NRC Schedules Webinar to Discuss Safety Performance of Global Nuclear Fuel Plant, page-6

Looking deeper into this, it shows me that this webinar isn't for GNF-A's benefit or for GLE either, they were told of their performance with Criticality inspections back in 2015 at exit meetings on October 13 and November 19
see here https://www.nrc.gov/docs/ML1602/ML16026A580.pdf

What I believe this webinar is all about is informing the public about what has been happening at Wilmington with respect to GNF-A's and GLE's efforts at recycling and handling Special Nuclear Materials for RECYCLING.

I believe the public are about to be told on the 12th April 2017 in the US, just what has been happening at Wilmington for the last six or seven years?
I reckon this is a MEDIA EVENT to inform the public?
If GLE and GNF-A want to continue with this effort and build a Pilot plant to prove that a full scale commercial plant is viable? then I reckon it would be about now that the Public should be informed about what has been happening and what is going to happen in the future? I hope I am right because that would also mean that the reorg is a done deal wouldn't it?

I remember reading just recently that one of the US senators liked the idea of recycling, he also said something about using technology developed at Argonne, he was talking about Pyroprocessing (I did post something on HC to that effect not long ago).

http://citeseerx.ist.psu.edu/viewdoc/download?doi=10.1.1.658.2464&rep=rep1&type=pdf Page 3

ADVANCED FUEL CYCLE STUDIES
A method for recycling used oxide fuel and other forms of
metal fuel involves multiple steps known as electrometallurgical
processing (a.k.a., pyroprocessing). The initial step towards the
recycling process is chopping the spent oxide fuel rods into
smaller pieces and reducing the oxide content, while metal fuel
rods do not need to be reduced. This results in a metallic feed
for the electrorefiner where it is then added to the anode basket
located in a molten salt bath. During the electrorefining, the
uranium and plutonium is transported to a cathode basket while
the fission products and other transuranic elements remain in
the salt bath. The transported metal formations on the cathode
are dendritic and therefore need to be consolidated. The
consolidation occurs in a crucible where the uranium and
plutonium metal is formed into an ingot.
This method is similar to that performed at Argonne National Laboratory [8-9]. The resulting ingot may then be used for potential fabrication of fast
reactor fuel.
The metal dendrite formations and ingots are a criticality
safety concern, which are formed from such processes as
electrorefining, cathode processing, and casting processes.
The MCNP5 modeling of plutonium and uranium metal systems
may be used for preliminary reprocessing batch size analysis
providing insight on component sizing and economics.
As such, a GEH validation of MCNP5 was performed for
uranium and plutonium metal systems to support design studies
relating to reprocessing operations.
A total of 151 critical benchmark experiments were selected to bound expected
parameter ranges. Each experiment was modeled using MCNP5 to determine the effective neutron multiplication factor (keff) of the experiment.
The results were then statistically evaluated and analyzed for trends to determine the USL using the GEH USLSA statistical method. A corresponding set of four AOAs were established, including [10]:

It would not surprise me in the least if a small quantity of recycled Uranium from GLE has already been processed by GNF-A into LEU or even a MOX fuel?