactive material.
April 2011 - Slide 30 of 133 Seminar for ASLBP (G-114)
Dose exceeds 5 rem when:
wrong radioactive drug wrong route wrong individual wrong mode leaking sealed source Medical Event (10 CFR 35.3045)
April 2011 - Slide 31 of 133 Seminar for ASLBP (G-114)
According to the DuPont Merck website, a 10 mCi dose of Cardiolite will produce the following approximate doses:
Large Intestine 1.5 rem Bladder 1.5 rem Small Intestine 1.0 rem Kidneys 0.6 rem Ovaries*
0.4 rem Testes**
- if patient was female
- if patient was male Typical 99mTechnetium Doses
April 2011 - Slide 32 of 133 Seminar for ASLBP (G-114)
OK, so its not a Medical Event, but could it be an overexposure of a member of the public since hes not a radiation worker and he wasnt scheduled to receive the radiation dose as a patient ?
Licensee Event Report 11/98
April 2011 - Slide 33 of 133 Seminar for ASLBP (G-114)
Public Doses - 10 CFR 20.1301 (a) Each licensee shall conduct operations so that--
(1) The dose to a member of the public does not exceed 100 mrem, excluding the dose from any medical administration the individual has received But wait a minute, does this really qualify as a medical administration given that he wasnt supposed to get it at all (it wasnt prescribed by any physician)
April 2011 - Slide 34 of 133 Seminar for ASLBP (G-114)
NRC Policy It was a medical administration. Although he wasnt supposed to get it and it wasnt prescribed, the injection of radioactive material in a hospital is considered a medical administration and all medical administrations of byproduct material are subject to 10 CFR Part 35 (medical regulations) not 10 CFR Part 20 (radiation safety regulations) so the public limit of 100 mrem doesnt apply.
The bottom line is there was no violation of NRC regulations (he can pursue malpractice but he didnt sustain much harm other than psychological and a small risk of cancer)
April 2011 - Slide 35 of 133 Seminar for ASLBP (G-114)
Hospital visitor:
exposed by source transported down hall (< 100 mrem)
exposed by source inside a nearby patient (< 500 mrem)
caregiver (2,000 mrem +)
inadvertently given radioactive material (< 5,000 mrem)
Some Limits on Exposures to a Member of the Public Releases to environment (15-50 mrem)
Nuclear Power Plant and Most Licensees (< 100 mrem)
April 2011 - Slide 36 of 133 Seminar for ASLBP (G-114)
Nuclear Medicine Accidents Phoenix AZ (89)
Therapeutic Dose Instead of Diagnostic
April 2011 - Slide 37 of 133 Seminar for ASLBP (G-114)
Linear Accelerators (X-rays or Electrons)
Teletherapy (Sealed Source Outside the Body)
Brachytherapy (Sealed Source Inside the Body)
Radiation Therapy with Sealed Sources
April 2011 - Slide 38 of 133 Seminar for ASLBP (G-114)
Teletherapy Teletherapy Unit Source Head (see source drawer display) 5,000 Ci 130 R/min @ 1 m
April 2011 - Slide 39 of 133 Seminar for ASLBP (G-114) 18 mm 19 mm Capsule
( 5,000 Ci)
Cobalt-60 Pellets Teletherapy Source
April 2011 - Slide 40 of 133 Seminar for ASLBP (G-114)
After 5 treatments, the prescribing physician said, Oops, the tumor is actually located to the RIGHT side of the brain!
A patient received cobalt-60 treatment for a brain tumor LEFT of midline. 10 treatments were prescribed at 180 rad per day. The written directive prescribed 2 fields.
73% to the LEFT 27% of the dose was to be delivered to the RIGHT side R
L Time for Another Quiz WOULD YOU CONSIDER THIS A REPORTABLE MEDICAL EVENT?
April 2011 - Slide 41 of 133 Seminar for ASLBP (G-114)
OGC Interpretation The doc goofed. He incorrectly identified the location of the tumor volume and thus prepared a written directive based on this error.
However, the prescribed dose was administered in accordance with the written directive, therefore this incident does not constitute a medical event.
April 2011 - Slide 42 of 133 Seminar for ASLBP (G-114)
Stereotactic Radiosurgery (SRS)
Gamma Knife 201 Co-60 sources about 33 Curies each
April 2011 - Slide 43 of 133 Seminar for ASLBP (G-114)
Gamma Knife
April 2011 - Slide 44 of 133 Seminar for ASLBP (G-114)
Sealed Source(s) Placed Inside Body Terminology Temporary vs Permanent Implant Intracavitary vs Interstitial Applicators Seeds-Needles-Wire-Ribbons Manual Brachytherapy High Dose Rate Remote Afterloading (HDR)
April 2011 - Slide 45 of 133 Seminar for ASLBP (G-114)
Cesium-137 (Cs-137) tube sources Iridium-192 (Ir-192) seeds in nylon ribbon Paladium-103 (Pd-103) seeds Iodine-125 (I-125) seeds Sr-90 Eye applicators Manual Brachytherapy
April 2011 - Slide 46 of 133 Seminar for ASLBP (G-114)
Manual Brachytherapy Source 3/4 inch
April 2011 - Slide 47 of 133 Seminar for ASLBP (G-114)
Applicators
April 2011 - Slide 48 of 133 Seminar for ASLBP (G-114)
Seeds
April 2011 - Slide 49 of 133 Seminar for ASLBP (G-114)
I-125 Seed Small seeds are sealed sources, but they can be crushed or broken
April 2011 - Slide 50 of 133 Seminar for ASLBP (G-114)
Strontium-90 Beta Eye Applicator plastic shield for physician source attached here and placed on eye sources
April 2011 - Slide 51 of 133 Seminar for ASLBP (G-114)
Sr-90 Eye Applicator Typical Storage Boxes
April 2011 - Slide 52 of 133 Seminar for ASLBP (G-114)
High Dose Remote Afterloading (HDR)
Source travels from unit, through catheter (plastic guide tube) into patient
April 2011 - Slide 53 of 133 Seminar for ASLBP (G-114)
HDR Source 0.08 R/min @ 1 m 13 R/sec @ 1 cm (0.3 mm)
(0.1 mm)
(0.5 mm)
April 2011 - Slide 54 of 133 Seminar for ASLBP (G-114)
Prostate HDR
April 2011 - Slide 55 of 133 Seminar for ASLBP (G-114)
HDR Breast Treatment
April 2011 - Slide 56 of 133 Seminar for ASLBP (G-114)
HDR Accident CAUSES Inadequate Training Failure to Follow Procedures Equipment Design & Testing Weak Regulations INDIANA PA (92) [NUREG 1480]
4.3 Curie Iridium-192 Source Left Inside Patient Patient Died Source Discovered at Commercial Waste Facility Prescribed Dose 1.8 Krad - Delivered 1.6 Mrad Doses to 94 people other than patient
April 2011 - Slide 59 of 133 Seminar for ASLBP (G-114)
Brachytherapy (Stent & Theraspheres) 20-40 micrometers diameter (about 1,000th of an inch)
Beads with beta source
April 2011 - Slide 60 of 133 Seminar for ASLBP (G-114)
Mammosite (1 minute video)
April 2011 - Slide 61 of 133 Seminar for ASLBP (G-114)
NeoVista Epi-Rad90
April 2011 - Slide 62 of 133 Seminar for ASLBP (G-114)
END OF MEDICAL APPLICATIONS
INDUSTRIAL APPLICATIONS
April 2011 - Slide 64 of 133 Seminar for ASLBP (G-114)
Radiography (H-305)
Irradiators (H-315)
Well Logging (H-314)
Gauges (G-108)
Topics
April 2011 - Slide 65 of 133 Seminar for ASLBP (G-114)
Double Encapsulated Source
April 2011 - Slide 66 of 133 Seminar for ASLBP (G-114)
INDUSTRIAL RADIOGRAPHY
April 2011 - Slide 67 of 133 Seminar for ASLBP (G-114)
What is Industrial Radiography?
April 2011 - Slide 68 of 133 Seminar for ASLBP (G-114)
Industrial Radiography (10 CFR Part 34)
SOURCES:
Iridium-192 (T1/2 = 74 days)
Cobalt-60 (T1/2 = 5 years) 192Ir ACTIVITY:
~ 100 Ci OUTPUT:
~ 1 R/min @ 1 m
~ 130 R/sec @ 1 cm TYPES:
X-Ray or Radionuclides
April 2011 - Slide 69 of 133 Seminar for ASLBP (G-114)
QSA Global (Sentinel)
Model 660 192Ir Radiography Cameras Source Production
& Equipment Co.
Model SPEC-150 Industrial Nuclear Co.
Model IR-100 Sentinel Model 880
April 2011 - Slide 70 of 133 Seminar for ASLBP (G-114) 60Co Radiography Cameras SPEC Model SPEC-300 Sentinel Model 680B
Radiography Camera Design Locking key DU shield pill
April 2011 - Slide 72 of 133 Seminar for ASLBP (G-114)
Source Assembly (Pigtail) pill lock button cable
April 2011 - Slide 73 of 133 Seminar for ASLBP (G-114)
Radiography Camera
& Associated Equipment Control Sheaths End Stop Connector Drive Control Lock Assembly Source Guide Tube Crank
April 2011 - Slide 74 of 133 Seminar for ASLBP (G-114)
Collimators
April 2011 - Slide 75 of 133 Seminar for ASLBP (G-114)
Source Changer Old One Goes In New One Comes Out
April 2011 - Slide 76 of 133 Seminar for ASLBP (G-114)
Permanent Radiographic Installation & Field Operations Portable Darkroom
April 2011 - Slide 77 of 133 Seminar for ASLBP (G-114)
Radiography Boundaries (ideal vs practical)
April 2011 - Slide 78 of 133 Seminar for ASLBP (G-114)
Setting up to shoot the weld Field Site Radiography
April 2011 - Slide 79 of 133 Seminar for ASLBP (G-114)
Posilock Release Field Site Radiography
April 2011 - Slide 80 of 133 Seminar for ASLBP (G-114)
Using distance
& shielding Cranking out the source Field Site Radiography
April 2011 - Slide 81 of 133 Seminar for ASLBP (G-114)
Survey after a shot Field Site Radiography
April 2011 - Slide 82 of 133 Seminar for ASLBP (G-114)
Field Radiography (indoors)
April 2011 - Slide 83 of 133 Seminar for ASLBP (G-114)
Offshore Radiography Laybarge Drilling platform
April 2011 - Slide 84 of 133 Seminar for ASLBP (G-114)
Reciprocity (NRC Form 241)
Two man rule
Radiographer Certification Some Radiography Issues
April 2011 - Slide 85 of 133 Seminar for ASLBP (G-114)
Improper Shipment Korea USA (1990) truck drivers (0.5 - 35 rem estimated)
Source should have been sealed in here Instead it was lying here It wasnt supposed to have any source at all
April 2011 - Slide 86 of 133 Seminar for ASLBP (G-114)
Note: The following slides show graphic injuries sustained by individuals involved in radiography accidents. to These images are intended to demonstrate the serious consequences of failure to follow procedures and the importance of doing thorough inspections Radiography Accidents
April 2011 - Slide 87 of 133 Seminar for ASLBP (G-114) 31 days 1979 Industrial Radiography Accident 50 days 19 months
April 2011 - Slide 88 of 133 Seminar for ASLBP (G-114)
Industrial Radiography Accident 14 days 24 days 27 days 56 days 102 days 5 years
April 2011 - Slide 89 of 133 Seminar for ASLBP (G-114)
IRRADIATORS
April 2011 - Slide 90 of 133 Seminar for ASLBP (G-114)
Sterilization Irradiators (10 CFR Part 36)
Preservation
April 2011 - Slide 91 of 133 Seminar for ASLBP (G-114)
I source always shielded II open beam port III source underwater IV source stored underwater, exposed in air Irradiator Categories
April 2011 - Slide 92 of 133 Seminar for ASLBP (G-114)
An irradiator in which the sealed source is completely enclosed in a dry container constructed of solid materials and is shielded at all times, and where human access to the sealed source and the volume undergoing irradiation is not physically possible in the designed configuration (ANSI Std N43.7)
Category I - Self-Contained Dry Source Storage Irradiators
April 2011 - Slide 93 of 133 Seminar for ASLBP (G-114)
Category II Open Beam Port Irradiator Beam Port A controlled human access irradiator in which the sealed source is enclosed in a dry container constructed of solid materials, is fully shielded when not in use and is exposed within a radiation volume that is maintained inaccessible during use by an entry control system (ANSI Std. N43.12)
April 2011 - Slide 94 of 133 Seminar for ASLBP (G-114)
Category III Self Contained Wet Source Source An irradiator in which the sealed source is contained in a water filled storage pool and is shielded at all times, and where human access to the sealed source and the volume undergoing irradiation is physically restricted in the designed configuration and proper mode of use (ANSI Std. N43.15)
April 2011 - Slide 95 of 133 Seminar for ASLBP (G-114)
Category IV (Manual Tote Box System)
Source A controlled human access irradiator in which the sealed source is contained in a water filled storage pool, is fully shielded when not in use and is exposed within a radiation volume that is maintained inaccessible during use by an entry control system (ANSI Std. N43.10)
April 2011 - Slide 96 of 133 Seminar for ASLBP (G-114)
Category IV Sources pencil module
April 2011 - Slide 97 of 133 Seminar for ASLBP (G-114)
Irradiator Accidents EL SALVADOR (1989)
Category IV - 18K Ci Cobalt-60 Doses (estimated) - 3K - 8K rad Injuries - 2 Fatalities - 1 within 7 months ISRAEL (1990)
Category IV - 340K Ci Cobalt-60 Dose (estimated) - 1.5K rad Fatalities - 1 within 40 days
April 2011 - Slide 98 of 133 Seminar for ASLBP (G-114)
Category IV - 1.2 MCi Cesium-137
No injuries & no doses
Contaminated Pool Water (1 Leaking Capsule out of 252)
Decontamination Completed 1992 Irradiator Accidents USA - Puerto Rico (LER 40693 4/21/2004)
Category IV - 4 MCi Cobalt-60
Doses - 2.8 & 4.4 rem in a few seconds
Injuries - none
source Product Path NRC AIT - Stuck 2 MCi 60Co Source Entry into Pool Irradiator (2004)
source in pool Worker Path
~11:30 AM - walk from product Exit Door to Personnel Door
source exposed
~ 1:00 PM - walk from product Exit Door to B stop and return to Exit Door Worker Path
source exposed Worker path 30 rad/sec Proposed path Dose rates with one source rack unshielded (2,000,000 Ci 60Co)
April 2011 - Slide 103 of 133 Seminar for ASLBP (G-114)
WELL LOGGING
April 2011 - Slide 104 of 133 Seminar for ASLBP (G-114)
Operating Oil Rig
April 2011 - Slide 105 of 133 Seminar for ASLBP (G-114)
Well Logging Operations Drill-to-Stop Measurement While Drilling Tracer studies and field flood studies
April 2011 - Slide 106 of 133 Seminar for ASLBP (G-114)
Well Logging (Drill-to-stop)
April 2011 - Slide 107 of 133 Seminar for ASLBP (G-114)
Measurement While Drilling (MWD)
April 2011 - Slide 108 of 133 Seminar for ASLBP (G-114)
Cobalt-60 & Cesium-137 Americium-241 Iridium-192 & Hydrogen-3 Cobalt-57 & Iodine-131
Depleted Uranium Well Logging Sources
April 2011 - Slide 109 of 133 Seminar for ASLBP (G-114) well logging tools without sources Well Logging (Vehicle and Tools)
April 2011 - Slide 110 of 133 Seminar for ASLBP (G-114)
Well Logging Sealed Sources 137Cs 241Am:Be
April 2011 - Slide 111 of 133 Seminar for ASLBP (G-114)
Well Logging (Source and Tool)
(Am-Be)
April 2011 - Slide 112 of 133 Seminar for ASLBP (G-114)
Sealed Source Handling Tool Engaging sealed source in transport container Handling Tool
April 2011 - Slide 113 of 133 Seminar for ASLBP (G-114)
Installing sealed source into MWD well logging tool Sealed Source Handling Removing source from the transport container
April 2011 - Slide 114 of 133 Seminar for ASLBP (G-114)
Incidents Lost Sources
- During Transport
- On Rig
- Down Well Unauthorized Maintenance
April 2011 - Slide 115 of 133 Seminar for ASLBP (G-114)
Plaque for Abandoned Source in Well
April 2011 - Slide 116 of 133 Seminar for ASLBP (G-114)
April 2011 - Slide 117 of 133 Seminar for ASLBP (G-114)
GAUGES (10 CFR Parts 30, 31, 32)
April 2011 - Slide 118 of 133 Seminar for ASLBP (G-114)
Detector Source Holder 1 curie cesium-137 Fixed Gauge 6 mR/min @ 1 m
April 2011 - Slide 119 of 133 Seminar for ASLBP (G-114)
Flow and Fill
April 2011 - Slide 120 of 133 Seminar for ASLBP (G-114)
Product Level
April 2011 - Slide 121 of 133 Seminar for ASLBP (G-114)
Product Thickness
April 2011 - Slide 122 of 133 Seminar for ASLBP (G-114)
Reality Gauges
April 2011 - Slide 123 of 133 Seminar for ASLBP (G-114)
Problems
- Accountability (thrown out as scrap metal)
- Environment (encased in molten steel)
- Maintenance
April 2011 - Slide 124 of 133 Seminar for ASLBP (G-114)
SOURCES 8-10 mCi Cesium-137 (gamma) 40-50 mCi Americium-241 (Am-Be) (alpha/neutron)
DOSE RATES (approximate) 20 mrem/hr at surface 2 mrem/hr at 1 foot Portable Gauges
April 2011 - Slide 125 of 133 Seminar for ASLBP (G-114)
Portable Gauge Operation source detector fixed distance source detector
April 2011 - Slide 126 of 133 Seminar for ASLBP (G-114)
Measure as you go Portable Gauges
April 2011 - Slide 127 of 133 Seminar for ASLBP (G-114)
Problems
Transportation
Theft
Construction (destruction?)
April 2011 - Slide 128 of 133 Seminar for ASLBP (G-114)
Gauge Hazard THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL Less than IAEA Category 3 sources are sources that are very unlikely to cause permanent injury to individuals. The amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. This source is not amongst those sources or devices identified by the IAEA to be of concern from a radiological standpoint.