Archived Web Page: Draft Regulatory Document RD-364Joint Canada - United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages

F. APPLICATION CONTENT GUIDANCE

1.0 GENERAL INFORMATION

This section of the application should present an introduction and a general description of the package. The applicant should also specify that the application is intended to meet the regulatory requirements of the CNSC regulations, namely the PTNS Regulations which refer to IAEA TS-R-1, 1996 (Revised), and the NRC’s 10 CFR Part 71. As indicated in this guide, the application should demonstrate that the package meets the more stringent of the two. In the following text, shaded boxes identify the more stringent requirements where there are significant differences. If the approval is only sought for one of the two countries, this guide may not apply.

The purpose of the application should be clearly stated. The application may be for approval of a new design, for modification of an approved design, or for renewal of an existing approval. Applications for a new design should be whole and complete and should contain the information required in Subpart D, Application for Package Approval, of 10 CFR Part 71 and Section VI of TS-R-1 which is referenced in Subsection 1(4) of the PTNS Regulations, as applicable.

Applications for modification of an approved design should clearly identify the changes being requested. Modifications may include design changes, changes in authorized contents, or changes in conditions of the approval. Design changes should be clearly identified in revised packaging drawings. The application should include an assessment of the changes and justification that these changes do not affect the ability of the package to meet the regulatory requirements. Applications for modifications may be subject to the provisions of 10 CFR 71.19, Previously Approved Package, and Paragraphs 816 and 817 of TS-R-1 as referenced in Paragraph 16(1)(a)(viii) of the PTNS Regulations. For package designs approved prior to this guide becoming effective, revised package applications may be submitted for approval under this guide.

Packaging that does not conform to the drawings referenced in the design approval is not authorized for use. Likewise, only contents specified in the approval may be transported. Package operations, acceptance tests, and the maintenance program may also be specified as conditions of the approval.

1.1 Introduction

This section should identify the proposed use of the package, the model number, and, in the case of fissile material packages, the proposed criticality safety index (CSI) and the value of “N”, as defined in 10 CFR 71.59, Standards for Arrays of Fissile Material Packages, and Paragraph 681 of TS-R-1 which is incorporated in Subsection 1(1) of the PTNS Regulations by reference to Paragraph 672 of TS-R-1. This section should clearly specify any restrictions regarding transport mode, stowage, exclusive use, or type of conveyance for shipment of the package.

1.2 Package Description

This section should include a package description as required by 10 CFR 71.33, General License: Plutonium-Beryllium Special Form Material, and Paragraphs 807 and 813 of TS-R-1 as referenced in Paragraph 7(1)(a) of the PTNS Regulations. The package description should be sufficiently detailed to provide an adequate basis for its evaluation.

1.2.1 Packaging

This section should give a description of the packaging and any ancillary equipment, with the major design features highlighted. Sketches, figures, or other schematic diagrams should be provided as appropriate. Engineering drawings of the packaging should be presented in the appendix. The general packaging description should include the following information:

1. The overall dimensions (the smallest overall dimension of the package must not be less than 10 centimetres (cm) as required by 10 CFR 71.43(a) or Paragraph 634 of TS-R-1 which is incorporated in Subsection 1(1) of the PTNS Regulations by reference to Paragraph 650 of TS-R-1));
2. Maximum (fully loaded) weight and minimum (empty) weight (if appropriate);
3. Maximum normal operating pressure as defined in 10 CFR 71.4, Definitions, or Paragraph 228 of TS-R-1;
4. Structural features, including lifting and tie-down devices, impact limiters or other energy-absorbing features, internal supporting or positioning features, outer shell or outer packaging, and packaging closure devices;
5. Secondary packaging components, including internal containers, spacers, shoring;
6. For spent nuclear fuel (SNF), internal components, such as baskets and any inner containers for damaged or consolidated fuel;
7. Tamper-indicating features as specified in 10 CFR 71.43(b) or Paragraph 635 of TS-R-1 which is incorporated in Subsection 1(1) of the PTNS Regulations by reference to Paragraph 650 of TS-R-1;
8. Packaging markings( e.g., model number, serial number, gross weight and assigned identification number);
9. The codes and standards used for package design, materials specification, fabrication, welding, and inspection;
10. Heat transfer features;
11. Containment features, including penetrations such as vents, ports, and sampling ports;
12. Neutron and gamma shielding features, including personnel barriers; and
13. Criticality control features, including neutron poisons, moderators, flux traps, and spacer.

The exact containment system boundary should be defined. This may include the containment vessel, welds, drain or fill ports, valves, seals, test ports, pressure relief devices, lids, cover plates, and other closure devices. If multiple seals are used for a single closure, the seal defined as the containment system seal should be clearly identified. A sketch of the containment system should be provided. All components should be shown on the engineering drawings in the appendix. Likewise, the confinement system for fissile material packages should be defined. The confinement system is composed of those features that are intended to ensure criticality safety, such as features that are designed to retain and provide geometry control of the fissile material.

1.2.2 Contents

This section should state the quantity of radionuclides to be transported. The description should include the following information (if appropriate):

1. General nature of contents (e.g., irradiated fuel, metallurgical specimens, radiographic source);
2. Identification and maximum quantity (radioactivity or mass) of the radioactive material;
3. Identification and quantity limits of fissile material;
4. Chemical and physical form, including density and moisture content, and the presence of any moderating constituents;
5. Location and configuration of contents within the packaging, including secondary containers, wrapping, shoring, and other material not defined as part of the packaging;
6. Identification and quantity of non-fissile material used as neutron absorbers or moderators;
7. Any material subject to chemical, galvanic, or other reaction, including the generation of gases;
8. Maximum weight of radioactive contents and maximum weight of payload, including secondary containers and packaging if applicable;
9. Maximum decay heat;
10. Any loading restrictions; and
11. For irradiated nuclear fuel:

1. Type of fuel and fuel assembly specifications, including the number of fuel rods and dimensional data for fuel rods and assembly structure,
2. Control assemblies or other contents (e.g., start-up sources),
3. Initial fissile mass,
4. Maximum irradiation and minimum irradiation (where applicable),
5. Minimum cooling time,
6. Initial enrichment (maximum and minimum if applicable),
7. Unique or unusual conditions, such as damaged fuel, non-uniform enrichments, and annular pellets,
8. Cavity fill gas, and
9. Estimates of surface contamination.

This section should identify any contents contained in any other class of hazardous material (other than Class 7) covered in the latest edition of The United Nations Recommendations on the Transport of Dangerous Goods [14] (e.g., explosive, pyrophoric, corrosive, flammable, oxidizing). This description should include the chemical and physical form of the material, the quantity limits of the material, and how the properties of such contents have been taken into account in the design of the packaging.

Additionally, this section should provide a description of the contents that is suitable for inclusion in the certificate, including the type and form of material and the maximum quantity of material per package.

1.2.3 Special Requirements for Plutonium

For packages that may contain plutonium in excess of 0.74 TBq (20 curies (Ci)) per package, this section should show that these contents must be in solid form, in accordance with 10 CFR 71.63, Special Requirements for Plutonium Shipments.

1.2.4 Operational Features

In the case of a complex package system, this section should describe the operational features of the package. This should include a schematic diagram showing all valves, connections, piping, openings, seals, containment boundaries, and so forth.

1.3 Appendix

The appendix should include the engineering drawings for the packaging. The drawings should clearly detail the safety features considered in the package evaluation. Packages authorized for shipment must conform to the approved design; that is, each packaging must be fabricated in conformance to the drawings referenced in the approval. While the details included in the drawings should be at a level that is sufficient for independent verification and certification purposes, it should be noted that additional details on certification drawings, similar to those needed for fabrication drawings, would require frequent review and approval by regulatory authorities if any changes are made.

Each drawing should include a title block that identifies the preparing organization, drawing number, sheet number, title, date, and signature or initials indicating approval of the drawing. Revised drawings should identify the revision number, date, and description of the change in each revision. Information that may be useful in developing and reviewing engineering drawings is included in NUREG ICR-5502 Engineering Drawings for 10CFR Part 71 Package Approvals [20]. The drawings should include the following:

1. General arrangement of packaging and contents, including dimensions;
2. Design features that affect the package evaluation;
3. Packaging markings (e.g., model number, serial number, gross weight, and assigned identification number);
4. Maximum allowable weight of package;
5. Maximum allowable weight of contents and secondary packaging;
6. Minimum weights if appropriate; and
7. Materials of construction, including appropriate material specifications and a materials list.

Information on design features should include the following as appropriate:

1. Identification of the design feature and its components;
2. Codes, standards, or other similar specification documents for fabrication, assembly, and testing;
3. Location with respect to other package features;
4. Dimensions with appropriate tolerances;
5. Operational specifications (e.g., bolt torque);
6. Weld design and inspection method; and
7. Gasketted joints in the containment system with sufficient detail to show, as a minimum, the surface finish and flatness requirements of the closure surfaces, the gasket or O-ring specification, and, if appropriate, the method of gasket or O-ring retention.

The appendix should also include a list of references, applicable pages from referenced documents that are not generally available, supporting information on special fabrication procedures, determination of the package category, and other appropriate supplemental information.