ML20247E631
| ML20247E631 | |
| Person / Time | |
|---|---|
| Issue date: | 10/10/1980 |
| From: | Wright E NRC |
| To: | Guinn P NRC |
| Shared Package | |
| ML20244B089 | List: |
| References | |
| SSD, NUDOCS 9805180405 | |
| Download: ML20247E631 (6) | |
Text
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DISTRIBUTION ECWright October 10, 1980 NMSS R/F FC Central File MCPB R/F 80-63 l
MEMORANDUM FOR:
Paul Guinn Material Licensing Branch FROM:
Earl G. Wright Material Certification and Procedures Branch
SUBJECT:
HEALTH AND SAFETY REVIEW: G-M CUSTOM GAUGING DEVICE 1.
Manufacturer 2.
Model Designation General Motors Corp.
Gamma Ray Parts Present Detection System h
3.
Manufacturer & Model No.
4.
Isotope & Maximum Activity of Sealed Source Amersham Corporation Americium-241, 100 millicuries Model #1CL p3.r source housing 5.
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This device is for use in an automatic, on-line system to inspect automobile assemblies for the presence of welded components such as seat belt anchor plates.
6.
Source Housing Description The Am-241 sealed source will be contained in a tungsten / steel source holder enclosed in a steel housing and secured to a frame support. This housin8 contains an electrically operated shutter mechanica (Kevex Co. Model 9401) which is controled by a micro-proceuor sequenced with assembly line operation. The shutter mechanism is equipped with a spring to return the device to the closed position in the event of power failure.
In the event of total l
shutter failure the hinged steel and lead safety lid can be closed manually and secured by padlocking.
(See drawing attachment #5 to application).
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Licensing and/or other Considerations These devices are for distribution only to licensed General Motors Assembly Plants.
The Model AMCL sealed source shall be installed in the source housing, serviced and maintained only by the Amersham Corp.,
or other persons specifically licensed to perform these services.
Installation, initial radiation survey, field operational shutter tests, and removal of device from service shall be performed only by the GM Corporate Industrial Radiation Safety Group (License # 21-12535-01).
Training of Users:
The GM Industrial Radiation Safety Group shall provide a training program to all responsible This training which shall be acceptable to the licensing authority.
users.
Leak Testing: The device shall be leak tested at six month intervals using procedures capable of detecting 0.005 uci of
' removable contamination.
Each device shall be labeled in accordance with the requirements of 10 CFR 20.203 [according to statements provided by Mr. John Bozymowski (313) 575-0970 in a telephone conversation with Earl' Wright on 10/08/80. The label will be provided by the g
Amersham Corp., and will meet these requirements).
8..
Safety Evaluation Summary Based on the information provided by General Motors Corp., in application dated June 24, 1980 and clarifying information provided by Mr. John Bozymowski in a telephone call with the undersigned dated 10/08/80, we consider the device identified in Paragraphs 1 through 6 above to be acceptable for licensing with the limitations specified in Paragraph 7.
Basic Considerations are as follows:
A.
This device has been designed for use only in GM Fisher Body Plants and will be used under the general radiological safety supervision of the GM Corporate Radiation Safety Group (License #21-12535-01).
In my telephone discussions with John Bozymowski on 10/08/80, he informed me that NRC's regional office has already licensed 6 plants for these devices and that they intend to distribute only 1 more unit and that is to the West Mifflin, Pa., location.
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80-63 B.
Radiation levels at 4 feet from the device are specified in the GM Survey Report to be 0.2 mr/hr or less.
Since the source housing V
will be used inside a protective enclosure and the nearest person J
will be at least 6 ft. sway (attach 2 to the application) during i
use of the device, we conclude that personnel exposures can easily l
be maintained within part'20 limits.
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Abnormal Conditions:
Mr. Bozymowski also informed me that there exista little I
likelihood for fire or explosion involving this unit. The materials being examined in the device are raw steel and no excess heating or painting operation are involved. Thus a low probability for fire or explosion is expected.
If damange to the device shielding were to result in completed loss of shielding the expected dose rate from a 100 mei Am-241 source would be about 200 mr/hr at 5 cas.
(Estimate based on information provided by Amersham Corporation.) Even if this occurs one would not expect personnel to be exposed in excess of Part-20 limits.
Furthermore, since the americium in the AMCL source is in the form of a fused ceramic sealed in stainless steel, temperatures in excess of 1000*C would be required to release radioactivity. We do not believe that temperatures in this ran8e are a credible possibility for the expected use of the device.
Thus the potential for failure of the sealed source encapsulation, with resulting internal exposure of personnel, is considered to be extremely unlikely.
a Earl G. Wright Material Certification and Procedures Branch l
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