ML21125A105

2. Proposed CoC No. 1042 Amendment 2 for Tn Americas, LLC

ML21125A105
Person / Time
Site:	07201042
Issue date:	08/03/2021
From:	John Mckirgan Storage and Transportation Licensing Branch
To:	TN Americas LLC
CJJacobs NMSS/DFM/STL 301.415.6825
Shared Package
ML21125A103	List: ML21125A104 ML21125A105 ML21125A106 ML21125A107
References
CAC 001028, EPID L-2019-LLA-0078
Download: ML21125A105 (4)

Text

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Page 1

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The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-related Greater than Class C Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the final safety analysis report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.

Certificate No.

Effective Date Expiration Date Docket No.

Amendment No.

Amendment Effective Date Package Identification No.

1042 6/7/2017 6/7/2037 72-1042 2

TBD USA/72-1042 Issued To: (Name/Address)

TN Americas LLC 7160 Riverwood Drive, Suite 200 Columbia, Maryland 21046 Safety Analysis Report Title TN Americas LLC, Safety Analysis Report for the NUHOMS EOS Horizontal Modular Storage System for Irradiated Nuclear Fuel CONDITIONS This certificate is conditioned upon fulfilling the requirements of 10 CFR Part 72, as applicable, the attached Appendix A (Technical Specifications), and the conditions specified below:

1. CASK:

a. Model Nos. NUHOMS EOS-37PTH, -89BTH, and 61BTH Type 2 DSCs The two digits refer to the maximum number of fuel assemblies stored in the dry shielded canister (DSC), the character P for pressurized water reactor (PWR) or B for boiling water reactor (BWR) is to designate the type of fuel stored, and T is to designate that the DSC is intended for transportation in a 10 CFR Part 71 approved package. The character H refers to designs that are also qualified for fuel with burnup greater than 45 GWd/MTU.

b. Description The NUHOMS EOS System is certified as described in the safety analysis report (SAR) and in the NRCs safety evaluation report (SER). The NUHOMS EOS System is a horizontal canister system composed of a steel dry shielded canister (DSC), a reinforced concrete horizontal storage module (HSM), and a transfer cask (TC). The welded DSC provides confinement and criticality control for the storage and transfer of irradiated fuel. The concrete module provides radiation shielding while allowing cooling of the DSC and fuel by natural convection during storage. The TC is used for transferring the DSC from/to the spent fuel pool area to/from the HSM and provides radiation shielding during these operations.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Certificate No.

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The principal component subassemblies of the DSC are the shell with bottom cover plates and bottom shield plug, or bottom forging assembly, ram/grapple ring, top shield plug, top cover plates, and basket assembly. The shell is a welded stainless or duplex steel sealed container with a length that is fuel-specific. The internal basket assembly for the EOS-37PTH and EOS-89BTH DSCs is composed of interlocking slotted plates to form an egg-crate like structure that forms a grid of fuel compartments to house the fuel assemblies. The grid structure is composed of one or more of the following: a steel plate, an aluminum plate and a neutron absorber plate. Basket transition rails, made of aluminum, provide the interface between the rectangular basket structure and the cylindrical DSC shell. The DSC is designed to hold either 37 PWR or 89 BWR fuel assemblies.

The 61BTH Type 2 DSC consists of the DSC shell assembly (cylindrical shell, canister bottom and top cover plates and shield plug assemblies) and a basket assembly. Top grid assemblies have been provided to accommodate hoist ring designs. The transition rails support the fuel assemblies and transfer mechanical loads to the DSC shell. The DSC is designated to hold up to 61 BWR fuel assemblies.

Different DSC basket configurations are provided for the EOS-37PTH DSC, with poison plates containing a borated metal matrix composite (MMC) at differing B-10 concentrations. The EOS-89BTH DSC has basket configurations that differ in the material used for the poison plates, either borated MMC or Boral, and the concentration of B-10 used.

The 61BTH Type 2 DSC is designated to use one of three types of poison materials in the basket:

Borated Aluminum alloy, Boron Carbide/Aluminum MMC or Boral.

The basket assembly aids in the insertion of the fuel assemblies, enhances subcriticality during loading operations, and provides structural support during a hypothetical drop accident. The DSC is designed to slide from the transfer cask into the HSM and back.

The HSM is a reinforced concrete unit and is designed to store DSCs with up to 50.0 kW decay heat.

The HSM has variable lengths to accommodate the range of DSC lengths. There are multiple versions of the HSM, the NUHOMS EOS-HSM (EOS-HSM) and the NUHOMS MATRIX HSM (HSM-MX).

When used without distinction, the term HSM refers to the EOS-HSM as well as the HSM-MX.

Because they are geometrically the same design overall, the term EOS-HSM refers to a single module for storage of a single DSC as a single unit (EOS-HSM) or as a split base unit (EOS-HSMS). Only the fabrication details differ. The HSM-MX is an alternate design with a two-tiered, staggered, high-density module, which contains multiple compartments to accommodate multiple DSCs.

The TC is designed and fabricated as a lifting device to meet NUREG-0612 and ANSI N14.6 requirements. It is used for transfer operations within the spent fuel pool area and for transfer operations to/from the HSM. The TC is a multi-walled cylindrical vessel, comprised of a gamma shield and neutron shield layers with a bottom end closure assembly and a bolted top cover plate. There are multiple versions of the TC. The EOS-TC system consists of the EOS-TC135 cask, the EOS-TC125 cask, and the EOS-TC108 cask. The EOS-TC108 is designed with a removable neutron shield for use at nuclear plant sites with space limitations and/or crane capacity limits. Two upper lifting trunnions are located near the top of the cask for downending/uprighting and lifting of the cask in the spent fuel pool area. The lower trunnions, located near the base of the cask, serve as the axis of rotation during downending/uprighting operations and as supports during transfer to/from the independent spent fuel storage installation (ISFSI).

The OS197 transfer cask is used to transfer the 61BTH Type 2 DSC to the HSM-MX. The OS197 includes the OS197H and OS197FC-B variants as described in the TS. The maximum loaded weight for the OS197 TCs and OS197H TCs is 110 tons and 125 tons, respectively.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Certificate No.

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With the exception of the TC, fuel transfer and auxiliary equipment necessary for ISFSI operations are not included as part of the NUHOMS EOS System referenced in this certificate of compliance (CoC).

Such site-specific equipment may include, but is not limited to, special lifting devices, the transfer trailer, and the skid positioning system.

c. Drawings The drawings for the NUHOMS EOS System are contained in Section 1.3, Section A.1.3, and Section B.1.3 of the SAR.

d. Principal Components The principal components of the NUHOMS EOS System that are important to safety are the DSC, HSM, and TC. These components are described in Section 2.1, Section A.2.1, and Section B.2.1 of the SAR.

2. OPERATING PROCEDURES Written operating procedures shall be prepared for handling, loading, movement, surveillance and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 9, Chapter A.9, and Chapter B.9 of the SAR.

3. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM Written cask acceptance tests and maintenance program shall be prepared consistent with the technical basis described in Chapter 10, Chapter A.10, and Chapter B.10 of the SAR.

4. QUALITY ASSURANCE Activities in the areas of design, purchase, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and components, and decommissioning shall be conducted in accordance with a quality assurance program that satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and that is established, maintained, and executed with regard to the cask system.

5. HEAVY LOADS REQUIREMENTS Each lift of a DSC and TC must be made in accordance with the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant-specific safety review (under 10 CFR 50.59 or 10 CFR 72.48, if applicable) is required to show operational compliance with NUREG-0612 and or existing plant-specific heavy loads requirements.

If a single failure proof crane is not used, the licensee must evaluate the accidental drop of the shielding components of the TC under 10 CFR 50.59, 10 CFR 72.48, and 10 CFR 72.212, and evaluate the consequences of the accident drops.

6. APPROVED CONTENTS Contents of the NUHOMS EOS System must meet the fuel specifications in Appendix A (Technical Specifications).

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Certificate No.

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7. DESIGN FEATURES Features or characteristics for the site, or cask system must be in accordance with Appendix A (Technical Specifications).

8. CHANGES TO THE CERTIFICATE OF COMPLIANCE The holder of this certificate who desires to change the certificate or technical specifications shall submit an application for amendment of the certificate or technical specifications.

9. PRE-OPERATIONAL TESTING AND TRAINING EXERCISE A dry run training exercise of the loading, closure, handling, unloading and transfer of the NUHOMS EOS System shall be conducted by each licensee prior to the first use of the system to load spent nuclear fuel assemblies. The training exercise shall not be conducted with spent nuclear fuel in the canister. The dry run may be performed in an alternate step sequence from the actual procedural guidelines in Chapter 9, Chapter A.9, and Chapter B.9 of the SAR. The dry run shall include, but need not be limited to the following:

Loading Operations

a. Fuel loading

b. DSC sealing, drying and backfilling operations

c. TC downending and transfer to the ISFSI

d. DSC transfer to the HSM Unloading Operations

e. DSC retrieval from the HSM

f.

Opening of the DSC

g. Flooding of the DSC Any of the above steps can be omitted if the site has already successfully loaded a NUHOMS EOS System or another NUHOMS system.

10. AUTHORIZATION The NUHOMS EOS System, which is authorized by this certificate, is hereby approved for general use by holders of 10 CFR Part 50 licenses for nuclear reactors at reactor sites under the general license issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, this certificate, and the attached Appendix A.

FOR THE NUCLEAR REGULATORY COMMISSION John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards

Attachment:

Appendix A. Technical Specifications Dated: TBD