United States Nuclear Regulatory Commission - Protecting People and the Environment

ACCESSION #: 9502020119

                                                  SENTINEL

                                                  Amersham Corporation
                                                  40 North Avenue
                                                  Burlington, MA 01803
                                                  tel (617) 272-2000
                                                  tel (800) 225-1383
                                                  fax (617) 273-2216

26 January 1995

Document Control Desk
U.S. Nuclear Regulatory Commission
Washington, DC 20555                              Amersham 
                                                  QSA
Dear Sir or Madam:

Amersham is providing additional information concerning a report on a
potential Part 21 defect that was reported to you on 14 November 1994.

We have performed the additional testing and analysis as described in our
letter dated 14 November 1994 with the following results.  We performed a
design/tolerance study of the parts to assure appropriateness of design
and conducted a detailed dimensional inspection of the source/drive cable
connector components to obtain actual tolerance information.  This
tolerance study also included the effects of possible distortion of the
S-tube due to pouring of the shield.  These investigations revealed that
there was nothing in the design even in a worst case buildup of the
tolerances that could create enough of an interference to create a source
hangup or binding situation.

We have also performed cycle testing of the model 680BE SN 124 to
determine if the hangup would be recreated.  The model 680BE was cycle
tested 1054 with no hangups or unusual findings.  The system was fully
operational at the conclusion of the cycle testing.

As a result of these findings, we have not found any evidence of a
manufacturing or design defect, therefore we have concluded there is not
a Part 21 defect in the 680 or the associated equipment used in
conjunction with this 680 device.

I trust this provides adequate information to close out the Part 21
interim report on this device.  Please contact me if you require any
additional information.

Sincerely,


Cathleen Roughan
Radiation Safety Officer


cc:  Mr. Francis Costello
     U.S. Nuclear Regulatory Commission
     Region I
     475 Allendale Road
     King of Prussia, PA 19406

     Mr. Steve Baggett
     Sealed Source Safety Section
     Source Containment and Devices Branch 
     Division of Industrial and Medical Safety, NMSS
     U.S. Nuclear Regulatory Commission
     1 White Flint North
     11555 Rockville Pike
     Rockville, Maryland 20852


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