ML19351E143
| ML19351E143 | |
| Person / Time | |
|---|---|
| Site: | 07109387 |
| Issue date: | 12/20/2019 |
| From: | William Allen Storage and Transportation Licensing Branch |
| To: | Christopher Regan Division of Fuel Management |
| W(Chris)Allen NMSS/DFM/STL 415.6877 | |
| Shared Package | |
| ML19351E141 | List: |
| References | |
| EPID: L-2019-LRM-0078 | |
| Download: ML19351E143 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 20, 2019 MEMORANDUM TO: Christopher Regan, Deputy Director Division of Fuel Management Office of Nuclear Material Safety and Safeguards FROM: Chris Allen, Project Manager /RA D.I.Doyle Acting for/
Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
SUBJECT:
SUMMARY
OF DECEMBER 4, 2019, PUBLIC MEETING WITH INDUSTRIAL NUCLEAR COMPANY TO DISCUSS THE NEW RAW MATERIAL SHIPPING CONTAINER PACKAGE
Background
This was a category 1 public meeting between Industrial Nuclear Company (INC), and U.S.
Nuclear Regulatory Commission (NRC) staff to discuss INCs proposed Raw Material Shipping Container package. Regulatory commitments were not made at the meeting. INC provided presentation slides prior to the meeting. The meeting presentation slides are attached as .
MEETING
SUMMARY
On December 4, 2019, NRC staff held a public meeting with INC representatives at the NRCs Two White Flint North Building in Rockville, Maryland. The list of meeting attendees is . The discussion followed the agenda provided in Enclosure 2.
After introductions and opening remarks, INC staff provided a description of the package, the materials used in fabrication, and the proposed contents. During the presentation, INC stated that they planned to develop a shielding model using the Monte Carlo Neutral Particle computer code, which would be validated against dose rate measurements generated using an Iridium-192 source, to determine the maximum allowable quantities of radioactive material presented for transport. INC also explained that portions of the package would be hot due to the proposed decay heat limit. However, they emphasized that the package design would be altered as necessary to meet the regulatory limits. Staff asked several questions about the heat transfer aspects of the package as well as the heat transfer model INC would use to validate the package. Staff encouraged INC to provide input and output computer files with their application as well as provide a thorough description of the package performance under hypothetical accident conditions. The inclusion of a thermal test as a pre-shipment operational step was also
C. Regan discussed. In addition, INC outlined the tests and analyses they planned to perform to demonstrate regulatory compliance. After INC completed its presentation, the meeting was adjourned.
Docket No.: 71-9387 EPID No. L-2019-LRM-0078
Enclosures:
- 1. Meeting Attendees
- 2. Agenda
- 3. Meeting Slides
ML19351E141 (Pkg) ML19351E143 (Ltr)
OFFICE: DFM DFM DFM SFigueroa NAME: WAllen DDoyle via e-mail DATE: 12/11/19 12/11/19 12/20/19 MEETING ATTENDEES NAME AFFILIATION Dan Doyle NRC Chris Allen NRC Jason Piotter NRC Eli Goldfeiz NRC Dave Tarantino NRC Patrick Koch NRC JoAnn Ireland NRC Gary Clark Orano Federal Services Ron Monteforte INC Enclosure 1
AGENDA Meeting between Industrial Nuclear Company (INC) and the Nuclear Regulatory Commission December 4, 2019 1:00 p.m. - 2:30 p.m.
Two White Flint 8-D-30
- Introductions
- Package Description
- Payload Discussion
- Certification Test Plan
- Summary Enclosure 2
Meeting Presentation Slides Enclosure 3