ML19213A037

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)

ML19213A037
Person / Time
Site:	07103035
Issue date:	08/01/2019
From:	John Mckirgan Spent Fuel Licensing Branch
To:	Boyle R US Dept of Transportation (DOT)
Garcia-Santos N
Shared Package
ML19213A035	List: ML19213A036 ML19213A037
References
EPID L-2018-LLA-0219, JCR-80Y-20T
Download: ML19213A037 (16)

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

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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