ML18355A864

Enclosure 1 - RAI (Non-Proprietary) (Letter to P. Narayanan Tn Americas LLC Application for Certificate of Compliance No. 1042, Amendment No. 1, to Nuhoms Eos System (Docket No. 72-1042, CAC No. 001028, EPID: L-2018-LLA-0043) - Request for

ML18355A864
Person / Time
Site:	07201042
Issue date:	12/21/2018
From:	Christian Jacobs Spent Fuel Licensing Branch
To:	Narayanan P TN Americas LLC
Jacobs C J
Shared Package
ML18355A862	List: ML18355A863 ML18355A864
References
CAC 001208, EPID L-2018-LLA-0043
Download: ML18355A864 (10)

Text

Code of Federal Regulations

apacity/demand 1.00 for structure to be satisfied for both overturning and sliding

The NUHOMS EOS System is designed to accommodate pressurized water reactor (PWR) (14x14, 15x15, 16x16 and 17x17 array designs) and boiling water reactor (BWR)

(7x7, 8x8, 9x9 and 10x10 array designs) fuel types and reload assemblies that are available for storage."

The EOS system is designed to store intact pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies (FAs) within the EOS-37PTH dry shielded canister (DSC) and EOS-89BTH DSC, respectively. The transfer casks (TCs)

EOS-TC108 and EOS-TC125/135 are used to transfer the EOS-DSC to the EOS horizontal storage module (EOS-HSM). Normal and off-normal condition, near-field dose rates are presented in this chapter for the EOS-TC and EOS-HSM

The methodology, source terms, and dose rates presented in this chapter are developed to be reasonably bounding for general licensee implementation of the EOS System.

The bounding HLZCs are used for dose rate analysisBased on MCNP scoping calculations, HLZC 4 bounds HLZC 1, and HLZC 4 and HLZC 5 result in similar peak dose rates for the EOS-TC125/135 and EOS-HSM. However, HLZC 4 results in larger average dose rates on the EOS-TC125/135 side surface compared to HLZC 5 because HLZC 4 has the largest heat load in the peripheral zone.

Therefore, HLZC 4 is used in design basis PWR calculations for the EOS-TC125/135 and EOS-HSM. Source terms for HLZC 4 are derived for 1.0 kW/FA in Zone 1 and 1.625 kW/FA in Zones 2 and 3 for a total DSC heat load of 52.0 kW. This bounds the maximum DSC heat load of 50.0

kW

Prior to using ORIGEN-ARP, detailed two-dimensional models of the design basis PWR and BWR FAs are developed in TRITON using the FA design data in Chapter 2. TRITON is used to generate ORIGEN-ARP data libraries as a function of burnup and enrichment. These libraries are collapsed from the ENDF/B-VII 238-group cross section library and are used by ORIGEN-ARP to compute the source terms

The methodology for developing damaged/failed fuel source terms is the same as used for developing intact fuel source terms."

The bounding HLZCs are used for dose rate analysis. Dose rates are generally larger for higher heat loads, and radial dose rates are dominated by fuel in the peripheral regions. For BWR fuel, it is determined by inspection that HLZC 1 is bounding for the EOS-TC125/135 and HLZC 2 is bounding for the EOS-TC108. For PWR fuel, it is also determined by inspection that HLZC 2 is bounding for the EOS-TC108

Control components not explicitly listed herein, but that meet the definition provided above and have similar functional characteristics as those listed above, are also authorized within the DSC. For intact fuel assemblies, a maximum fuel cladding temperature limit of 400 °C (752 °F) has been established for normal conditions of storage and for short-term storage operations such as transfer and vacuum drying [4-1]. During off-normal storage and accident conditions, the fuel cladding temperature limit is 570 °C (1058 °F) [4-1].

The structural analysis for damaged fuel cladding described in Chapter 3 demonstrates that the cladding does not undergo additional degradation under normal and off-normal conditions of storage.