Text

E-61285 Enclosure 1, French Approval Certificate of a Package Design, Number F/348/AF-96 (Revision Gw), English
	ML22277A727
Person / Time
Site:	07103097
Issue date:	06/13/2022
From:	Boyle R, Shaw D; TN Americas LLC
To:	; Division of Fuel Management
	Garcia-Santos N
Shared Package
ML22277A716	List: ML22277A726; ML22277A727; ML22277A728; ML22277A729; ML22277A730; ML22277A731; ML22277A733; ML22277A734; ML22277A735; ML22277A736; ML22277A737; ML22277A738; ML22277A739; ML22277A740; ML22277A741; ML22277A742; ML22277A743; ML22277A744; ML22277A745; ML22277A746; ML22277A747; ML22277A748; ML22277A749; ML22277A750; ML22277A751; ML22277A752; ML22277A753; ML22277A754; ML22277A755; ML22277A757; ML22277A758; ML22277A759; ML22277A760; ML22277A761; ML22277A762; ML22277A763; ML22277A764; ML22277A765; ML22277A766; ML22277A767; ML22277A768; ML22277A769; ML22277A770; ML22277A771; ML22277A772; ML22277A773; ML22277A774; ML22277A775; ML22277A776; ML22277A777; ... further results
References
	A33010, E-61285, EPID L-2022-DOT-0008
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Enclosure 1 to E-61285

French Approval Certificate of a Package Design, Number F/348/AF-96 (Revision Gw), English FRENCH REPUBLIC

F/348/AF-96 (Gw) page 1/3

APPROVAL CERTIFICATE FOR A PACKAGE DESIGN

The Competent French Authority, Having regard to Article R. 595-1 of the French Environmental Code; Having regard to the request submitted by the company Orano NPS in letter COR-22-000220-013 dated 22 February 2022; Having regard to safety analysis report DOS-18-016472-000 Rev. 5.0 of 21 February 2022; Having regard to the certificate previously issued under reference F/348/AF-96 (Fu);

Having regard to the results of the public consultation conducted from 29 June 2021 to 14 July 2021; Hereby certifies that the package design comprising the FCC4 packaging described hereafter in Appendix 0 revision w and loaded with:

x up to 2 new GAIA PWR 17 x 17 XL, PWR 17 x 17 XLR, PWR 17 x 17 fuel assemblies, in version 1 of the packaging, as described in Appendix 1 revision w; or x up to 2 new PWR 16 x 16 fuel assemblies, in version 2 of the packaging, as described in Appendix 2 revision w; or x up to 2 new PWR 18 x 18 PWR fuel assemblies, in version 2 of the packaging, as described in Appendix 3 revision w; or x up to 2 boxes containing new, unassembled PWR 17 x 17 XL or PWR 17 x 17 XLR fuel rods, in version 1 of the packaging, as described in Appendix 4 revision w; or x up to 2 boxes containing new, unassembled PWR 17 x 17 twelve-foot fuel rods, in version 1 of the packaging, as described in Appendix 5 revision w; or x up to 2 boxes containing new, unassembled PWR 15 x 15 fuel rods, in version 1 of the packaging, as described in Appendix 6 revision w; or x up to 2 boxes containing new, unassembled PWR 14 x 14 eight-foot fuel rods, in version 1 of the packaging, as described in Appendix 7 revision w; or x up to 2 boxes containing new, unassembled PWR 14 x 14 ten-foot fuel rods, in version 1 of the packaging, as described in Appendix 8 revision w; or x up to 2 boxes containing new, unassembled PWR 16 x 16 fuel rods, in version 1 of the packaging, as described in Appendix 10 revision w; or x up to 2 boxes containing new, unassembled PWR 18 x 18 fuel rods, in version 1 of the packaging, as described in Appendix 11 revision w; or x up to 2 new EPR 17 x 17 fuel assemblies, or one new EPR 17 x 17 fuel assembly fitted with a cluster and a smooth-walled dummy, or an EPR assembly mock-up, in version 1, as described in Appendix 12 revision w; or x up to 2 boxes containing new EPR 17 x 17 fuel rods, in version 1 of the package, as described in Appendix 13 revision w;

15 rue Louis Lejeune

CS 70013

92541 Montrouge Cedex

France Telephone: +33 (0) 1 46 16 40 00 / E-mail: info@asn.fr

asn.fr

F/348/AF-96 (Gw) page 2/3

is compliant, as a type A package design for fissile materials, with the requirements for the regulations and agreements listed below:

- International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material, Safety Standards Series No. SSR-6 (Rev. 1), 2018 Edition;

- Agreement concerning the International Carriage of Dangerous Goods by Road (ADR);

- European Agreement concerning the International Carriage of Dangerous Goods by Inland Waterways (ADN);

- Regulation concerning the International Carriage of Dangerous Goods by Rail (RID);

- International Maritime Dangerous Goods Code (IMDG code of the IMO);

- amended French order of 23 November 1987 on the safety of ships, and particularly section 411 of the appended regulation (the RSN order);

- amended French Order of 29 May 2009, on the carriage of dangerous goods by overland routes (the TMD order).

This certificate does not release the shipper from the obligation to comply with the requirements laid down by the authorities of the countries through or to which the package is to be shipped.

This certificate expires on 31 December 2027.

Registration number: CODEP-DTS-2022-027480.

Signed in Montrouge, 13 June 2022.

On behalf of the President of the French Nuclear Safety Authority by delegation, the Director of Transport and Sources,

Fabien FÉRON F/348/AF-96 (Gw) page 3/3

SUMMARY

OF CERTIFICATE ISSUES Issue Certificate Revision date Expiry date Type of issue reference body t 0 1 2 3 4 5 6 7 8 9 10 11 12 13

11/12/17 31/12/22 Renewal F/348/IF-96 Fo - o o o o o o o o o - o o o o

29/12/17 31/12/22 Modification F/348/IF-96 Fp - p o o o o o o o o - o p o p

14/08/19 31/12/22 Extension F/348/AF-96 Fq - q q q q q q q q q - q q q q

20/03/20 31/12/22 Extension F/348/IF-96 Fr - r r r r r r r r r - r r r r

21/04/21 31/12/22 Extension F/348/IF-96 Fs - s s s s s s s s s - s s s s

11/03/22 31/12/22 Extension F/348/IF-96 Ft - t t t t t t t t t - t t t t

11/03/22 31/12/22 Extension F/348/AF-96 Fu - u u u u u u u u u - u u u u Extension 19/04/22 31/12/22 (cancels and F/348/AF-96 Fu - u u u u u u u u u - u u u u replaces) 13/06/22 31/12/27 Renewal F/348/IF-96 Gv - v v v v v v v v v - v v v v

13/06/22 31/12/27 Renewal F/348/AF-96 Gw - w w w w w w w w w - w w w w

F/348/AF-96 (0w) page 1/4

APPENDIX 0 FCC4 PACKAGING

1. DESCRIPTION OF THE PACKAGING The packaging was designed, manufactur ed, inspected, tested, maintained an d used in compliance with safety analysis report DOS-18-016472-000 Rev. 5.0.

The packaging, which is generally cylindrical in shape, is shown in figures 0.1 and 0.2.

The packaging design drawings bear the reference numbers 229K0400 or 229K0600 for version 1 and 229K0500 for version 2.

The overall external dimensions of the packaging are:

- length: 5,748 mm:

- width: 1,134 mm:

- height: 1,297 mm The maximum permissible mass of the loaded packaging during transport is 5,550 kg.

The packaging comprises the following main sub-assemblies:

Packaging body The FCC4 packaging consists of a cylindrical enclosure, with a horizontal axis, composed of two linked half -

shells comprising:

- a metal cradle consisting of two longitudinal members and suspended from the lower shell by means of rubber shock absorbers;

- an internal equipment resting on the cradle and intended to house one of the contents.

This internal equipment is composed of :

- a support frame with a rigid, inverted T-shaped structure designed to hold the content in place horizontally. The fabricated part of the frame contains neutron-absorbing resin. A tilting pin on the bottom plate allows the support frame to be moved into a vertical position for loading or unloading assemblies;

- two 'L' shaped doors containing neutron-absorbing resin which are attached to the support frame and encapsulate the contents;

- a bottom plate supporting the fuel assemblies during loading and unloading when the support frame is in the upright position;

- a two-piece top plate, which serves to close the cavities and secure the contents at the other end.

Packaging closing system The two cylindrical half-shells are connected together using 50 bolts.

The doors and top plates are connected to the frame us ing ball pins and spindles. The bottom plate is screwed to the frame.

Shock-absorbing systems Two axial shock absorbers are attached to the end of the upper shell. They are composed of two metal boxes containing a block of balsa wood.

Two additional axial shock absorbers are attached to the top plates when transporting EPR assemblies.

F/348/AF-96 (0w) page 2/4

Handling and tie-down elements Items are handled using a suitable lifting beam or slings equipped with shackles or hooks, according to one of the following three lifting methods:

- By 4 lifting boxes welded to the upper shell and made of a folded sheet of metal with a hole in it for a shackle or a hook;

- By 4 lifting boxes welded to the lower shell;

- By fork slots located under the lower shell.

The packaging is also designed so that it can be secured during transportation in accordance with the recommendations in chapter 1.7 of safety analysis report DOS-18-016472-009 Rev. 2.0.

Safety functions Containment and radiation protection functions are provided by the fuel rods.

Sub-criticality continuity is guaranteed by the isolation system consisting of the elements identified in the appendices describing the contents and, for the packaging, by the following elements:

- the internal equipment, consisting of the frame, doors and end plates and, in the case of rod boxes, the radial and axial spacer system and the rod boxes themselves, together forming two neutron cavities;

- neutron-absorbing resin contained in the doors and frame;

- the upper and lower shells that protect the internal equipment in normal and accident conditions of transport.

The fuel is protected against impacts by the two half-shells and the internal equipment.

Fire protection is mainly provided by the two half-shells, the internal equipment and the resin in the doors and frame.

2. ACTIONS TO BE TAKEN BY THE SHIPPER PRIOR TO SHIPPING THE PACKAGE The packaging is to be used in accordance with procedur es that comply with the inst ructions for use in Chapter 1.7 of safety analysis report DOS-18-016472-009 Rev. 2.0.

3. MAINTENANCE PROGRAMME The packaging is to be maintained in accordance with the procedures described in Chapter 1.8 of safety analysis report DOS-18-016472-010 Rev. 1.0.

4. NOTIFICATION The ASN shall be kept informed via the following email address: dts-transport@asn.fr of any packaging that is taken out of service or transferred to another owner. Accordingly, any owner that transfers a packaging must communicate the name of the new owner.

5. QUALITY MANAGEMENT SYSTEM The principles of the quality management system to be applied to the design, manufacture, inspection, testing, maintenance and use of the package must comply with the principles described in Chapter 1.9 of safety analysis report DOS-18-016472-008 Rev. 1.0.

F/348/AF-96 (0w) page 3/4

FIGURE 0.1

PACKAGING DIAGRAM

F/348/AF-96 (0w) page 4/4

FIGURE 0.2

THREE-DIMENSIONAL VIEW OF THE PACKAGING

F/348/AF-96 (1w) page 1/2

ANNEXE 1 CONTENT N°1:

NEW PWR TYPE 17 uu 17 FOURTEEN-FOOT XL, XLR OR GAIA FUEL ASSEMBLIES

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 1 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of a maximum of two new fuel assemblies for pressurized water reactor (PWR), as described below:

Characteristics of the fuel assemblies Name 17 x 17 XL, XLR or GAIA (1)

Type of array 17 x 17 fourteen foot Nominal array pitch (mm) 12.6 Total maximum mass of a fuel assembly with or without a rod 877 cluster (kg)

Maximum mass of UO2 per assembly (kg) 690 Nominal active length (mm) 4,267 Maximum number of fuel rods 288 (2)

Characteristics of fuel rods Cladding material Zirconium alloy, possibly pre-oxidised, possibly chromium-plated Minimum metal thickness (mm) 0.52 Minimum outer diameter (mm) 9.40 Pellets: ENU (3)

Maximum diameter (mm) 8.30 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/Utotal) (%) 5 Maximum mass ratio 232U/Utotal (%) 5x10-8 Maximum mass ratio 234U/Utotal (%) 0.055 Maximum mass ratio 236U/Utotal (%) 0.05 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) 17 x 17 XL, XLR and GAIA refer to the 17 x 17 fourteen foot array of assemblies for 1000, 1300 and 1450 MWe reactors. Authorised contents may be composed of assemb lies with different identifiers provided they have the characteristics mentioned in the above table.

(2) This number corresponds to the maximum number of fuel rods that can be inserted into a structure (assembly skeleton or quiver), including guide tubes.

(3) ENU: Enriched Natural Uranium.

Glycerine residues up to a maximum of 5 grams can be present on the fuel assemblies.

F/348/AF-96 (1w) page 2/2

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 At (% over 50 mm) 12 25

Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rod assemblies composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All assemblies in a load meet the conditions defined in the following table:

Maximum initial enrichment per fuel rod for each Minimum number of fuel rods per fuel assembly assembly in the load (235U/Utotal) in the load (1) 5 % 264 (1) Incomplete UO2 fuel rod assemblies can be supplemented wi th gadolinium-carrying rods, rods containing depleted uranium or other metallic ma terial, or bars filled with a metallic material (excluding graphite and

beryllium), possibly containing a neutron poison. These supplementary rods or bars will be equivalent in size to the UO2 rods. The expression number of rods per assembly is understood to mean the total number of fuel rods and replacement rods or bars.

All fuel assemblies in the load, except one, can be replaced by fuel assembly skeletons.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5-1 of the safety analysis report.

The content part of the isolation system under consideration comprises the following elements:

- the characteristics of the fuel assemblies as described in the Table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation;

- the structure of the assembly (grids, end-pieces).

Criticality Safety Index (CSI): 0.625 (N number = 80).

F/348/AF-96 (2w) page 1/2

ANNEXE 2 CONTENT NO. 2 PWR TYPE NEW 16 uu 16 FUEL ASSEMBLIES

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 2 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of a maximum of two new fuel assemblies for pressurized water reactor (PWR), as described below:

Characteristics of the fuel assemblies Type of array 16 x 16 Nominal array pitch (mm) 14.3 Total maximum mass of a fuel assembly with or without a rod 877 cluster (kg)

Maximum mass of UO2 per assembly (kg) 639 Nominal active length (mm) 3,900 Maximum number of fuel rods 236 (1)

Characteristics of fuel rods Cladding material oxidised, possibly chromium-plated Zirconium alloy, possibly pre-

Minimum metal thickness (mm) 0.68 Minimum outer diameter (mm) 10.70

Pellets: ENU (2)

Maximum diameter (mm) 9.14 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/Utotal) (%) 4.5 Maximum mass ratio 232U/Utotal (%) 5x10-8 Maximum mass ratio 234U/Utotal (%) 0.055 Maximum mass ratio 236U/Utotal (%) 0.05 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) This number corresponds to the maximum number of fuel rods that can be inserted into a structure (assembly skeleton or quiver), including guide tubes.

(2) ENU: Enriched Natural Uranium.

Glycerine residues up to a maximum of 5 grams can be present on the fuel assemblies.

F/348/AF-96 (2w) page 2/2

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 At (% over 50 mm) 12 25

Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rod assemblies composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or fuel pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All assemblies in a load meet the conditions defined in the following table:

Maximum initial enrichment per fuel rod for each Minimum number of fuel rods per fuel assembly in the load (235U/Utotal) assembly in the load (1) 4.5 % 236 (1) Incomplete UO2 fuel rod assemblies can be supplemented wi th gadolinium-carrying rods, rods containing depleted uranium or other metallic ma terial, or bars filled with a metallic material (excluding graphite and

beryllium), possibly containing a neutron poison. These supplementary rods or bars will be equivalent in size to the UO2 rods. The expression number of rods per assembly is understood to mean the total number of fuel rods and replacement rods or bars.

All fuel assemblies in the load, except one, can be replaced by fuel assembly skeletons.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5-1 of the safety analysis report.

The content part of the isolation system under consideration comprises the following elements:

- the characteristics of the fuel assemblies as described in the Table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation;

- the structure of the assembly (grids, end-pieces).

Criticality Safety Index (CSI): 8.33 (N number = 6).

F/348/AF-96 (3w) page 1/2

ANNEXE 3 CONTENT NO. 3 NEW PWR TYPE 18 uu 18 FUEL ASSEMBLIES

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 2 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of a maximum of two new fuel assemblies for pressurized water reactor (PWR), as described below:

Characteristics of the fuel assemblies Type of array 18 x 18 Nominal array pitch (mm) 12.7 Total maximum mass of a fuel assembly with or without a rod 877 cluster (kg)

Maximum mass of UO2 per assembly (kg) 630 Nominal active length (mm) 3,900 Maximum number of fuel rods 300 (1)

Characteristics of fuel rods Cladding material oxidised, possibly chromium-plated Zirconium alloy, possibly pre-

Minimum metal thickness (mm) 0.60 Minimum outer diameter (mm) 9.46 Pellets: ENU (2)

Maximum diameter (mm) 8.08 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/Utotal) (%) 4.5 Maximum mass ratio 232U/Utotal (%) 5x10-8 Maximum mass ratio 234U/Utotal (%) 0.055 Maximum mass ratio 236U/Utotal (%) 0.05

Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) This number of rods corresponds to the maximum number of rods that can be inserted into a structure (assembly skeleton or quiver), including in the guide tubes.

(2) ENU: Enriched Natural Uranium.

Glycerine residues up to a maximum of 5 grams can be present on the fuel assemblies.

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 F/348/AF-96 (3w) page 2/2

At (% over 50 mm) 12 25

Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rod assemblies composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or fuel pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All assemblies in a load meet the conditions defined in the following table:

Maximum initial enrichment per fuel rod for each Minimum number of fuel rods per fuel assembly in assembly in the load (235U/Utotal) the load (1) 4.5 % 300 (1) Incomplete UO2 fuel rod assemblies can be s upplemented with gadolinium -carrying rods, rods containing depleted uranium or other metallic material, or bars filled with a metallic material (excluding graphite and beryllium),

possibly containing a neutron poison. These supplementary rods or bars will be equivalent in size to the UO2 rods.

The expression number of rods per assembly is understood to mean the total number of fuel rods and replacement rods or bars.

All fuel assemblies in the load, except one, can be replaced by fuel assembly skeletons.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5-3 of the safety analysis report.

The isolation system under considerat ion comprises the following elements:

- the characteristics of the fuel assemblies as descri bed in the Table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation;

- the structure of the assembly (grids, end-pieces).

Criticality Safety Index (CSI): 8.33 (N number = 6).

F/348/AF-96 (4w) page 1/4

ANNEXE 4 CONTENT NO. 4 PWR TYPE 17 uu 17 XL OR 17 u-FOOT FUEL RODS

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 1 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of new fuel rods for pressurised water reactors (PWR), as described below:

Characteristics of fuel rods Name 17 x 17 XL or XLR Type of assembly array housing these rods 17 x 17 fourteen foot Maximum total mass per cavity (kg) 856 Maximum total mass of the rods per box (kg) 537 Maximum mass of UO2 (kg) 443/box Nominal active length (mm) 4,267 Maximum number of fuel rods per box 185 Cladding material Zirconium alloy, possibly pre-oxidised, possibly chromium-plated Minimum metal thickness (mm) 0.52 Minimum outer diameter (mm) 9.40

Pellets: ENU (2)

Maximum diameter (mm) 8.30 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/U total) (%) 5 Maximum mass ratio 232U/U total (%) 5x10-8 Maximum mass ratio 234U/U total (%) 0.055 Maximum mass ratio 236U/U total (%) 0.05 Minimum Gd2O3 mass content in gadolinium-carrying rods (%) (1) 2 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) Fuel rods with a Gd2O3 content of less than 2% are considered as (non gadolinium -carrying) UO2 fuel rods.

(2) ENU: Enriched Natural Uranium.

F/348/AF-96 (4w) page 2/4

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 At (% over 50 mm) 12 25

Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rods composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or fuel pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All fuel rods in a load meet the conditions defined in the following table:

Maximum initial enrichment of each fuel rod in the Minimum number of fuel rods per box (1) load (235U/Utotal) 5 % Full row of fuel or inert rods (1) Incomplete rows of fuel rods are supplemented with solid stainless steel (or zirconium alloy) bars, with a nominal diameter of between 9.5 and 10 mm, possibly containing a neutron poison. The term number of rods per box is understood to mean the total number of fuel rods and steel (or zirconium alloy) bars.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. INTERNAL FITTINGS The internal fitting is a rod box, which is described in Chapters 1.3-1 and 1.3-2 of the safety analysis report.

3.1 Rod box The unassembled rods are grouped together in FCC4-type rod boxes, which are inserted in place of the assemblies inside the version 1 FCC4s.

The box is made of a folded U-shaped sheet, which is closed at the ends and reinforced by two members welded to the top of the sheet.

A radial spacer system holds the rods in position. A diagram is provided in Figure 4.1.

The minimum height of the radial spacer is 85 mm.

3.2 Rod box spacers A set of 2 spacers longitudinally holds the box in place in the cavity (a top spacer and a bottom spacer). A detailed description of the spacers can be found in Chapter 1.3-1 of the safety analysis report.

F/348/AF-96 (4w) page 3/4

4. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5 -2 of the safety analysis report.

The isolation system under considerat ion comprises the following elements:

- the characteristics of the fuel rods as describe d in the table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation.

Criticality Safety Index (CSI):

- when UO2 rods are transported, the criticality safety index is equal to 0 (number N = infinity),

- when UO2-Gd2O3 rods are transported, the criticality safe ty index is 0 (number N = infinity).

F/348/AF-96 (4w) page 4/4

FIGURE 4.1

DIAGRAM OF THE RODS BOX

F/348/AF-96 (5w) page 1/4

ANNEXE 5 CONTENT NO. 5 PWR TYPE 17 uu 17 TWELVE-FOOT FUEL RODS

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 1 FCC 4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of new fuel rods for pressurised water reactors, as described below:

Characteristics of fuel rods Type of assembly array housing these rods 17 x 17 twelve foot Maximum total mass per cavity (kg) 856 Maximum total mass of the rods per box (kg) 461 Maximum mass of UO2 (kg) 380/box Nominal active length (mm) 3,658 Maximum number of fuel rods per box 185 Cladding material Zirconium alloy, possibly pre-oxidised, possibly chromium-plated Minimum metal thickness (mm) 0.52 Minimum outer diameter (mm) 9.40 Pellets: ENU (2)

Maximum diameter (mm) 8.30 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/U total) (%) 5 Maximum mass ratio 232U/U total (%) 5x10-8 Maximum mass ratio 234U/U total (%) 0.055 Maximum mass ratio 236U/U total (%) 0.05

Minimum Gd2O3 mass content in gadolinium-carrying rods (%) (1) 2 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) Fuel rods with a Gd2O3 content of less than 2% are considered as (non gadolinium -carrying) UO2 fuel rods.

(2) ENU: Enriched Natural Uranium.

F/348/AF-96 (5w) page 2/4

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 At (% over 50 mm) 12 25

Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rods composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or fuel pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All fuel rods in a load meet the conditions defined in the following table:

Maximum initial enrichment of each fuel rod in the Minimum number of fuel rods per box (1) load (235U/Utotal) 5 % Full row of fuel or inert rods (1) Incomplete rows of fuel rods must be supplemented with solid stainless steel (or zi rconium alloy) bars, with a nominal diameter of between 9.5 mm and 10 mm, possibly containing a neutron poison. The term number of rods per box is understood to mean the total number of fuel rods and steel (or zirconium alloy) bars.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. INTERNAL FITTINGS The internal fitting is a rod box, which is described in Chapters 1.3-1 and 1.3-2 of the safety analysis report.

3.1 Rod box The unassembled rods are grouped together in FCC4-type rod boxes, which are inserted in place of the assemblies inside the version 1 FCC4s.

The box is made of a folded U-shaped sheet, which is closed at the ends and reinforced by two members welded to the top of the sheet.

A system of axial and radial spacers is used to adapt to the lengths of the rods and to hold them in position. A diagram is provided in Figure 5.1. The minimum height of the radial spacer is 85 mm.

3.2 Rod box spacers

A set of 2 spacers longitudinally holds the box in place in the cavity (a top spacer and a bottom spacer). A detailed description of the spacers can be found in Chapter 1.3-1 of the safety analysis report.

F/348/AF-96 (5w) page 3/4

4. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5 -2 of the safety analysis report.

The content part of the isolation system under consideration comprises the following elements:

- the characteristics of the fuel rods as describe d in the table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation.

Criticality Safety Index (CSI):

- when UO2 rods are transported, the criticality safety index is equal to 0 (number N = infinity);

- when UO2-Gd2O3 rods are transported, the criticality sa fety index is 0 (number N = infinity).

F/348/AF-96 (5w) page 4/4

FIGURE 5.1

DIAGRAM OF THE RODS BOX

F/348/AF-96 (6w) page 1/4

ANNEXE 6 CONTENT NO. 6 PWR TYPE 15 uu 15 FUEL RODS

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 1 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of new fuel rods for pressurised water reactors (PWR), as described below:

Characteristics of fuel rods Type of assembly array housing these rods 15 x 15 Maximum total mass per cavity (kg) 856 Maximum total mass of the rods per box (kg) 470 Maximum mass of UO2 (kg) 389/box Nominal active length (mm) 3,658 Maximum number of fuel rods per box 148 Cladding material Zirconium alloy, possibly pre-oxidised, possibly chromium-plated Minimum metal thickness (mm) 0.57 Minimum outer diameter (mm) 10.68 Pellets: ENU (2)

Maximum diameter (mm) 9.40 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/U total) (%) 5 Maximum mass ratio 232U/U total (%) 5x10-8 Maximum mass ratio 234U/U total (%) 0.055 Maximum mass ratio 236U/U total (%) 0.05 Minimum Gd2O3 mass content in gadolinium-carrying rods (%) (1) 2 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) Fuel rods with a Gd2O3 content of less than 2% are considered as (non gadolinium -carrying) UO2 fuel rods.

(2) ENU: Enriched Natural Uranium.

F/348/AF-96 (6w) page 2/4

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 At (% over 50 mm) 12 25 Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rods composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or fuel pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All fuel rods in a load meet the conditions defined in the following table:

Maximum initial enrichment of each fuel rod in the Minimum number of fuel rods per box (1) load (235U/Utotal) 5 % Full row of fuel or inert rods (1) Incomplete rows of fuel rods are supplemented with solid stainless steel (or zirconium alloy) bars, with a nominal diameter of between 10.7 mm and 11 mm, po ssibly containing a neutron poison. The term number of rods per box is understood to mean the total number of fuel rods and steel (or zirconium alloy) bars.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. INTERNAL FITTINGS The internal fitting is a rod box, which is described in Chapters 1.3-1 and 1.3-2 of the safety analysis report.

3.1 Rod box The unassembled rods are grouped together in FCC4-type rod boxes, which are inserted in place of the assemblies inside the version 1 FCC4s.

The box is made of a folded U-shaped sheet, which is closed at the ends and reinforced by two members welded to the top of the sheet.

A system of axial and radial spacers is used to adapt to the lengths of the rods and to hold them in position. A diagram is provided in Figure 6.1.

The minimum height of the radial spacer is 85 mm.

3.2 Rod box spacers A set of 2 spacers longitudinally holds the box in place in the cavity (a top spacer and a bottom spacer). A detailed description of the spacers can be found in Chapter 1.3-1 of the safety analysis report.

F/348/AF-96 (6w) page 3/4

4. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5 -2 of the safety analysis report.

The content part of the isolation system under consideration comprises the following elements:

- the characteristics of the fuel rods as describe d in the table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation.

Criticality Safety Index (CSI):

- when UO2 rods are transported, the criticality safety index is equal to 0 (number N = infinity);

- when UO2-Gd2O3 rods are transported, the criticality sa fety index and 0 (number N = infinity).

F/348/AF-96 (6w) page 4/4

FIGURE 6.1

DIAGRAM OF THE RODS BOX

F/348/AF-96 (7w) page 1/4

ANNEXE 7 CONTENT NO. 7 PWR TYPE 14 uu 14 EIGHT-FOOT FUEL RODS

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 1 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of new fuel rods for pressurised water reactors (PWR), as described below:

Characteristics of fuel rods Type of assembly array housing these rods 14 x 14 eight foot Maximum total mass per cavity (kg) 856 Maximum total mass of the rods per box (kg) 471 Maximum mass of UO2 (kg) 394/box Nominal active length (mm) 2,413 Maximum number of fuel rods per box 222 Cladding material Zirconium alloy, possibly pre-oxidised, possibly chromium-plated Minimum metal thickness (mm) 0.57 Minimum outer diameter (mm) 10.68 Pellets: ENU (2)

Maximum diameter (mm) 9.40 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/U total) (%) 5 Maximum mass ratio 232U/U total (%) 5x10-8 Maximum mass ratio 234U/U total (%) 0.055 Maximum mass ratio 236U/U total (%) 0.05

Minimum Gd2O3 mass content in gadolinium-carrying rods (%) (1) 2 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) Fuel rods with a Gd2O3 content of less than 2% are considered as (non gadolinium -carrying) UO2 fuel rods.

(2) ENU: Enriched Natural Uranium.

F/348/AF-96 (7w) page 2/4

The mechanical strength properties of the fuel rod clad ding material meet one of the following two triplets:

1 2 Rp0.2 (MPa) 520 250 Rm (MPa) 710 400 At (% over 50 mm) 12 25

Maximum activity per packaging: The maximum ac tivity of the contents is less than 1 A2.

Physical state: Fuel rods composed of sintered pellets placed in a cladding. The cladding can be covered with a layer of chromium up to 30 m thick.

Chemical form: Uranium oxide (UO2) pellets and/or fuel pellets composed of a mixture of UO 2 and a body that acts as a neutron poison. The pellets may contain chromium oxide (but no other doping agents).

Special form: The material transported is not in any special form.

2. LOADING CONDITIONS All fuel rods in a load meet the conditions defined in the following table:

Maximum initial enrichment of each fuel rod in the Minimum number of fuel rods per box (1) load (235U/Utotal) 5 % Full row of fuel or inert rods (1) Incomplete rows of fuel rods are supplemented with solid stainless steel (or zirconium alloy) bars, with a nominal diameter of between 10.7 mm and 11 mm, possibly containing a neutron poison. The term number of rods per box is understood to mean the total number of fuel rods and steel (or zirconium alloy) bars.

The presence of desiccant is permitted.

The presence of materials with more hydrogen content than water is not authorised within the packaging.

3. INTERNAL FITTINGS The internal fitting is a rod box, which is described in Chapters 1.3-1 and 1.3-2 of the safety analysis report.

3.1 Rod box The unassembled rods are grouped together in FCC4-type rod boxes, which are inserted in place of the assemblies inside the version 1 FCC4s.

The box is made of a folded U-shaped sheet, which is closed at the ends and reinforced by two members welded to the top of the sheet.

A system of axial and radial spacers is used to adapt to the lengths of the rods and to hold them in position. A diagram is provided in Figure 7.1. The minimum height of the radial spacer is 85 mm.

3.2 Rod box spacers

A set of 2 spacers longitudinally holds the box in place in the cavity (a top spacer and a bottom spacer). A detailed description of the spacers can be found in Chapter 1.3-1 of the safety analysis report.

F/348/AF-96 (7w) page 3/4

4. SUB-CRITICALITY CONTINUITY Sub-criticality continuity is covered in Chapter 2.5 -2 of the safety analysis report.

The content part of the isolation system under consideration comprises the following elements:

- the characteristics of the fuel rods as describe d in the table in Chapter 1 of this Appendix;

- the cladding tubes which guarantee the containment of the fissile material in an accident situation.

Criticality Safety Index (CSI):

- when UO2 rods are transported, the criticality safety index is equal to 0 (number N = infinity);

- when UO2-Gd2O3 rods are transported, the criticality sa fety index is 0 (number N = infinity).

F/348/AF-96 (7w) page 4/4

FIGURE 7.1

DIAGRAM OF THE RODS BOX

F/348/AF-96 (8w) page 1/4

ANNEXE 8 CONTENT NO. 8 PWR TYPE 14 uu 14 TEN-FOOT FUEL RODS

The safety analysis report justifying the authorised content is report DOS-18-016472-000 Rev. 5.0.

This content is loaded into a version 1 FCC4 packaging.

1. DEFINITION OF AUTHORISED RADIOACTIVE CONTENT The authorised radioactive content, which are described in Chapter 1.3 of safety analysis report DOS-18-016472-005 Rev. 4.0, consist of new fuel rods for pressurised water reactors (PWR), as described below:

Characteristics of fuel rods Type of assembly array housing these rods 14 x 14 ten foot Maximum total mass per cavity (kg) 856 Maximum total mass of the rods per box (kg) 443 Maximum mass of UO2 (kg) 374/box Nominal active length (mm) 3,048 Maximum number of fuel rods per box 167 Cladding material Zirconium alloy, possibly pre-oxidised, possibly chromium-plated Minimum metal thickness (mm) 0.57 Minimum outer diameter (mm) 10.68 Pellets: ENU (2)

Maximum diameter (mm) 9.40 Maximum oxide density (100% of the theoretical density) 10.96 Maximum initial enrichment (235U/U total) (%) 5 Maximum mass ratio 232U/U total (%) 5x10-8 Maximum mass ratio 234U/U total (%) 0.055 Maximum mass ratio 236U/U total (%) 0.05 Minimum Gd2O3 mass content in gadolinium-carrying rods (%) (1) 2 Maximum absolute internal pressure of fuel rods at 20 °C (in bar) 32.7 (1) Fuel rods with a Gd2O3 content of less than 2% are considered as (non gadolinium -carrying) UO2 fuel rods.

(2) ENU: Enriched Natural Uranium.

F/348/AF-96 (8w) page 2/4