ML20199A831

Provides Listed Info for Hypothetical Accident Condition Testing of Amersham 660 Series Projectors W/Stainless Steel Screws Performed in Dec 1997 Under Test Plan 74

ML20199A831
Person / Time
Site:	07109033
Issue date:	01/09/1998
From:	Mcdaniel W AMERSHAM CORP.
To:	Chappell C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9801280096
Download: ML20199A831 (5)

Text

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-9033 1

SENTINEL 9 Jant$ary 1998 Amersham Corporation 40 North Avenue Burlington, MA 01803 Mr. Cass R. Chappell tel (617) 272-2000 tel (800) 8151383 Office of Nuclear Material Safety and Safeguards fn (617) 273-2216 Nuclear Regulatory Commissien Washington, DC 20555 PAmersham QSA

Dear Mr. Chappell:

As you requested in our telephone call on 6 January 1998, we are providing the following information for Hypothetical Accident Condition Testing of Amersham's 660 Series projectors with stainless steel screws performed in December 1997 under Test Plan 74.

On 23-24 December 1997, four (4) test specimens were subjected to 30 foot drop and puncture tests as specified in Test Plan 74. Based on visual and radiographic inspection, there was n-evidence of fract. ire of the new stainless steel screws and the end plates remained secure. In addition there was no eviderce that torque preload had an effect on the damage to the packages inflicted by the drop and puncture tests.

On 30 December 1997, three (3) of the test specimens that haa been subjected to drop and puncture tests were subjected to the thermal test as specified in our Test Plan 74. The fourth unit Wds not subjected to the thermal test as it was not as severely damaged as the other specimens.

On the next day, the specimens were examined at the thermal test site. We found no visible evidence of uranium oxide outside the specimens. In addition, one of the specimens had cooled to room temperature and the other two specimens bad internal temperatures above 400 C. The specimens were left at the test site to cool naturally. On 2 January 1998, e internal temperature of the specimens was taken and found to be at room temperature. The specimens were then bagged and packaged for transport from the test site to our Burlington site.

Upon receipt in Burlington on 5 January 1998, the specimens were radiographed. The stair.less steel screws remained intact and continued to secure the end plates. There was no significant j

loss of shielding due to oxidation. We noticed that the shields on all three thermally tested units

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were displaced from the positions recorded on radiographs taken after drop and puncture testing.

In all three cases, ali or a significant portion of this displacement was in a plane that was

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7 horizot tal during thermal testing (these units were tested in their normal upright orientation).

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We take this as a strong indication that a portion of this shield movement was due to the handling in transport the specimens received after thermal testip~ was completed.

C C.: 3 9001280096 900109 ff

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Profile results to date show dose output levels at 1 meter from package surface (see enclosed -

- 4.mfiHng data) of:

- 4.7 mR/hr for Specimen D (handle corner drop).

- 9.3 R/hr for Specimen A (bottom edge drop)

-- 2.7 mR/hr fhr 3pecimen B (handle corner drop after 30 foot drop and puncture tests)

It is unclear at this time whether the handling Specimen A received during transport was of

- significant magnitude as to have caused the dose reading to exceed 1 R/hr at I meter. Conclusive 1 analysis of the specimens is ongoing.-

i We are progressing with additional testing and evaluation to determine the condition of the specimens immediately after thermal testing but befbre packaging and eansport. This includes additional drop and puncture testing to be performed on 8-11 January 1998 at Valley Tree in l --

_ Oroveland, MA and thermal testing, with preliminary source position determination prior to l'

handling and shipment, to be performed on 13-15 January at Manufacturing Sciences in Oak-

Ridge, TN.

It is important to note that at this time we are not reporting test failures as a result of testing in accordance with Test Plan 74. We are informing the NRC that due to the potential damage incurred during transport we are repeating the bottom edge drop in Test Plan 74 (at 120 in-lb torque) and performing further assessments of the other units.

Please call me or Greg Field if you have any questions.

4

. Regards, l-William M. McDaniel QSA Operations and Site Manager

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