ML18143B674
| ML18143B674 | |
| Person / Time | |
|---|---|
| Site: | 07103091 |
| Issue date: | 11/16/2017 |
| From: | Fulford G Nordion |
| To: | Boyle R, John Vera Spent Fuel Licensing Branch, US Dept of Transportation (DOT) |
| Garcia-Santos N | |
| Shared Package | |
| ML18143B680 | List: |
| References | |
| Download: ML18143B674 (3) | |
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2 Q1 Nordion to provide a summary (paragraph) of the measurements and tolerances of the DU shielding and Stainless Steel cladding around the UK201.
R1. Minimum and maximum tolerance information is provided in the table below for the main material shielding thicknesses of the F-522/UK-201/F248X transport package. The dimensions are for the thickness of individual materials in the radial direction as it provides the least shielding compared to the top and bottom directions as shown in Appendix 4 of the IS/TR 2650 F522 Engineering Assessment.
The following dimensions are ordered from the center of the package to the outer surface.
Component Dimension Minimum (mm)
Maximum (mm)
Material F248X Leakproof Insert Wall Thickness Stainless Steel UK-201 Shielding Vessel Inner Sleeve Thickness Stainless Steel Shielding Thickness Depleted Uranium Outer Shell Thickness Stainless Steel F-522 Overpack Inner Shell Stainless Steel Foam Polyurethane Foam Outer Shell Stainless Steel Q2. NRC to follow up on Microshield 10.0 capability.
R2. Nordion confirms that the settings in Microshield 10.0 where left in their default state for the flux to dose rate conversion factors.
Q3. Nordion to provide additional information on how we determine I-132 equivalency R3. As previously discussed, the process for Mo-99 production is currently being developed. As we continue to refine the process further studies will be performed to characterize the impurities within the shipments. The most notable impurities when considering shielding will likely include in varying activity levels. Prior to the initial shipments, Nordion will evaluate the content characterization to ensure it is consistent with the approved contents on the transport certificate.
Note: Nordion has previous experience with a similar process as we developed an historic process for Mo-99 production from HEU material that required similar characterization prior to shipment approval.
In terms of A2 equivalencies, we fully expect the Mo-99 contribution will be by far the largest contribution
). For labeling and shipping purposes, the dominant isotope will be Mo-99.
To ensure that impurities within the transport package are below the proposed I-132 1850 GBq equivalent dose, a method involving dose measurements will be performed on the container before shipment. See the following process steps:
3 Q4. Nordion to provide a summary of actual data from target irradiations to provide information on Rb target variability.
R4. Please see the table below for activity data for recent shipments of Sr-82/Rb-82 targets as shipped. This data is representative of targets shipped between November, 2016 and April, 2017.
Please note that the values in the table below do not represent actual shipments but instead show the range of individual isotopes found within separate shipments.