Letter Sequence Other |
|---|
|
Results
Other: ML22277A727, ML22277A728, ML22277A729, ML22277A730, 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, ML22277A778, ML22277A779... further results
|
MONTHYEARML22277A7611998-08-19019 August 1998
E-61285, Enclosure 4, 009h1 Appendix 2.1-8, Document No. TFXDC2108, Modified RCC Container - Proto 2 - Regulatory Test Programme (Public)
Project stage: Other
ML22277A7592004-05-0505 May 2004
E-61285, Enclosure 4, 009g1 Appendix 2.1-7, Document No. TFXEDC2104, Revision E, Modification of RCC Containers Choice of Prototype 2 Drop Configurations for Regulatory Tests (Public)
Project stage: Other
ML22277A7832004-10-29029 October 2004
E-61285, Enclosure 4, 013c1 Appendix 2.5-3, Document No. FF/DC/01106 E0, Revision a, Safety/Criticality Study of FCC3v2 Containers 14 X 14 8 Foot and 14 X 14 10 Footassemblies (FCC-3/FCC-4) (Public)
Project stage: Other
ML22277A7852007-12-19019 December 2007
E-61285, Enclosure 4, 013d1 Appendix 2.5-4, Document No. FF/DC/04191, Revision B, Safety/Criticality Study for FCC4 Packages & 17x17XL Assemblies Justification for an Increased Cavity Cross Section (Public)
Project stage: Other
ML22277A7512009-01-0101 January 2009
E-61285, Enclosure 4, 009c1 Ap 2.1-3 Document No. NTC-08-00135891E-NPV, Revision 01E, Analysis of the Fatigue Strength of the FCC3/FCC4 Containers (Public)
Project stage: Other
ML22277A7732009-06-27027 June 2009
E-61285, Enclosure 4, 010d1 Appendix 2.2-4, Document No. NTC-08-00118662E-NPV, Revision 1E, Note on the Characterization of Resin Fs 69 (Public)
Project stage: Other
ML22277A7492012-01-18018 January 2012
E-61285, Enclosure 4, 009b1 Appendix 2.1-2, Document No. NEEL-F 2008 DC 118, Revision B E1 (Npv), FCC4 Containers for Fresh Fuel Assemblies Data for the Fatigue Strength Analysis of the Lifting Boxes and Upper Shell (Public)
Project stage: Other
ML22277A7722012-04-0202 April 2012
E-61285, Enclosure 4, 010d Appendix 2.2-4, Document No. DOS-13-00081778-204-NPV, Revision 00, Reference to 10373-B-1, Revision 3, Summary Note on the Characterisation of Fs 69 Resin (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7382012-04-0202 April 2012
E-61285 Enclosure 4, 003d Appendix 1.4-4, Document No. DOS-13-00081778-044-NPV, Rev. 00, Reference to Photographs_FCC4, Rev. 0, Photographs of the FCC4 Package (Public)
Project stage: Other
ML22277A7622012-04-0202 April 2012
E-61285, Enclosure 4, 009i Appendix 2.1-9, Document No. DOS-13-00081778-109-NPV, Revision 00, Reference to Tfx DC 2087, Revision a, Container Prototype n°1 – Drop Test Report (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7972012-04-0202 April 2012
E-61285 Enclosure 4, 002d Appendix 1.3-4, Document No. DOS-13-00081778-034-NPV, Rev. 00, Reference to SQ/95/602PBO/CC, Revision 0,, Leaching Tests on Enriched Reprocessed Uranium (Eru) Pellets (Public)
Project stage: Other
ML22277A7822012-04-0202 April 2012
E-61285, Enclosure 4, 013c Appendix 2.5-3, Document No. DOS-13-00081778-503-NPV, Revision 00, Reference to Ffdc 01106, Revision a, Criticality-safety Analysis of FCC3 Containers Version 2-Assembly Types 14x14 8-foot and 14x14 10-ft (FCC-3/F
Project stage: Other
ML22277A7482012-04-0202 April 2012
E-61285, Enclosure 4, 009b Appendix 2.1-2, Document No. DOS-13-00081778-102-NPV, Rev 00, Reference to NEEL-F 2008 DC 118, Rev. B, FCC4 Containers for Fresh Fuel Assemblies – Data for Fatigue Resistance Analysis of Lifting Boxes and Upper Sh
Project stage: Other
ML22277A7602012-04-0202 April 2012
E-61285, Enclosure 4, 009h Appendix 2.1-8, Document No. DOS-13-00081778-108-NPV, Revision 00, Reference to Tfx DC 2108, Revision B, Modified RCC Container - Prototype 2 - Regulatory Test Programme (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7582012-04-0202 April 2012
E-61285, Enclosure 4, 009g Appendix 2.1-7, Document No. DOS-13-00081778-107-NPV, Revision 00, Reference to Tfxedc 2104, Revision E, Modification of RCC Containers - Selection of Drop Configurations for Prototype 2 in the Context of Regulato
Project stage: Other
ML22277A7632012-04-0202 April 2012
E-61285, Enclosure 4, 009j Appendix 2.1-10, Document No. DOS-13-00081778-110-NPV, Revision 00, Reference to Tfxe DC 2132, Revision B, Container Prototype No. 2 – Drop Test Report (FCC-3 - FCC4) (Public)
Project stage: Other
ML22277A7842012-09-0303 September 2012
E-61285, Enclosure 4, 013d Appendix 2.5-4, Document No. DOS-13-00081778-504-NPV, Rev. 00, Reference to Ffdc 04191, Rev. B, Safety/Criticality Study for FCC4 Packages, 17x17 Xl Assemblies Justification for an Increased Cavity Cross (FCC-3/FC
Project stage: Other
ML22277A7472015-06-0909 June 2015
E-61285, Enclosure 4, 009a1 Ap 2.1-1 Document No. FFDC05091, Revision B (Npv, English), FCC-4 Lashing Diagrams (Public)
Project stage: Other
ML22277A7742015-12-0101 December 2015
E-61285, Enclosure 4, 010e Appendix 2.2-5, Document No. DOS-13-00081778-205-NPV, Revision 00, Analysis of the Impact of Glycerine on the Thermal Safety Analyses (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7662016-09-0101 September 2016
E-61285, Enclosure 4, 009m Appendix 2.1-13, Document No. DOS-13-00081778-113-NPV, Revision 2, Complementary Analysis of FCC Package Behaviour in Accidental Drop Conditions (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7642018-05-18018 May 2018
E-61285 Enclosure 4, 009k Ap 2.1-11 DOS-19-021165-011-NPV, Version 1.0, Justification of the Performance of the FCC3 Shell Fasteners During a 9m Vertical Drop (FCC-3/FCC-4) (Public)
Project stage: Other
ML22277A7572021-10-28028 October 2021
E-61285 Enclosure 4, 009f1 Ap 2.1-6 FFDC04223-EN Npv Revision 4.0, Transportation in FCC Container Mechanical Aspects Related to a Change in the Fuel Assembly Materials (FCC-3/FCC-4) (Public)
Project stage: Other
ML22277A7702022-04-29029 April 2022
E-61285, Enclosure 4, 010a1 Appendix 2.2-1, Document No. FFP_D02-ARV-01-198-455, Justification by CFO Simulation of the Thermal Behavior of the FCC Container - FCC (Public)
Project stage: Other
ML22277A7342022-05-23023 May 2022
E-61285 Enclosure 4, Chapter 1.4, Document No. DOS-19-021166-005-NPV, Version 1.0, Specification Relating to the Packaging (Public)
Project stage: Other
ML22277A7962022-06-0303 June 2022
E61285 Enclosure 4, 002c1 Appendix 1.3-3, Document No. FFDC05098-EN, Revision 3.0, Impact Strength of Zr Alloys Proposal for the Specification of the Cladding Materials in the Shipment Approval (Public)
Project stage: Other
ML22277A7272022-06-13013 June 2022
E-61285 Enclosure 1, French Approval Certificate of a Package Design, Number F/348/AF-96 (Revision Gw), English
Project stage: Other
ML22277A7282022-06-13013 June 2022
E-61285 Enclosure 2, French Approval Certificate of a Package Design, Number F/348/AF-96 (Revision Gw), French (Public)
Project stage: Other
ML22277A7292022-08-0202 August 2022
E-61285 Enclosure 5 Orano NPS Statement of Proprietary Information, FCC-4 Application Submitted on August 18, 2022 (Public)
Project stage: Other
ML22277A7782022-08-0303 August 2022
E-61285, Enclosure 4, 013a Appendix 2.5-1, Doc. No. DOS-19-021165-015-NPV, Version 1.0, Ref. to Ffdc 00817 E0, Version 4.0, Safety/Criticality Study of FCC3 and FCC4 containers-15x15 and 17x17 assemblies-7x17 Xl, 17x17 EPR, 16x16 and 18x1
Project stage: Other
ML22277A7792022-08-0303 August 2022
E-61285, Enclosure 4, 013a1 Appendix 2.5-1, Document No. FF/DC/00817 E0, Revision 4.0, Safety/Criticality Study of FCC3 and FCC4 Containers 15x15 and 17x17 Assemblies 17x17 Xl, 17x17 EPR, 16x16 and 18x18 Assemblies (Public)
Project stage: Other
ML22277A7922022-08-0303 August 2022
E-61285 Enclosure 4, 002 Chapter 1.3, Document No. DOS-19-021166-002-NPV, Version 2.0, Specifications Relating to Radioactive Content (Public)
Project stage: Other
ML22277A7772022-08-0303 August 2022
E-61285, Enclosure 4, 013 Chapter 2.5, Document No. DOS-19-021165-014-NPV, Version 1.0, Criticality-Safety Analysis (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7862022-08-0303 August 2022
E-61285, Enclosure 4, 013e Appendix 2.5-5, Document No. DOS-13-00081778-505-NPV, Rev. 00, Reference to FS1-001285, Criticality-Safety Study FCC4 Containers Justification of the Increase in the Cross Section of the Cavity (FCC-3/FCC-4 (Publi
Project stage: Other
ML22277A7692022-08-0303 August 2022
E-61285, Enclosure 4, 010a Appendix 2.2-1, Document No. DOS-19-021165-018-NPV, Version 1.0, SAR, Reference to D02-ARV-01-198-455, Revision a, Justification by Cfd Simulation of the Thermal Behavior of the FCC Container (FCC-3 and FCC-4) (Pu
Project stage: Other
ML22277A7902022-08-0303 August 2022
E-61285 Enclosure 4, 000 Document No. DOS-19-021166-000-NPV, Revision 2.0, Table of Contents, Orano NPS Safety Analysis Report for FCC-4 and the Reference Documents (Public)
Project stage: Other
ML22277A7762022-08-0303 August 2022
E-61285, Enclosure 4, 012 Chapter 2.4, Document No. DOS-13-00081778-400-NPV, Revision 1, Analysis of External Dose Rates (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7952022-08-0303 August 2022
E-61285 Enclosure 4, 002c Appendix 1.3-3, Document No. DOS-19-021165-021-NPV, Version 1.0, Safety Analysis Report, FCC-3 and FCC-4, Reference to Ffdc 05098 EN, Version 3.0, Impact Strength of Zr Alloys...(Public)
Project stage: Other
ML22277A7932022-08-0303 August 2022
E-61285 Enclosure 4, 002a Appendix 1.3-1, Document No. DOS-13-00081778-031-NPV, Rev. 1, Description of Red Boxes for FCC4 Containers (Public)
Project stage: Other
ML22277A7802022-08-0303 August 2022
E-61285, Enclosure 4, 013b Appendix 2.5-2, Document No. DOS-19-021165-01-NPV, Version 1.0, Reference to Ffdc 01046 E0, Version 3.0, Safety/Criticality Study of FCC3 and FCC4 containers-Transport of Fuel Rods in Boxes (Public)
Project stage: Other
ML22277A7872022-08-0303 August 2022
E-61285, Enclosure 4, 013e1 Appendix 2.5-5, Document No. FS1-0012857 E0, Revision 1, Safety Criticality Analysis, FCC4 Fuel Shipping Casks - Justification of the Enlarged Neutronic Cavity Section (Public)
Project stage: Other
ML22277A7442022-08-0303 August 2022
E-61285, Enclosure 4, 008 Chapter 1.9, Document No. DOS-19-021166-008-NPV, Version 1.0, Quality Assurance (Public)
Project stage: Other
ML22277A7812022-08-0303 August 2022
E-61285, Enclosure 4, 013b1 Appendix 2.5-2, Document No. FF/DC/01046 E0, Version 3.0, Safety/Criticality Study of FCC3 and FCC4 Containers Transport of Fuel Rods in Boxes (Public)
Project stage: Other
ML22277A7552022-08-0303 August 2022
Enclosure 4, 009e1 Appendix 2.1-5, Document No. Ffp D02-ARV-01-186-618-NPV, Revision a, FCC 4 - Containers for Fresh Fuel Assemblies - Stacking Behaviour (Public)
Project stage: Other
ML22277A7942022-08-0303 August 2022
E-61285 Enclosure 4, 002b Appendix 1.3-2, Document No. DOS-13-00081778-032-NPV, Rev. 1, Drawing of Rod Boxes for FCC4 Containers, List of Drawings (Public)
Project stage: Other
ML22277A7502022-08-0303 August 2022
E-61285, Enclosure 4, 009c Appendix 2.1-3, Document No. DOS-13-00081778-103-NPV, Revision 00, Reference to NTC-08-00135891, Revision 1, Analysis of the Fatigue Behaviour of FCC3/FCC4 Containers, Tn International Document (Public)
Project stage: Other
ML22277A7682022-08-0303 August 2022
E-61285, Enclosure 4, 010 Chapter 2.2, Document No. DOS-19-021165-013-NPV, Version 1.0, Thermal Analysis (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7752022-08-0303 August 2022
E-61285, Enclosure 4, 010f Appendix 2.2-6, Document No. DOS-13-00081778-206-NPV, Revision 00, Thermal Behaviour of the FCC Packaging Under Normal Conditions of Transport (FCC-3 - FCC-4) (Public)
Project stage: Other
ML22277A7882022-08-0303 August 2022
E-61285, Enclosure 4, 013f Appendix 2.5-6, Document No. DOS-13-00081778-506-NPV, Rev. 00, Nuclear Logistics Operations, Reference to Ffdc 00561, Rev. 4, Critically Safety Study Transport Package for Fresh UO2 Fuel (Uncertainties) (FCC-3/FCC
Project stage: Other
ML22277A7422022-08-0303 August 2022
E-61285 Enclosure 4, 006 Chapter 1.7, Document No. DOS-19-021166-006-NPV, Version 1.0, Instruction for Use of Packaging (Old Reference: DOS-13-00081778-070) (Public)
Project stage: Other
ML22277A7402022-08-0303 August 2022
E-61285 Enclosure 4, 004 Chapter 1.5, Document No. DOS-19-021166-003-NPV, Version 2.0, Package Performance Characteristics (Public)
Project stage: Other
2015-12-01
[Table View] |
Text
Non-proprietary version Form: PM04-4-MO-6 rev. 03 Orano NPS SAFETY ANALYSIS REPORT Unrestricted Orano APPENDIX 1.4-5 ANALYSIS OF THE AGEING MECHANISMS OF THE FCC3 AND FCC4 PACKAGE MODELS FCC3/FCC4 Prepared by / signature Verified by / signature Identification:
DOS-19-021166-010-NPV Version 1.0 Page 1 / 6 Contents Statusofrevision 2
- 1. Introduction 3
- 2. Descriptionofpackaginguse 3
- 3. Materials 3
- 4. Potentialeffectsonthepackagecomponents 4
- 5. Conclusion 6
- 6. References 6
()
orano
Form: PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification:
DOS-19-021166-010-NPV Version 1.0 Page 2 of 6 Non-proprietary version Status of revision Version Date Purpose and record of revisions Prepared by/ Verified by 1.0 See page 1 First issue
Form: PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification:
DOS-19-021166-010-NPV Version 1.0 Page 3 of 6 Non-proprietary version
- 1.
Introduction The purpose of this chapter is to present the aspect justifying that the package as defined in this safety analysis report meets the requirements in section 613A of the IAEA regulations <1>.
- 2.
Description of packaging use The FCC3 and FCC4 models are intended for the transport of fresh fuel as type IP-2 or type A package containing fissile material.
The FCC3 and FCC4 packagings are used as per the requirements of chapter 1.7, particularly with dry loading/unloading of content. The loading and unloading operations are carried out:
With the internal equipment in a vertical position for the assemblies with or without control clusters, With the internal equipment equipped with rod boxes in a horizontal position for non-assembled rods.
The maximum power of the contents is W.
The loaded packagings are designed to be transported on public highways in a horizontal position.
- 3.
Materials The materials used in the components of the FCC3 and FCC4 packagings are described in chapter 1.4.
The content is described in chapter 1.3. It is constituted of leak-tight zirconium alloy rods enclosing non-irradiated enriched uranium pellets which are either placed in a metal structure forming the fuel assemblies or take the form of non-assembled rods. The non-assembled rods are collected in rod boxes, whose constituent materials are specified in chapter 1.3-1.
The main package materials (important with regard to containment safety, radiation protection and criticality safety functions, along with the drop and fire protection functions) subjected to the transport conditions are listed in the table below:
Component Material Corrosion protection coating Lower and upper half-shells Closure flange Steels and
( and ),,
Steels,
Steel Grade LF2 Yes (Corrosion protection coating +
paint coating)
Internal equipment:
Doors and frame, top and bottom plates, connection of doors with frame, connection of top and bottom plates with frame and doors, Stainless steels Half-shells bolted connections:
Special head screws Nuts of special head screws
( class )
or Yes Neutron-absorbing resin contained in the doors and frame (see table 1.4.1 of chapter 1.4)
Axial shock absorber Balsa
Form: PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification:
DOS-19-021166-010-NPV Version 1.0 Page 4 of 6 Non-proprietary version Component Material Corrosion protection coating Shock absorber closure plate Shock absorber bolted connections with the upper shell Rod box:
radial spacers and radial support plate, axial spacers and axial end support plate
- stainless steel Rod boxes:
radial compensation spacers Aluminium alloy Claddings Zirconium alloy M5Framatome and Zircaloy-4
- 4.
Potential effects on the package components On the basis of the transport conditions (overland, maritime, river), the following effects must be taken into account:
The effect of moisture (external environment),
The effect of temperature on the materials, The effect of irradiation due to the presence of radioactive material, The effect of fatigue caused by the transport method.
4.1.
The effects of moisture The following section details the design and operating principles used to evaluate the effects of moisture.
As the packagings are dry-loaded in buildings protected from adverse weather, the moisture in the packaging corresponds to that of the room at the time the contents are loaded/unloaded.
All the outer surfaces of the upper and lower shells are protected by a paint coating or a corrosion protection coating (for the bolted joints of the half-shells for example).
The FCC3 or FCC4 packaging is equipped with a cleanliness gasket for the connection between the half-shells, limiting the risks of water penetrating inside the half-shells.
The metal internal equipments are.
The shock absorbers are formed of a enclosure. The wood is therefore contained in leak-tight enclosures. Before each shipment, the shock absorbers are checked for permissible defects (as defined in chapter 1.4), to detect any deterioration (see chapter 1.7).
As an additional means of prevention:
Before shipment (see chapter 1.7):
Check that the paintwork has not detached from the uninterrupted sections of the packaging, Check that there is no water in the bottom of the lower shell.
To each periodic servicing(see chapter 1.8):
Form: PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification:
DOS-19-021166-010-NPV Version 1.0 Page 5 of 6 Non-proprietary version Search for paintwork defects and restauration if necessary of the defective zones on the inner and outer shell surfaces if deficient paintwork is detected, Visually and functionally check over the entire stroke of all the connecting bolts, with nuts, for the 2 half-shells Systematically check the good overall condition of the packaging.
The checks carried out before each transport and during maintenance operations protect against any corrosion effects caused by moisture for the FCC3 and FCC4 packagings.
Regarding the content, fissile material is contained by the fuel rod claddings and the zirconium alloy welded plugs. The fuel assemblies (composed of fuel rods) are intrinsically designed to operate in a wet environment under high pressure and temperature in the reactor core; as a result, moisture is not expected to affect the containment of the fuel rods in ambient conditions during the regulatory transport period not exceeding one year.
On this basis, as far as the presence of moisture is concerned, the design, the use and the servicing of the FCC3 and FCC4 packages are such that their condition cannot be modified in any manner liable to modify the conclusions of the analysis chapters in this safety analysis report.
4.2.
The effects of temperature on the materials As mentioned in §2, after loading, the packaging releases a maximum power of W.
Regarding the fuel assembly claddings and bearing in mind the low power of the contents and the maximum temperature in normal conditions of transport of + °C (see chapter 2.2), no thermal creep effect is expected throughout the transport period.
Regarding the neutron-absorbing resin in the doors and in the frame of the internal fittings, the maximum temperature reached by the package remains well below the limit operating temperature of the resin (°C). In these low temperature conditions, considering the operating limit, no significant ageing effect is expected for the chemical composition of the resin over the packaging service life (a period at least equal to 37 years, which corresponds to the minimum fatigue service life for the FCC3 and FCC4 packagings as defined in chapter 2.1).
The effects of the maximum temperature in normal conditions of transport (+°C) on the mechanical behaviour of the aluminium in the rod box compensation spacers and on the degradation of the paintwork on the half-shells are negligible. Moreover, as stated in §4.1, checks on the paintwork condition before shipment and during packaging maintenance provide protection against any degradation.
Thus, considering the low thermal power of the contents, no significant effect of thermal ageing on the FCC3 and FCC4 packaging components is expected over the whole service life of the packaging (at least 37 years).
4.3.
The effects of irradiation due to the presence of radioactive material The claddings of the fuel assemblies are made of zirconium alloy type M5Framatome or Zircaloy-
- 4. These materials have a very low neutron absorption cross-section in the thermal domain and do not undergo irradiation ageing due to the neutrons.
As the fuel is not irradiated, the radiation level sustained by the package materials is low. On this basis, variation in the properties of the packaging materials and of the content (see §3) under the effect of irradiation are not significant throughout the service life of the FCC3 or FCC4 packaging and throughout the transport period for the content (no more than one year as per regulations).
Form: PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification:
DOS-19-021166-010-NPV Version 1.0 Page 6 of 6 Non-proprietary version 4.4.
The effects of fatigue caused by the transport methods Fuel assembly cladding stresses in the transport phase are limited by the strength of the packaging structures surrounding them.
Chapter 2.1 shows that the package model withstands the stresses arising from road, maritime and rail transport over a period of at least 37 years, under repeated tie-down and handling conditions (at a rate of transport operations per year for the FCC3 packaging and transport operations per year for the FCC4 packaging).
Further, during each maintenance operation, the FCC3 and FCC4 packagings are subjected to the following checks (see chapter 1.8):
systematic check of the good overall condition of the packaging and replacement of any non-compliant component, 100% surface inspection of the welds connecting the handling boxes and the upper shells, the welds on the reinforcing support angles located on each side of the handling boxes and the peripheral welds between the half-shells and the flanges, Check pin wear, Check for deformation and the good condition of the pin and connection stops (retaining rings, lock pin, set screw, lock washer, presence of thread lock),
Check the condition of the ball locking pins and effective locking in the clevises.
Moreover, the good overall condition of the packaging is checked for each transport operation.
On this basis, as far as the effects of fatigue related to the transport methods are concerned, the design, the use and the servicing of the FCC3 and FCC4 packages are such that their condition cannot be modified in any manner liable to modify the conclusions of the analysis chapters in this safety analysis report throughout the packaging service life (at least 37 years).
- 5.
Conclusion The FCC3 and FCC4 packagings are designed for the transport of fresh fuel rod assemblies or non-assembled fresh fuel rods.
Chapters 1.7 and 1.8 describe the packaging maintenance and use conditions for transport operations.
The analyses conducted in this chapter demonstrate that, with consideration for the guidelines, the safety functions of the FCC3 and FCC4 packagings are not deteriorated due to ageing over a minimum period of 37 years (defined in the fatigue analysis for the conveyances).
Accordingly, the FCC3 and FCC4 package models are designed to meet IAEA regulations <1>
particularly §613A, which states: The design of the package shall take into account ageing mechanisms.
- 6.
References
<1>
Regulations for the safe transport of radioactive material - Specific safety requirements No.
SSR IAEA - see edition applicable to Chapter 1.2.