Letter Sequence Other |
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EPID:L-2018-LLA-0219, Package: Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035) (Open) |
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MONTHYEARML18360A2362018-12-21021 December 2018
Letter to R. Boyle Request for Additional Information for Review of the Revalidation of the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035)(w/Enclosure)
Project stage: RAI
ML19213A0372019-08-0101 August 2019
Letter to R. Boyle Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035) (W/Enclosure 1)
Project stage: Other
ML19213A0352019-08-0101 August 2019
Package: Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035)
Project stage: Request
ML19213A0362019-08-0101 August 2019
Enclosure 2: Certificate from Competent Authority (Letter to R. Boyle Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035))
Project stage: Other
2018-12-21
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Category:Letter
MONTHYEARML23159A0032023-06-14014 June 2023
Transmittal Letter - Request for Additional Information for Japanese Certificate of Competent Authority No. J/2045/B(U)F, Model No. JRC-80Y-20T Package, Revalidation Request (Docket No. 71-3035)
ML23115A3202023-05-0101 May 2023
Application for the Japanese Certificate of Competent Authority No. J/2045/B(U)F, Revision 14, Model No. Jrc-80y-20t - Accepted for Review - Cost Activity Code/Enterprise Project Identification Number (CAC 001794/EPID L-2023-DOT-0006)
ML23115A0742023-04-0303 April 2023
Transmittal Letter from R. Boyle (DOT) to Dfm Director (Nrc), Request for Revalidation Recommendation for the Model No. JRC-80Y-20T (J/2045/B(U)F)
ML23115A0862023-04-0303 April 2023
Enclosure 2-1 - Safety Analysis Report for the Japanese Certificate of Competent Authority Model No. JRC-80Y-20T (J/2045/B(U)F) (English)
ML23115A0842023-04-0303 April 2023
Enclosure 3-1 - Summary of Change of SAR for Model No. JRC-80Y-20T (J/2045/B(U)F) (Non-Proprietary)
ML23115A0822023-04-0303 April 2023
Enclosure 4-1, Comparison Table of the 2019 Safety Evaluation Report (SAR) (J/61/B(U)F-96) and the 2023 SAR (J/2045/B(U)F) for the Model No. JRC-80Y-20T (Non-Proprietary)
ML23115A0792023-03-0303 March 2023
Transmittal Letter from Edlow International Company to the U.S. DOT, Application for Validation of the Model No. JRC-80Y-20T Package (J/2045/B(U)F)
ML23115A0812023-02-15015 February 2023
Enclosure 5, Revision 0, Japan Atomic Energy Agency, Statement of Proprietary Information, Revalidation Application for the Japanese Mode No. JRC-80Y-20T Package (J/2045/B(U)F)
ML23115A0802019-08-16016 August 2019
U.S. Certificate of Competent Authority USA/0208/B(U)F-96, Revision 13 (Japanese Certificate J/61/B(U)F-96), Expired May 28.2022
ML19213A0372019-08-0101 August 2019
Letter to R. Boyle Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035) (W/Enclosure 1)
ML23115A0782019-08-0101 August 2019
Safety Evaluation Report (SER) for Revision 13 of the Certificate of Competent Authority Issued by the U.S. DOT, Model No. JRC-80Y-20T
ML18360A2362018-12-21021 December 2018
Letter to R. Boyle Request for Additional Information for Review of the Revalidation of the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035)(w/Enclosure)
2023-06-14
[Table view]
Category:Safety Evaluation Report
MONTHYEARML19213A0372019-08-0101 August 2019
Letter to R. Boyle Certificate of Approval No. J/61/B(U)F-96, Revision 3, for the Model No. JCR-80Y-20T Packaging (Docket No. 71-3035) (W/Enclosure 1)
2019-08-01
[Table view] |
Text
1.1Package Description ....................................................................................................... 12.1Description of Structural Design and Analysis ................................................................ 22.2Weights and Centers of Gravity ...................................................................................... 22.3Evaluations ...................................................................................................................
.. 22.4Evaluation Findings ........................................................................................................ 34.1Description of the Thermal Design ................................................................................. 44.2Thermal Evaluation under Normal Conditions of Transport and Hypothetical Accident Conditions ....................................................................................................................
................. 44.3Evaluation Findings ........................................................................................................ 46.1Shielding Design .............................................................................................................
56.2Shielding Evaluation ....................................................................................................... 56.3Evaluation Findings ........................................................................................................ 97.1Description of Criticality Design ...................................................................................... 97.2Spent Nuclear Fuel Contents ......................................................................................... 97.3General Consideration for Criticality Safety .................................................................. 107.4Demonstration of Maximum Reactivity ......................................................................... 107.5Evaluation Findings ...................................................................................................... 11
1.1 Package Description
2.1 Description of Structural Design and Analysis 2.2 Weights and Centers of Gravity 2.3 Evaluations
2.4 Evaluation Findings
4.1 Description of the Thermal Design 4.2 Thermal Evaluation under Normal Conditions of Transport and Hypothetical Accident Conditions
4.3 Evaluation Findings
6.1 Shielding Design 6.2 Shielding Evaluation
526 523 527 (for non-exclusive use packages) 652 (for Type B(U) packages) 648(b) (under NCT) 659(b)(1)
Gamma Source Term
.
Neutron Source Term.
drain hole
(
6.3 Evaluation Findings
7.1 Description of Criticality Design 7.2 Spent Nuclear Fuel Contents 501(c) 525 673 680 682 685 686
7.3 General Consideration for Criticality Safety
7.4 Demonstration of Maximum Reactivity
7.5 Evaluation Findings