ML21067A168

Proposed Coc No. 1029 Re Tn Americas LLC, Final Safety Analysis Report for the Standardized Advanced NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel

ML21067A168
Person / Time
Site:	07201029
Issue date:	08/06/2021
From:	John Mckirgan Storage and Transportation Licensing Branch
To:	TN Americas LLC
CTMarkley - NMSS/DFM/STL - 301.415.6293
Shared Package
ML21067A164	List: ML21067A166 ML21067A167 ML21067A168 ML21067A169 ML21067A170 ML21067A171 ML21067A172 ML21067A173 ML21067A174 ML21067A175
References
CAC 001028, EPID L-2019-RNW-0014
Download: ML21067A168 (5)

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 and High-Level Radioactive 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 (Certificate)

Expiration Date Docket No.

Amendment No.

1029 02/05/2003 02/05/2023 72-1029 0

Amendment Effective Date N/A Package Identification No.

USA/72-1029 Renewed Effective Date mm/dd/2021 Renewed Expiration Date 02/05/2063 Revision No 0

Revision Effective Date N/A Issued To: (Name/Address)

TN Americas LLC 7160 Riverwood Drive, Suite 200 Columbia, MD 21046 Safety Analysis Report Title TN Americas LLC, Final Safety Analysis Report for the Standardized Advanced NUHOMS 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 No. Standardized Advanced NUHOMS-24PT1 The two digits refer to the 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

b. Description The Standardized Advanced NUHOMS System is certified as described in the Final Safety Analysis Report (FSAR) and in the U. S. Nuclear Regulatory Commissions (NRCs) Safety Evaluation Report (SER). The Standardized Advanced NUHOMS System is a horizontal canister system composed of a steel dry shielded canister (DSC), a reinforced concrete advanced horizontal storage module (AHSM), and a transfer cask (TC). The Standardized Advanced NUHOMS is similar to the Standardized NUHOMS except that it has been enhanced to withstand high seismic spectra and to reduce radiological doses. 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 Building to/from the AHSM.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Supplemental Sheet 1029 0, Rev. 1 Certificate No.

Amendment No.

Renewed Yes Page 2

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1.b. Description (continued)

The principal component subassemblies of the DSC are the shell with integral bottom cover plate and shield plug and ram/grapple ring, top shield plug, top cover plate, and basket assembly. The shell length is fuel-specific. The internal basket assembly is composed of guide sleeves, support rods, and spacer disks. This assembly is designed to hold 24 PWR fuel assemblies. 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 AHSM and back without undue galling, scratching, gouging, or other damage to the sliding surfaces.

The AHSM is a reinforced concrete unit with penetrations located at the top and front for air flow.

The penetrations are protected from debris intrusions by wire mesh screens during storage operation. The DSC Support Structure, a structural steel frame with rails, is installed within the AHSM module to provide for sliding the DSC in and out of the AHSM and to support the DSC within the AHSM. AHSMs are arranged in arrays to minimize space and maximize self-shielding.

Adjacent AHSMs are keyed and tied to provide maximum resistance to environmental conditions including high seismic loads.

The TC is used for transfer operations within the Spent Fuel Pool Building and for transfer operations to/from the AHSM. The TC is a cylindrical vessel with a bottom end closure assembly and a bolted top cover plate. 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 Building. The lower trunnions, located near the base of the cask, serve as the axis of rotation during downending/

uprighting operations and as supports during transport to/from the Independent Spent Fuel Storage Installation (ISFSI).

With the exception of the TC, fuel transfer and auxiliary equipment necessary for ISFSI operations are not included as part of the Standardized Advanced NUHOMS 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 Standardized Advanced NUHOMS System are contained in Section 1 of the SAR.

d. Basic Components The basic components of the Standardized Advanced NUHOMS System that are important to safety are the DSC, AHSM, and TC. These components are described in Section 2.5 and Table 2.5-1 of the SAR.

Written operating procedures shall be prepared for cask handling, loading, movement, surveillance, and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 8 of the SAR.

2. OPERATING PROCEDURES

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Supplemental Sheet Written cask acceptance tests and maintenance program shall be prepared consistent with the technical basis described in Chapter 9 of the SAR.

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

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 existing plant-specific heavy loads requirements.

Contents of the Standardized Advanced NUHOMS System must meet the fuel specifications description as provided in the Appendix to this certificate.

Features or characteristics for the site, cask, or ancillary equipment must be in accordance with the Appendix to this certificate.

A dry run training exercise of the loading, closure, handling, unloading, and transfer of the Standardized Advanced NUHOMS System shall be conducted by the licensee prior to the first use of the system to load spent fuel assemblies. The training exercise shall not be conducted with spent fuel in the canister. The dry run may be performed in an alternate step sequence from the actual procedural guidelines in Chapter 8 of the SAR. The dry run shall include but not be limited to the following:

3. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM

4. QUALITY ASSURANCE

5. HEAVY LOADS REQUIREMENTS

6. APPROVED CONTENTS

7. DESIGN FEATURES

8. PRE-OPERATIONAL TESTING AND TRAINING EXERCISE 1029 0, Rev. 1 Certificate No.

Amendment No.

Renewed Yes Page 3

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

a. DSC retrieval from AHSM

b. Flooding of DSC

c. Opening of DSC 9.

UFSAR UPDATE FOR RENEWED COC The CoC holder shall submit an updated final safety analysis report (UFSAR) to the Commission, in accordance with 10 CFR 72.4, within 90 days of the effective date of the CoC renewal. The UFSAR shall reflect the changes resulting from the review and approval of the CoC renewal. The CoC holder shall continue to update the UFSAR pursuant to the requirements of 10 CFR 72.248.

72.212 EVALUATIONS FOR RENEWED COC USE Any general licensee that initiates spent fuel dry storage operations with the Standardized Advanced NUHOMS Horizontal Modular Storage System after the effective date of the CoC renewal, and any general licensee operating a Standardized Advanced NUHOMS Horizontal Modular Storage System as of the effective date of the CoC renewal, including those that put additional storage systems into service after that date, shall:

a. as part of the evaluations required by 10 CFR 72.212(b)(5), include evaluations related to the terms, conditions, and specifications of this CoC amendment as modified (i.e.,

changed or added) as a result of the CoC renewal;

b. as part of the document review required by 10 CFR 72.212(b)(6), include a review of the UFSAR changes resulting from the CoC renewal and the NRC Safety Evaluation Report related to the CoC renewal; and

c. ensure that the evaluations required by 10 CFR 72.212(b)(7) and (8) capture the evaluations and review described in (a.) and (b.) of this CoC condition.

The general licensee shall complete Condition 10 prior to entering the period of extended operation or no later than one year after the effective date of the CoC renewal, whichever is later.

11. AMENDMENTS AND REVISIONS FOR RENEWED COC All future amendments and revisions to this CoC shall include evaluations of the impacts to aging management activities (i.e., time-limited aging analyses and aging management programs) to ensure that they remain adequate for any changes to SSCs within the scope of the CoC renewal.

1029 0, Rev. 1 Certificate No.

Amendment No.

Renewed Yes Page 4

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10.

PRE-OPERATIONAL TESTING AND TRAINING EXERCISE (continued)

Loading Operations

a. Fuel Loading

b. DSC sealing, drying, and backfilling operations

c. TC downending and transport to the ISFSI

d. DSC transfer to the AHS 8.

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

A. Technical Specifications Dated: Month NN, 2021 1029 0, Rev. 1 Certificate No.

Amendment No.

Renewed Yes Page 5

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12.

USE OF COC 1004 TRANSFER CASKS General licensees shall not use the OS197, OS197H, and the OS200FC TCs aged 20 years or more to perform the TC functions described in the Standardized Advanced NUHOMS System UFSAR after the PEO for CoC 1004 ends.

INITIAL TERM Any Standardized Advanced NUHOMS System loaded up to and including those loaded on February 5, 2023, shall be considered loaded during the initial CoC term.

AUTHORIZATION The Standardized Advanced NUHOMS 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, and the attached Appendix A.

13.

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