ML20174A552

Draft Coc for Magnastor Amendment 9

ML20174A552
Person / Time
Site:	07201031
Issue date:	02/04/2009
From:	John Mckirgan Storage and Transportation Licensing Branch
To:	NAC International
BWhite NMSS/DFM/STL 415.6577
Shared Package
ML20174A550	List: ML20174A551 ML20174A552 ML20174A553 ML20174A554 ML20174A555
References
CoC No. 1031
Download: ML20174A552 (3)

Text

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Page 1 of 3 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 Expiration Date Docket No. Amendment No. Amendment Effective Date Package Identification No.

1031 2/4/2009 2/4/2029 72-1031 9 TBD USA/72-1031 Issued To: (Name/Address)

NAC International Inc.

3930 East Jones Bridge Road Norcross, GA 30092 Safety Analysis Report Title NAC International Inc., Final Safety Analysis Report for the MAGNASTOR System, Docket No. 72-1031 APPROVED SPENT FUEL STORAGE CASK Model No.: MAGNASTOR Description The MAGNASTOR system is certified as described in the safety analysis report (SAR) and in NRCs safety evaluation report (SER) accompanying the certificate of compliance (CoC).

The MAGNASTOR system (the cask) consists of the following components: (1) transportable storage canister (TSC), which contains the spent fuel; (2) concrete cask, which contains the TSC during storage; and (3) a transfer cask, which contains the TSC during loading, transfer and unloading operations. The cask may store up to 37 pressurized water reactor (PWR) fuel assemblies or 87 boiling water reactor (BWR) fuel assemblies. Authorized PWR and BWR contents are specified in Appendix B to this Certificate.

The TSC is the confinement system for the stored fuel. The TSC assembly consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a closure lid, a closure ring, and two sets of redundant penetration port covers. The cylindrical shell plus the bottom plate, closure lid, and welded inner port covers are stainless steel and constitute the confinement boundary. The electroless nickel-coated carbon steel fuel basket is a developed-cell circular cylinder configuration with either 37 PWR or 87 BWR fuel assembly locations. The fuel assembly locations (cells) in the PWR and BWR baskets include neutron absorber panels on up to four sides for criticality control. Each neutron absorber panel is covered by a stainless steel sheet to protect the material during fuel loading and unloading, and to maintain it in position.

The concrete cask is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during long-term storage. The concrete cask is a reinforced concrete (Type II Portland cement) structure with a carbon steel inner liner. The liner inner diameter incorporates standoffs to minimize impact loads on the TSC and to maintain convective heat flow paths under accident conditions. The concrete cask has an

NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. 1031 FOR SPENT FUEL STORAGE CASKS Amendment No. 9 Supplemental Sheet Page 2 of 3 Description (Continued) annular air passage to allow a passive convection air flow around the TSC. The air inlets and outlets are offset in elevation from the TSC to minimize radiation streaming. The spent fuel decay heat is transferred from the fuel assemblies to the TSC shell using pressurized helium circulated by convection through the fuel basket, conduction and radiation. Heat flows by convection from the TSC shell to the circulating air and by radiation from the TSC shell to the concrete cask liner. The heated air is exhausted, by convective flow, through the concrete cask air outlets. The top of the concrete cask is closed by a carbon steel and concrete lid bolted in place.

There are two types of transfer casks. The standard MAGNASTOR transfer cask (MTC) provides shielding during TSC movements between work stations, the concrete cask, or the transport cask. It is a multiwall (carbon steel/lead/NS-4-FR/steel) design with retractable (hydraulically operated) bottom shield doors that are used during loading and unloading operations. The second version of the transfer cask, the MTC2, has stainless steel walls.

Primary difference between the passive MAGNASTOR transfer cask (PMTC) and the standard MTC is that the PMTC contains a demineralized water shield tank instead of NS-4-FR. The PMTC is designed for use in a high ambient temperature environment to passively cool the loaded TSC during transfer operations.

CONDITIONS

1. OPERATING PROCEDURES 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 9 of the SAR.

2. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM Written cask acceptance tests and a maintenance program shall be prepared consistent with the technical basis described in Chapter 10 of the SAR. Metal matrix composites (MMCs), as described in Chapter 10 of the SAR, are limited to 0.5% open porosity, as determined by qualification testing.

This restriction does not apply to neutron absorbing plates constructed from Boral.

3. QUALITY ASSURANCE 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.

4. HEAVY LOADS REQUIREMENTS Each lift of a MAGNASTOR TSC, transfer cask, or concrete cask must be made in accordance with the 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 requirements, if applicable) is required to show operational compliance with existing plant-specific heavy loads requirements.

NRC FORM U.S. NUCLEAR REGULATORY COMMISSION 651A (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. 1031 FOR SPENT FUEL STORAGE CASKS Amendment No. 9 Supplemental Sheet Page 3 of 3

5. APPROVED CONTENTS Contents of the MAGNASTOR system must meet the specifications given in Appendix B to this certificate.

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

7. CHANGES TO THE CERTIFICATE OF COMPLIANCE The holder of this certificate who desires to make changes to the certificate, which includes Appendix A (Technical Specifications and Design Features) and Appendix B (Approved Contents), shall submit an application for amendment of the certificate.

8. AUTHORIZATION The MAGNASTOR system, which is authorized by this certificate, is hereby approved for general use by holders of 10 CFR Part 50 and Part 52 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 and Appendix B.

FOR THE NUCLEAR REGULATORY COMMISSION draft John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Attachments:

1. Appendix A

2. Appendix B Dated: draft