ML23069A232

Attachment 3: HI-STORM 100 Amendment 19 CoC Reorganization

ML23069A232
Person / Time
Site:	Holtec
Issue date:	03/10/2023
From:	Holtec
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML23069A227	List: ML23069A229 ML23069A230 ML23069A231 ML23069A232 ML23069A233 ML23069A234 ML23069A235 ML23069A236 ML23069A237 ML23069A238 ML23069A239 ML23069A240 ML23069A241
References
EPID L-2022-LLA-0028, CoC No. 1014, CAC 001028, 5014959
Download: ML23069A232 (1)

Text

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) CERTIFICATE OF COMPLIANCE 10 CFR 72 FOR SPENT FUEL STORAGE CASKS Page 1 of 4

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 Expiration Docket No. Amendment No. Amendment Effective Date Package Identification No.

Date Date 1014 05/31/00 05/31/20 72-1014 1169 TBD USA/72-1014 Issued To: (Name/Address)

Holtec International Holtec Technology Campus One Holtec Blvd.

Camden, NJ 08104

Safety Analysis Report Title Holtec International Inc.,

Final Safety Analysis Report for the HI-STORM 100 Cask System

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, the attached Appendix A (Inspections, Tests and Evaluations) and Appendix B (Technical Specifications) for aboveground systems except Version E, HI-TRAC MS, MPC-32M, and Version 1 of MPC-32 and MPC-68; the attached Appendix C (Inspections, Tests and Evaluations) and Appendix D (Technical Specifications) for the HI-STORM 100S Version E, HI-TRAC MS, MPC-32M, and Version 1 of MPC-32 and MPC-68M; or the attached Appendix A-100U (Inspections, Tests and Evaluations) and Appendix B-100U (Technical Specifications) for underground systems, and the conditions specified below:

I. Technology

a. Model No.: HI-STORM 100 Cask System

The HI-STORM 100 Cask System (the cask) consists of the following components: (1) interchangeable multi-purpose canisters (MPCs), which contain the fuel; (2) a storage overpack (HI-STORM), which contains the MPC during storage; and (3) a transfer cask (HI-TRAC), which contains the MPC during loading, unloading and transfer operations. The cask stores up to 32 pressurized water reactor fuel assemblies or 68 boiling water reactor fuel assemblies.

The HI-STORM 100 Cask System is certified as described in the Final Safety Analysis Report (FSAR) and in the U.S. Nuclear Regulatory Commissions (NRC) Safety Evaluation Report (SER) accompanying the Certificate of Compliance (CoC).

The MPC is the confinement system for the stored fuel. It is a welded, cylindrical canister with a honeycombed fuel basket, a baseplate, a lid, a closure ring, and the canister shell. All MPC components that may come into contact with spent fuel pool water or the ambient environment are made entirely of stainless steel or passivated aluminum/aluminum alloys such as the neutron absorbers. The canister shell, baseplate, lid, vent and drain port cover plates, and closure ring are the main confinement boundary components. All confinement boundary components are made entirely of stainless steel. The honeycombed basket, which contains neutron absorbing material, provides criticality control.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) CERTIFICATE OF COMPLIANCE Certificate No. 1014 10 CFR 72 FOR SPENT FUEL STORAGE CASKS Amendment No. 16 Supplemental Sheet Page 3 of 4

ii. Construction/Fabrication Alternatives to Codes, Standards, and Criteria

Proposed alternatives to the ASME Code, Sections II and III, 1995 Edition with Addenda through 1997 including modifications to the alternatives allowed by item i may be used on a case-specific basis when authorized by the Director of the Office of Nuclear Material Safety and Safeguards or designee. The request for such alternative should demonstrate that:

1. The proposed alternatives would provide an acceptable level of quality and safety, or

2. Compliance with the specified requirements of the ASME Code,Section III, 1995 Edition with Addenda through 1997, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

b. The NRC has approved an exemption request by the CoC applicant from the requirements of 10 CFR 72.236(f), to allow a Supplemental Cooling System to provide for decay heat removal in accordance with Section 3.1.4 of Appendices B and D.

c. Heavy Loads Requirements

Each lift of an MPC, a HI-TRAC transfer cask, or any HI-STORM overpack must be made in accordance to the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant specific 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. Lifting operations outside of structures governed by 10 CFR Part 50 must be in accordance with Section 4.2 and Sections 2.1.6 and 2.3 (if applicable) of Appendix A.

d. Pre-Operational Testing and Training

i. Dry Run Training Exercise

1. A dry run training exercise of the loading, closure, handling, unloading, and transfer of the HI-STORM 100 Cask 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 MPC. The dry run may be performed in an alternate step sequence from the actual procedures, but all steps must be performed. The dry run shall include, but is not limited to the following:

2. Moving the MPC and the transfer cask into the spent fuel pool or cask loading pool.

3. Preparation of the HI-STORM 100 Cask System for fuel loading.

4. Selection and verification of specific fuel assemblies to ensure type conformance.

5. Loading specific assemblies and placing assemblies into the MPC (using a dummy fuel assembly), including appropriate independent verification.

6. Remote installation of the MPC lid and removal of the MPC and transfer cask from the spent fuel pool or cask loading pool.

7. MPC welding, NDE inspections, pressure testing, draining, moisture removal (by vacuum drying or forced helium dehydration, as applicable), and helium backfilling. (A mockup may be used for this dry-run exercise.)

8. Operation of the HI-STORM 100 SCS or equivalent system, if applicable.

9. Transfer cask upending/downending on the horizontal transfer trailer or other transfer device, as applicable to the sites cask handling arrangement.

10. Transfer of the MPC from the transfer cask to the overpack/VVM.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) CERTIFICATE OF COMPLIANCE Certificate No. 1014 10 CFR 72 FOR SPENT FUEL STORAGE CASKS Amendment No. 16 Supplemental Sheet Page 4 of 4

11. Placement of the HI-STORM 100 Cask System at the ISFSI, for aboveground systems only.

12. HI-STORM 100 Cask System unloading, including flooding MPC cavity, removing MPC lid welds. (A mockup may be used for this dry-run exercise.)

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Dated TBD

Attachments:

1. Appendix A

2. Appendix B

3. Appendix A-100U

4. Appendix B-100U

5. Appendix C

6. Appendix D