ML19168A065
| ML19168A065 | |
| Person / Time | |
|---|---|
| Site: | 07109383 |
| Issue date: | 06/13/2019 |
| From: | Bernie White Spent Fuel Licensing Branch |
| To: | Christopher Regan Office of Nuclear Material Safety and Safeguards |
| White B | |
| References | |
| EPID L-2019-LRM-0011 | |
| Download: ML19168A065 (5) | |
Text
June 13, 2019 MEMORANDUM TO: Christopher M. Regan, Deputy Director Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards FROM: Bernard White, Senior Project Manager /RA/
Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards
SUBJECT:
SUMMARY
OF FEBRUARY 21, 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 a high-level overview of its corporate organization, operations, and spent fuel management; the CASTOR geo69 transportation package; and the safety basis of the package design.
Background
On February 21, 2019, a partially closed meeting was held in Rockville, Maryland, at the request of GNS 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 February 8, 2019 (see Agencywide Documents Access and Management System (ADAMS) Accession No. ML19045A340). The meeting attendance list is provided as Enclosure No. 1, the non-proprietary presentation slides are located at ADAMS Accession No. ML19050A405, the proprietary presentation slides are located at ADAMS Accession No. ML19050A407.
CONTACT: Bernard H. White, NMSS/DSFM (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 Model No. CASTOR geo69. 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 casted as a monolithic piece of ductile cast iron (cylindrical shell and bottom part) without the need for a weld seam. The package body of iron has radial fins machined on the outside of the package 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.
To be used in the U.S. at nuclear power plants where the crane capacity is 100 metric tons, the CASTOR geo69 system includes a cask loading unit to transfer a canister from the spent fuel pool to the transport package. The canister is fabricated from stainless steel and is closed by a lid that is locked using a bayonet system. The bottom of the cask loading unit is removable to lower the canister into the packaging body. The canister is closed by a bolted lid and welded bottom.
The basket is constructed from an aluminum alloy and will hold up to 69 boiling-water reactor 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. The maximum enrichment and burnup of the BWR fuel assemblies is 4.6 weight percent and 60 GWd/MTU, respectively. The minimum cooling time prior to loading is designed to be 10 years. When the burnup is greater than 45 GWd/MTU, the basket location will utilize and additional boundary to contain the spent fuel.
Gesellschaft für Nuklear-Service mbH briefly discussed its quality assurance program, which it states is based on GNS Integrated Management System is based on the International Organization for Standardization (ISO) 9001, 2015 Edition, Quality management systems -
Requirements. GNS stated that its quality assurance program meets the requirements for quality management (QM) system in accordance with the International Atomic Energy Agency requirements in Specific Safety Requirements No. SSR-6, Regulations for the Safe Transport of Radioactive Material, and with the German regulation BAM-GGR 011 "Quality Assurance Measures of Packagings for Competent Authority Approved Package Designs for the Transport of Radioactive Material." At the meeting, GNS asked about submitting its quality assurance program for NRC review and the appropriate time to do that.
Gesellschaft für Nuklear-Service mbH discussed the safety functions of the package and provided a high-level overview of their evaluations to determine that the package design meets Title 10 of the Code of Federal Regulations Part 71, Packaging and Transportation of Radioactive Material. GNS discussed the half-scale drop tests it performed on similar packages and how the testing will validate the finite element analysis GNS will perform to evaluate the certificate tests. GNS stated that the calculations of drop tests for the safety basis will be verified using data from the scale model drop tests. GNS stated that it has performed over 100 drop tests for different CASTOR casks to validate its calculations for the hypothetical accident condition tests. Structural calculations will be performed using LS DYNA and ANSYS finite element codes.
C. Regan 3 Gesellschaft für Nuklear-Service mbH stated that its thermal evaluation will be performed using ANSYS-Thermal and ANSYS FLUENT codes. The results will be benchmarked with examples from the Sandia benchmarks and temperatures will be compared with measured cask surface temperatures on casks in storage at the storage facility in Gorleben, Germany.
For evaluation of dose rates and criticality safety, GNS stated that it would be using SAS2H and ORIGEN-S from the SCALE 5.1 code system and OBERON and LOAD-CHECK programs by Wissenschaftlich-Technische Ingenieurberatung GmbH. To calculate the dose rates, GNS stated that it plans to use MCNP Version 6 with ENDF/B-VII continuous energy cross section data. To validate its dose rates GNS plans on comparing measured and calculated dose rate values for loaded CASTOR V casks, since they have similar designs.
To evaluate the criticality safety of the package, GNS said it will use the KENO-VI from SCALE 5.1 code system with the 238-group ENDF/B-V cross section data. Self-shielded resonance cross sections will be processed with CENTRM. To benchmark the criticality calculations, GNS will use critical benchmark experiments from, The International Criticality Safety Benchmark Evaluation Project Handbook. GNS stated that it has evaluated numerous critical benchmarks, including those with different absorber materials between the fuel rods.
The NRC staff asked GNS about fracture toughness at the cold temperatures that is evaluated for the cold test for normal conditions of transport in Title 10 of the Code of Federal Regulations, Section 71.71(c)(2). GNS stated that it had evaluated numerous samples taken from the cores of previously fabricated casks. GNS stated that it has a large database of fracture toughness values and correlations between microstructure and strength. GNS stated that at the next pre-application meeting it would present this information to the NRC.
Finally, GNS state that it plans on submitting its application in December 2019 for NRC approval. Prior to the submittal, GNS would like to have another pre-application meeting to discuss its safety analyses in more depth.
Docket No. 71-9383 EPID No. L-2019-LRM-0011
Enclosures:
- 1. Meeting Attendees
C. Regan 4
SUBJECT:
SUMMARY
OF FEBRUARY 21, 2019, MEETING WITH GESELLSCHAFT FÜR NUKLEAR-SERVICE MBH TO DISCUSS THE PROPOSED APPLICATION FOR THE CASTOR GEO69 PACKAGE, DOCUMENT DATE: June 13, 2019 Closes EPID No. L-2019-LRM-0011 DISTRIBUTION:
D. Marcano G:\SFST\Bernie White\Casework\Castor Geo69\Summary for February 21 2019 meeting.docx ADAMS Accession No. ML191658A065 OFC NMSS/DSFM NMSS/DSFM NMSS/DSFM NAME SFigueroa BWhite JMcKirgan Via email DATE 5/10/19 5/13/19 6/13/19 Official Use Only - Proprietary Information
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: February 21, 2015, 1:00 - 4:00 p.m.
NAME AFFILIATION Attendance in person Bernie White NRC/NMSS/DSFM Antonio Rigato NRC/NMSS/DSFM Zhian Li NRC/NMSS/DSFM Roland Hüggenberg GNS Rainer Nring GNS Linus Bettermann GNS Jens Schrder GNS Melissa Mann URENCO USA Richard Goorvich URENCO USA Lionel Antognelli TN Americas JoAnn Ireland NRC/NMSS/DSFM Yong Kim NRC/NMSS/DSFM Chris Allen NRC/NMSS/DSFM Meraj Rahimi NRC/NMSS/DSFM Phone Attendees Jeremy Smith NRC/NMSS/DSFM Ace Hoffman Member of the public Carla Roque-Cruz NRC/NMSS/DSFM Ray Lutz Citizen Oversight Donna Gilmore Member of the public David Tarantino NRC/NMSS/DSFM Carlyn Green Ux Consulting Enclosure 1