ML12146A387
| ML12146A387 | |
| Person / Time | |
|---|---|
| Issue date: | 05/25/2012 |
| From: | NRC/OI, NRC/OIG |
| To: | |
| References | |
| Download: ML12146A387 (99) | |
Text
03/22/10 - slide 0 G-112 OIG/OI Reactor & Materials Overview INDUSTRIAL APPLICATIONS H R T D Human Resources Training & Development
03/22/10 - slide 1 G-112 OIG/OI Reactor & Materials Overview Radiography Irradiators Well Logging Gauges Topics
03/22/10 - slide 2 G-112 OIG/OI Reactor & Materials Overview Double Encapsulated Source
03/22/10 - slide 3 G-112 OIG/OI Reactor & Materials Overview INDUSTRIAL RADIOGRAPHY
03/22/10 - slide 4 G-112 OIG/OI Reactor & Materials Overview Radiograph Welds
03/22/10 - slide 5 G-112 OIG/OI Reactor & Materials Overview QSA Global (Sentinel)
QSA Model 660 Series 192Ir Radiography Cameras Source Production
& Equipment Co.
Model SPEC-150 Industrial Nuclear Co.
Model IR-100
03/22/10 - slide 6 G-112 OIG/OI Reactor & Materials Overview 60Co Radiography Cameras SPEC Model SPEC-300 AEA Model 741
03/22/10 - slide 7 G-112 OIG/OI Reactor & Materials Overview Camera Labels
03/22/10 - slide 8 G-112 OIG/OI Reactor & Materials Overview Radiography Camera Design Locking key DU shield pill
03/22/10 - slide 9 G-112 OIG/OI Reactor & Materials Overview Source Assembly (Pigtail) pill lock button cable
03/22/10 - slide 10 G-112 OIG/OI Reactor & Materials Overview Sources Ir-192 wafers & Co-60 pellets
03/22/10 - slide 11 G-112 OIG/OI Reactor & Materials Overview Radiography Camera &
Associated Equipment Control Sheaths End Stop Connector Drive Control Lock Assembly Crank Source Guide Tube end stop beam collimator
03/22/10 - slide 12 G-112 OIG/OI Reactor & Materials Overview Daily Inspection Source Connector
03/22/10 - slide 13 G-112 OIG/OI Reactor & Materials Overview Radiographic Equipment
03/22/10 - slide 14 G-112 OIG/OI Reactor & Materials Overview Radiation Safety Equipment TLD Pocket Dosimeter Alarming Ratemeter Electronic Dosimeter Survey Meter
03/22/10 - slide 15 G-112 OIG/OI Reactor & Materials Overview Industrial Radiography (10 CFR Part 34)
SOURCE:
Iridium-192 (74 d) or Cobalt-60 (5.3 y)
OPERATIONS:
Field or Fixed 192Ir ACTIVITY:
~ 100 Ci OUTPUT:
~ 1 R/min @ 1 m
~ 130 R/sec @ 1 cm TYPES:
X-Ray or Radionuclides
03/22/10 - slide 16 G-112 OIG/OI Reactor & Materials Overview Source Changer Old One Goes In New One Comes Out
03/22/10 - slide 17 G-112 OIG/OI Reactor & Materials Overview Permanent Radiographic Installation
03/22/10 - slide 18 G-112 OIG/OI Reactor & Materials Overview Radiography Rig for Field Operations (portable darkroom mounted on truck)
03/22/10 - slide 19 G-112 OIG/OI Reactor & Materials Overview Radiography Areas (idealized)
03/22/10 - slide 20 G-112 OIG/OI Reactor & Materials Overview Field Radiography (outdoors) welding setup move source exposure crank out
03/22/10 - slide 21 G-112 OIG/OI Reactor & Materials Overview Field Radiography (indoors)
03/22/10 - slide 22 G-112 OIG/OI Reactor & Materials Overview Unusual Locations Off Shore Oil Drilling Platform Lay Barge (pipe laying operation)
03/22/10 - slide 23 G-112 OIG/OI Reactor & Materials Overview Pipeliner Radiation Comes out from Bottom Turn Handle to Expose Source
03/22/10 - slide 24 G-112 OIG/OI Reactor & Materials Overview Pipeline Crawler
03/22/10 - slide 25 G-112 OIG/OI Reactor & Materials Overview Reciprocity (NRC Form 241) (0)
Two man rule (1)
Radiographer Certification (2)
Some Radiography Issues
03/22/10 - slide 26 G-112 OIG/OI Reactor & Materials Overview Accident Causes Failure to:
perform surveys follow procedures Equipment malfunction
03/22/10 - slide 27 G-112 OIG/OI Reactor & Materials Overview Potential Problems Source
03/22/10 - slide 28 G-112 OIG/OI Reactor & Materials Overview Accident Reconstruction
03/22/10 - slide 29 G-112 OIG/OI Reactor & Materials Overview used 6 tongs to shake pigtail out of guide tube, pick it up & return it to shielded position in camera Radiography Source Retrieval
03/22/10 - slide 30 G-112 OIG/OI Reactor & Materials Overview 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
03/22/10 - slide 31 G-112 OIG/OI Reactor & Materials Overview Warning photos of radiation injury
03/22/10 - slide 32 G-112 OIG/OI Reactor & Materials Overview 31 days 1979 Industrial Radiography Accident 50 days 19 months
03/22/10 - slide 33 G-112 OIG/OI Reactor & Materials Overview Industrial Radiography Accident 14 days 24 days 27 days 56 days 102 days 5 years
03/22/10 - slide 34 G-112 OIG/OI Reactor & Materials Overview Severe injury to a non-radiation worker resulting from a radiographer failing to use a survey meter to confirm the source had been returned to the shielded container
185 GBq (5 Ci) 192Ir source in shirt pocket for 90 min
estimated skin dose 30 Gy (3,000 rad)
whole body 2-5 Gy (200-500 rad)
Day 15 Industrial Radiography Accidents
03/22/10 - slide 35 G-112 OIG/OI Reactor & Materials Overview Case Study NRC PNO-III-02-019 May 1, 2002
03/22/10 - slide 36 G-112 OIG/OI Reactor & Materials Overview END OF INDUSTRIAL RADIOGRAPHY
03/22/10 - slide 37 G-112 OIG/OI Reactor & Materials Overview IRRADIATORS
03/22/10 - slide 38 G-112 OIG/OI Reactor & Materials Overview
Sterilization Irradiators (10 CFR Part 36)
Preservation
03/22/10 - slide 39 G-112 OIG/OI Reactor & Materials Overview I
source always shielded II open beam port III source underwater IV source stored underwater, exposed in air Categories
03/22/10 - slide 40 G-112 OIG/OI Reactor & Materials Overview 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
03/22/10 - slide 41 G-112 OIG/OI Reactor & Materials Overview 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)
03/22/10 - slide 42 G-112 OIG/OI Reactor & Materials Overview 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)
03/22/10 - slide 43 G-112 OIG/OI Reactor & Materials Overview 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)
03/22/10 - slide 44 G-112 OIG/OI Reactor & Materials Overview SOURCES:
Cobalt-60 & Cesium-137 ACTIVITIES:
~ 1,000 - 10,000,000 Ci +
(approximate)
DOSE RATES:
(approximate)
Category I - Sample Irradiator - 500 rad/sec at sample Category IV - Product Irradiator - 300 rad/sec at 1 meter Specifications
03/22/10 - slide 45 G-112 OIG/OI Reactor & Materials Overview rack Category IV (Sources) pencil module source element source exchange
03/22/10 - slide 46 G-112 OIG/OI Reactor & Materials Overview Tyco Kendall irradiator facility in Deland, FL The Tyco Kendall irradiator uses Co-60 for gamma sterilization of medical products Tour of an Irradiator
03/22/10 - slide 47 G-112 OIG/OI Reactor & Materials Overview Personnel entry door -
source rising Tour of an Irradiator
03/22/10 - slide 48 G-112 OIG/OI Reactor & Materials Overview Intrusion alarms electric eyes at personnel entry door Tour of an Irradiator pressure sensitive mat
03/22/10 - slide 49 G-112 OIG/OI Reactor & Materials Overview Personnel entry
- chain barrier Tour of an Irradiator
03/22/10 - slide 50 G-112 OIG/OI Reactor & Materials Overview Emergency pull chain &
start-up warning alarm Tour of an Irradiator
03/22/10 - slide 51 G-112 OIG/OI Reactor & Materials Overview Irradiator pool float switches Tour of an Irradiator
03/22/10 - slide 52 G-112 OIG/OI Reactor & Materials Overview Pool water treatment equipment Radiation monitor Tour of an Irradiator
03/22/10 - slide 53 G-112 OIG/OI Reactor & Materials Overview Product exit door Radiation monitor Tour of an Irradiator
03/22/10 - slide 54 G-112 OIG/OI Reactor & Materials Overview Roof plug Tour of an Irradiator
03/22/10 - slide 55 G-112 OIG/OI Reactor & Materials Overview Loaded product carriers &
overhead rails Tour of an Irradiator
03/22/10 - slide 56 G-112 OIG/OI Reactor & Materials Overview 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
03/22/10 - slide 57 G-112 OIG/OI Reactor & Materials Overview USA - Georgia (1988)
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)
03/22/10 - slide 62 G-112 OIG/OI Reactor & Materials Overview END OF IRRADIATORS
03/22/10 - slide 63 G-112 OIG/OI Reactor & Materials Overview WELL LOGGING
03/22/10 - slide 64 G-112 OIG/OI Reactor & Materials Overview Operating Oil Rig (Used During NRC Training Course)
03/22/10 - slide 65 G-112 OIG/OI Reactor & Materials Overview USES:
Oil Exploration Field & Tracer Studies WELL LOGGING (10 CFR Part 39)
TYPES:
Gamma Logging Neutron Logging Logging While Drilling
03/22/10 - slide 66 G-112 OIG/OI Reactor & Materials Overview TERMINOLOGY:
Wireline Service Tools (Logging & Injection)
SOURCES:
Cobalt-60 & Cesium-137 Americium-241 Iridium-192 & Hydrogen-3 Cobalt-57 & Iodine-131 Well Logging
03/22/10 - slide 67 G-112 OIG/OI Reactor & Materials Overview well logging tools without sources Well Logging (Vehicle and Tools)
03/22/10 - slide 69 G-112 OIG/OI Reactor & Materials Overview Well Logging Sealed Sources 137Cs 241Am:Be
03/22/10 - slide 70 G-112 OIG/OI Reactor & Materials Overview Well Logging (Source and Tool)
(Am-Be)
03/22/10 - slide 71 G-112 OIG/OI Reactor & Materials Overview Well Logging (Vehicle at Site)
03/22/10 - slide 72 G-112 OIG/OI Reactor & Materials Overview Incidents Lost Sources During Transportation On Rig Down Well Unauthorized Maintenance
03/22/10 - slide 73 G-112 OIG/OI Reactor & Materials Overview Accidents Involving Well Logging Well Logging Source Source:
Am-Be (200 GBq)
==
Description:==
Source destroyed during recovery operation
03/22/10 - slide 74 G-112 OIG/OI Reactor & Materials Overview Plaque for Abandoned Source in Well
03/22/10 - slide 75 G-112 OIG/OI Reactor & Materials Overview Conventional Tracers Studies Tracer Transport Container Tracer Pumps Radiation Survey Meter at Tracer Distribution Junction before entering Well
03/22/10 - slide 76 G-112 OIG/OI Reactor & Materials Overview NUREG-1794 Augmented Inspection Team (AIT)
Loss of control of 1.3 curie Cs-137 source on May 21, 2002, in Montana Source lay unshielded on the drill rig floor for 2 days exposing 31 members of the public Direct cause: Failure of logging engineer to properly transfer the source to its transport container immediately after removal from tool Contributing causes: Failure to perform required radiation surveys; false indication of plug assembly Root cause: Failure to adequately investigate precursor events (six similar events occurred from 1987 and 2001, and only the direct cause of
03/22/10 - slide 78 G-112 OIG/OI Reactor & Materials Overview END OF WELL LOGGING
03/22/10 - slide 79 G-112 OIG/OI Reactor & Materials Overview GAUGES
03/22/10 - slide 80 G-112 OIG/OI Reactor & Materials Overview GAUGES (10 CFR Parts 30, 31, 32)
Process Control (fixed)
Road Paving (portable)
03/22/10 - slide 81 G-112 OIG/OI Reactor & Materials Overview FIXED GAUGES
03/22/10 - slide 82 G-112 OIG/OI Reactor & Materials Overview Detector Source Holder 1 curie cesium-137 Operation 6 mR/min @ 1 m
03/22/10 - slide 83 G-112 OIG/OI Reactor & Materials Overview Flow and Fill
03/22/10 - slide 84 G-112 OIG/OI Reactor & Materials Overview Fill Level
03/22/10 - slide 85 G-112 OIG/OI Reactor & Materials Overview Product Thickness
03/22/10 - slide 86 G-112 OIG/OI Reactor & Materials Overview Conveyor Belt
03/22/10 - slide 87 G-112 OIG/OI Reactor & Materials Overview Reality Gauges
03/22/10 - slide 88 G-112 OIG/OI Reactor & Materials Overview Combine radiation measurements with inspection of the physical condition of gauge, labels, supports, etc.
Fixed Gauge Inspections Evaluate environmental conditions to determine what hazards (to the gauges) are present (SS&D)
03/22/10 - slide 89 G-112 OIG/OI Reactor & Materials Overview Problems
- Accountability (thrown out as scrap metal)
- Environment (encased in molten steel) (1)
- Maintenance
03/22/10 - slide 90 G-112 OIG/OI Reactor & Materials Overview PORTABLE GAUGES
03/22/10 - slide 91 G-112 OIG/OI Reactor & Materials Overview SOURCES 8 mCi Cesium-137 (gamma) 40 mCi Americium-241 (Am-Be) (alpha/neutron)
DOSE RATES (approximate) 20 mrem/hr at surface 2 mrem/hr at 1 foot Portable Gauges
03/22/10 - slide 92 G-112 OIG/OI Reactor & Materials Overview Portable Gauges Density Moisture source detector fixed distance source detector
03/22/10 - slide 93 G-112 OIG/OI Reactor & Materials Overview Measure as you go Portable Gauges
03/22/10 - slide 94 G-112 OIG/OI Reactor & Materials Overview Problems
Transportation
Theft
Construction (destruction?)
03/22/10 - slide 95 G-112 OIG/OI Reactor & Materials Overview 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.
03/22/10 - slide 97 G-112 OIG/OI Reactor & Materials Overview END OF GAUGES
03/22/10 - slide 98 G-112 OIG/OI Reactor & Materials Overview END OF INDUSTRIAL