ML20027A674
| ML20027A674 | |
| Person / Time | |
|---|---|
| Site: | 07109383 |
| Issue date: | 01/29/2020 |
| From: | Bernie White Storage and Transportation Licensing Branch |
| To: | Christopher Regan Division of Fuel Management |
| White B | |
| References | |
| Download: ML20027A674 (5) | |
Text
January 29, 2020 MEMORANDUM TO: Christopher M. Regan, Deputy Director Division of Fuel Management Office of Nuclear Material Safety and Safeguards FROM: Bernard White, Senior Project Manager /RA/
Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
SUBJECT:
SUMMARY
OF SEPTEMBER 11, 2019, MEETING WITH GESELLSCHAFT FÜR NUKLEAR-SERVICE MBH TO DISCUSS THE PROPOSED APPLICATION FOR THE CASTOR GEO69 PACKAGE Purpose Gesellschaft für Nuklear-Service mbH (GNS) requested the partially-closed meeting to provide to the U.S. Nuclear Regulatory Commission (NRC) staff details of the design of its CASTOR geo69 transportation package, including the safety basis of the package design.
Background
On September 11, 2019, at the request of GNS, a partially closed meeting was held in Rockville, Maryland with the NRC staff to discuss GNS proposed application for the CASTOR geo69 transportation package. The list of meeting attendees, including those participating via telephone, is provided as Enclosure 1.
The meeting was noticed on August 28, 2019 (see Agencywide Documents Access and Management System (ADAMS) Accession No. ML19240B366). The meeting attendance list is provided as Enclosure 1, the non-proprietary presentation slides are located at ADAMS Accession No. ML19281A980, the proprietary presentation slides are located at ADAMS Accession No. ML19281A982.
CONTACT: Bernard H. White, NMSS/DFM (301) 415-6577
C. Regan 2 Discussion The purpose of the meeting was for GNS to present to the NRC its proposed spent fuel transportation package design for the CASTOR geo69 and the preliminary evaluations performed for the safety case. GNS provided the following high-level overview of its company and the proposed package design. The CASTOR geo69 is designed to be a dual-purpose storage cask and transport package. The packaging body is a monolithic piece of ductile cast iron (cylindrical shell and bottom part) without the need for a weld seam. The package body has radial fins machined on the outside of the packaging and holes bored through the longitudinal axis of the body for polyethylene rods for neutron shielding. The package body is closed by a double lid system which includes polyethylene plates for neutron shielding. The package contains impact limiters on the top and bottom, which are constructed of polyurethane foam encased in steel.
The basket is constructed from an aluminum alloy and will hold up to 69 boiling-water reactor (BWR) spent fuel assemblies. The basket contains poison for criticality safety. The BWR fuel assemblies may be loaded into the basket with or without their channels.
During the discussion of the technical evaluations, GNS provided an overview of its preliminary structural, thermal, containment, shielding, and criticality analysis. The structural discussion covered the impact limiters, their material properties and testing program, the preliminary finite element analysis of the 30-foot drop tests, and GNSs evaluation of fracture toughness. GNS discussed the validation using both finite element analysis and testing to verify the impact limiter deformation. In addition, GNS discussed its preliminary evaluation of the puncture test for hypothetical accident conditions.
The thermal evaluation analyzed both homogenous and preferential decay heat loading patterns. Discussion centered on the thermal evaluation along with maximum temperatures of package components, including peak fuel temperatures. GNS also discussed the containment analysis and the expected leakage rate based on the current structural evaluation of the package design.
GNS discussed the source term and shielding evaluation, which, like the thermal evaluation, is based on both homogenous and preferential loading patterns. The source term evaluation is performed using the SCALE system, whereas, dose rate analysis is performed using the Monte Carlo N-Particle Transport computer code. GNS provided estimated dose rates for the proposed loading patterns.
GNS discussed its criticality evaluation which it said utilizes conservative assumptions and is not based on burnup credit or moderator exclusion. GNS discussed the maximum neutron multiplication factor (keff) and how it will include uncertainty into the calculation of maximum keff.
The preliminary criticality evaluation is based on loading fuel assemblies with two different maximum enrichments for the bounding fuel assembly type. The criticality analysis for hypothetical accident conditions will include displacement of fuel assemblies based on an basket deformation resulting from the structural evaluation and any deformation of the fuel assembly. Finally, GNS discussed its approach to benchmarking the criticality evaluation.
C. Regan 3 Finally, GNS state that it plans on submitting its applications in early 2020 for quality assurance program approval and mid-2020 for package approval.
Docket No. 71-9383 EPID No. L-2019-LRM-0061
Enclosure:
Meeting Attendees
C. Regan 4
SUBJECT:
SUMMARY
OF SEPTEMBER 11, 2019, MEETING WITH GESELLSCHAFT FÜR NUKLEAR-SERVICE MBH TO DISCUSS THE PROPOSED APPLICATION FOR THE CASTOR GEO69 PACKAGE DATE: Janaury 28, 2020 Closes EPID No. L-2019-LRM-0061 Distribution: D. Marcano ADAMS Package Number: ML20027A674 *via email OFC NMSS/DFM NMSS/DFM NMSS/DFM NAME *SFigueroa *CMarkley for BWhite Via email DDoyle DATE 12/13/19 12/13/19 1/28/20
MEETING ATTENDEES Meeting
Title:
Pre-application for Model No. CASTOR geo69 transportation package
Participants:
Gesellschaft für Nuklear-Service mbH (GNS) with the U.S. Nuclear Regulatory Commission (NRC)
Date: September 11, 2019 NAME AFFILIATION Attendance in person Bernard White NRC/NMSS/DFM Rainer Nring GNS Michael Nekipelov GNS Dominik Bussman GNS Tobias Fischer-Wasels GNS Benjamin Jech GNS Norman Kent NKent Consulting Jeremy Smith NRC/NMSS/DFM Jimmy Chang NRC/NMSS/DFM John McKirgan NRC/NMSS/DFM John Wise NRC/NMSS/DFM Ricardo Rodrugez NRC/NMSS/DFM Carla Roque-Cruz NRC/NMSS/DFM Zhian Li NRC/NMSS/DFM Meraj Rahimi NRC/NMSS/DFM Yoira Diaz-Sanabria NRC/NMSS/DFM Phone Attendees Antonio Rigato NRC/NMSS/DSFM Brian Gutherman Gutherman Technical Services Enclosure 1