Letter Sequence Other |
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EPID:L-2022-DOT-0007, E-61283 Enclosure 5, Orano NPS Statement of Proprietary Information for the Application for the Validation Request for the FCC-3 Package (Approved, Closed) |
Results
Other: ML22271A186, ML22271A189, ML22271A190, ML22271A450, ML22271A452, ML22271A454, ML22271A455, ML22271A458, ML22271A460, ML22271A461, ML22271A463, ML22271A465, ML22271A466, ML22271A468, ML22271A470, ML22271A471, ML22271A472, ML22271A474, ML22271A476, ML22271A477, ML22271A479, ML22271A481, ML22271A482, ML22271A484, ML22271A486, ML22271A487, ML22271A636, ML22271A637, ML22271A638, ML22271A639, ML22271A640, ML22271A641, ML22271A642, ML22271A643, ML22271A644, ML22271A645, ML22271A646, ML22271A647, ML22271A648, ML22271A649, ML22271A650, ML22271A675, ML22271A677, ML22271A678, ML22271A686, ML22271A688, ML22271A790, ML22271A791, ML22271A792, ML22271A793... further results
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MONTHYEARML22271A6411998-08-19019 August 1998 E-61283 Enclosure 4, 009h1 Ap 2.1-8 TFXDC2108EN Npv, Revision B, Modified RCC Container - Proto 2 - Regulatory Test Programme (Public) Project stage: Other ML22271A6392004-05-0404 May 2004 E-61283 Enclosure 4, 009G1 AP 2.1-7 TFXEDC2104-NPV, Rev. E, Modification of FCC Containers Choice of Prototype 2 Drop Configurations for Regulatory Tests (Public) Project stage: Other ML22271A8002004-10-29029 October 2004 E61283, Enclosure 4, 013c1 Appendix 2.5-3, Document No. FF/DC/01106 Revision a, E0, Safety/Criticality Study of FCC3v2 Containers 14 X 14 8 Foot and 14 X 14 10 Foot Assemblies (Public) Project stage: Other ML22271A8022007-12-19019 December 2007 E61283, Enclosure 4, 013d1 Appendix 2.5-4, FF DC 04191, Revision B, Safety/Criticality Study for FCC4 Packages & 17x17XL Assemblies Justification for an Increased Cavity Cross Section (Public) Project stage: Other ML22271A6462009-01-0101 January 2009 E-61283 Enclosure 4, 009c1 Ap 2.1-3 Document No. NTC-08-00135891E-NPV, Revision No. 01E, Analysis of the Fatigue Strength of the FCC3/FCC4 Containers (Public) Project stage: Other ML22271A4702009-05-0101 May 2009 E-61283 Enclosure 4, 009a1 Appendix 2.1-1, FFDC05090-A EN Npv, FCC3 Containers - Lashing Diagrams (Public) Project stage: Other ML22271A8162009-06-27027 June 2009 E-61283 Enclosure 4, 010d1 Appendix 2.2-4, NTC-08-00118662E-NPV, Rev. 1E, Note on the Characterization of Resin Fs 69 Project stage: Other ML22271A6442010-07-0101 July 2010 E-61283 Enclosure 4, 009b1 Ap 2.1-2 F2, Document No. NEEL-F 2008 DC 117EN, Revision B, FCC3 Containers for Fresh Fuel Assemblies Data for the Fatigue Strength Analysis of the Lifting Boxes and Upper Shell (Public) Project stage: Other ML22271A8152012-04-0202 April 2012 E-61283 Enclosure 4, 010d Appendix 2.2-4 DOS-13-00081778-204-NPV, Rev. 00, Reference to 10373-B-1, Revision 3, Summary Note on the Characterization of Fs 69 Resin Project stage: Other ML22271A4772012-04-30030 April 2012 E-61283 Enclosure 4, 002a Appendix 1.3-1,Document No. DOS-13-00081779-031-NPV, Revision 00, Appendix 1.3-1 - Description of Fuel Rod Boxes for FCC3 Containers (Public) Project stage: Other ML22271A6432012-04-30030 April 2012 E-61283 Enclosure 4, 009j Ap 2.1-10 DOS-13-00081778-110-NPV, Revision 00, Container Prototype No. 2, Drop Test Report (Public) Project stage: Other ML22271A6422012-04-30030 April 2012 E-61283 Enclosure 4, 009i Ap 2.1-9 DOS-13-00081778-109-NPV, Revision 00, Container Prototype No. 1, Drop Test Report (Public) Project stage: Other ML22271A6402012-04-30030 April 2012 E-61283 Enclosure 4, 009h Ap 2.1-8 DOS-13-00081778-108-NPV, Revision 00, Modified RCC Container - Prototype 2 - Regulatory Test Programme (Public) Project stage: Other ML22271A6382012-04-30030 April 2012 E-61283 Enclosure 4, 009g Ap 2.1-7 DOS-13-00081778-107-NPV, Modification of RCC Containers - Selection of Drop Configurations for Prototype 2 in the Context of Regulatory Tests (Public) Project stage: Other ML22271A4842012-04-30030 April 2012 E-61283 Enclosure 4, 002d Appendix 1.3-4, Document No. DOS-13-00081778-034-NPV, Revision 00, Appendix 1.3-4 - Test Report Leaching of Enriched Reprocessed Uranium (Eru) Pellets (Public) Project stage: Other ML22271A4792012-04-30030 April 2012 E-61283 Enclosure 4, 002b Ap 1.3-2 DOS-13-00081779-032-NPV, Revision 00, Appendix 1.3-2 - Drawing of Fuel Rod Boxes for FCC3 Containers (Public) Project stage: Other ML22271A4712012-04-30030 April 2012 E-61283 Enclosure 4, 009b Appendix 2.1-2, Document No. DOS-13-00081779-102-NPV, Revision 00, FCC3 Containers for Fresh Fuel Assemblies – Data for Fatigue Resistance Analysis of Lifting Boxes and Upper Shell (Public) Project stage: Other ML22271A4682012-04-30030 April 2012 E-61283 Enclosure 4, 009a Appendix 2.1-1, Document No. DOS-13-00081779-101-NPV, Revision 00, Table of Contents, FCC3 Containers - Tie-down Diagrams, Areva (Public) Project stage: Other ML22271A4542012-04-30030 April 2012 E-61283 Enclosure 4, 003d Appendix 1.4-4, Document No. DOS-13-00081779-044-NPV, Revision 00, Table of Contents, Photographs of the FCC3 Package (Public) Project stage: Other ML22271A4522012-04-30030 April 2012 E-61283 Enclosure 4, 003c Appendix 1.4-3, Document No. DOS-13-00081778-043-NPV, Revision 00, Table of Contents, Summary of Toughness Tests Project stage: Other ML22271A8012012-09-0303 September 2012 E61283, Enclosure 4, 013d Appendix 2.5-4 (FCC3-FCC4), DOS-13-00081778-504-00-NPV, Rev. 00, Reference to Ffdc 04191, Rev. B, Safety/Criticality Study for FCC4 Packages and 17x17 Xl Assemblies Justification for an Increased Cavity Cross Secti Project stage: Other ML22271A4502012-09-30030 September 2012 E-61283 Enclosure 4, 003b Appendix 1.4-2. Document No. DOS-13-00081779-042-NPV, Revision 1, Drawings of the FCC3 Package, Version 2 (Public) Project stage: Other ML22271A6452013-04-30030 April 2013 E-61283 Enclosure 4, 009c Ap 2.1-3, Document No. DOS-13-00081778-103-NPV, Revision 00, Analysis of the Fatigue Behaviour of FCC3/FCC4 Containers, Tn International Document (Public) Project stage: Other ML22271A7902016-03-31031 March 2016 E-61283 Enclosure 4, 010e Appendix 2.2-5, Document No. DOS-13-00081778-205-NPV, Revision 00, Safety / Criticality Study of FCC3 and FCC4 Containers – Transport of Fuel Rods in Boxes (Public) Project stage: Other ML22271A8092017-09-0101 September 2017 E-61283 Enclosure 4, 009m Ap 2.1-13 DOS-13-00081778-113-NPV, Revision 2, Appendix 2.1-13 Complimentary Analysis of FCC Package Behaviour in Accidental Drop Conditions (Public) Project stage: Other ML22271A6372021-10-0808 October 2021 E-61283 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 Materias (Public) Project stage: Other ML22271A7992022-04-29029 April 2022 E-61283, Enclosure 4, 013c Appendix 2.5-3, Document No. DOS-13-00081778-503-NPV, Revision 00, Reference Document No. Ffdc 01106, Rev. a, Criticality-safety Analysis of FCC3 Containers Version 2 – Assembly Types 14x14 8-foot and 14x14 10-foo Project stage: Other ML22271A1902022-05-10010 May 2022 E-61283 Enclosure 2, Certificate of the French Competent Authority F/347/AF-96 (Gy), FCC-3 Transport Package (French Version) (Public) Project stage: Other ML22271A1892022-05-10010 May 2022 E-61283 Enclosure 1, Certificate of the French Competent Authority F/347/AF-96 (Gy), FCC-3 Transport Package (English Version) Project stage: Other ML22271A6502022-05-13013 May 2022 E-61283 Enclosure 4, 009e1 Ap 2.1-5, Framatome, Document No. D02-ARV-01-186-616, Revision a, FCC 3 - Containers for Fresh Fuel Assemblies - Stacking Behaviour (Non-proprietary) Project stage: Other ML22271A4742022-05-16016 May 2022 E-61283 Enclosure 4, DOS-19-021165-001-NPV, Version 2.0, Chapter 1.2, Administrative Information (Public) Project stage: Other ML22271A8072022-05-18018 May 2022 E-61283 Enclosure 4, 009k Appendix 2.1-11, Document No. DOS-19-021165-011-NPV, Version 1.o, Justification of the Performance of the FCC3 Shell Fasteners During a 9m Vertical Drop (Public) Project stage: Other ML22271A4762022-05-18018 May 2022 E-61283 Enclosure 4, 002 DOS-19-021165-002-NPV, Chapter 1.3, Specifications Relating to Radioactive Content (Public) Project stage: Other ML22271A4822022-06-0303 June 2022 E-61283 Enclosure 3, 002c1 Ap 1.3-3 Dwg FFDC05098-EN Npv, Revision 3.0, STR - Study Report (Public) Project stage: Other ML22271A1862022-07-21021 July 2022 E-61283 Enclosure 6, Document No. DOS-18-016471-000, Versions 1.0 and 5.0, Summary of Changes Between Version 1.0 to Version 2.0 for Safety Analysis Report for FCC-3 (File: Nte 22-005637-000-2.0-FCC3) (Public) Project stage: Other ML22271A4552022-08-0202 August 2022 E-61283 Enclosure 4, 003e Appendix 1.4-5, Document No. DOS-19-021166-010-NPV, Revision 0, Analysis of the Ageing Mechanisms of the Fcc3 and FCC4 Package Models (Public) Project stage: Other ML22271A1842022-08-0202 August 2022 E-61283 Enclosure 5, Orano NPS Statement of Proprietary Information for the Application for the Validation Request for the FCC-3 Package Project stage: Request ML22271A8082022-08-0303 August 2022 E-61283 Enclosure 4, 009l Appendix 2.1-12 DOS-13-00081778-112-NPV, Rev. 1, Appendix 2.1-12 FCC Packaging Rod Boxes - Proof of the Mechanical Strength of Box Equipment (Public) Project stage: Other ML22271A7942022-08-0303 August 2022 E-61283 Enclosure 4, 013a Appendix 2.5-1, Document No. DOS-19-021165-015-NPV, Version 1.0, Safety Analysis Report (Public) Project stage: Other ML22271A8102022-08-0303 August 2022 E-61283 Enclosure 4, 009n Appendix 2.1-14 DOS-19-021165-012-NPV, Version 1.0, Variation in the Mechanical Properties of Shell and Screw Steels Between 40°C …(Public) Project stage: Other ML22271A8122022-08-0303 August 2022 E-61283, Enclosure 4, 010a Appendix 2.2-1, DOS-19-021165-018-NPV, Version 1.0, Reference to D02-ARV-01-198-455 (Translation of D02-ARV-01- 167-814), Justification by Cfd Simulation of the Thermal Behavior of the FCC Container Project stage: Other ML22271A8132022-08-0303 August 2022 E-61283, Enclosure 4, 010a1 Ap 2.2.1 FFP_D02-ARV-01-198-455, Revision a, Justification by CFO Simulation of the Thermal Behavior of the FCC Container; Replacing Former Chapters 2.2-1 (Pved DC 04 055) and 2.2-2 (NEPL-F 2018 DC 152) (Public) Project stage: Other ML22271A8142022-08-0303 August 2022 E-61283 Enclosure 4, 010c Appendix 2.2-3, FS1-0062270, Rev. 1 (DOS-18-016472-017 (En), Rev. 1), Behavior of Rod Made of M5 Framatome or Zircaloy-4 Alloy Subjected to the IAEA Thermal Test in FCC Packaging (Public) Project stage: Other ML22271A1882022-08-0303 August 2022 E-61283, Transmittal Letter from Orano to DOT, Application for Validation of French Competent Authority Certificate F/347/AF-96 for Model No. FCC-3 Transport Package Project stage: Request ML22271A8112022-08-0303 August 2022 E-61283 Enclosure 4, 010 Chapter 2.2, Document No. DOS-19-021165-013-NPV, Version 1.0, Thermal Analysis (New Reference DOS-19-021165-013, Revision 1.0) (Public) Project stage: Other ML22271A7912022-08-0303 August 2022 E-61283 Enclosure 4, 010f Appendix 2.2-6 Document No. DOS-13-00081778-206-NPV, Revision 0, Thermal Behaviour of the FCC Packaging Under Normal Conditions of Transport (Public) Project stage: Other ML22271A8062022-08-0303 August 2022 E-61283 Enclosure 4, 013f, Appendix 2.5-6, Document No. FFDC00561EN, Criticality Safety Study-Fresh UO2 Fuel Transportation casks-Determining the Uncertainties Using Cristal, Revision 4 (Public) Project stage: Other ML22271A7972022-08-0303 August 2022 E-61283 Enclosure 4, 013b Appendix 2.5-2, Document No. DOS-19-021165-016-NPV, Version 1.0, Safety Analysis Report-Reference Ffdc 01046 E0, Version 3.0, Safety/Criticality Study of FCC3 and FCC4 Containers –Transport of Fuel Rods in Boxes (P Project stage: Other ML22271A7922022-08-0303 August 2022 E-61283 Enclosure 4, 012 Appendix 2.4, Document No. DOS-13-00081778-400, Revision 1, Analysis of External Dose Rates (Public) Project stage: Other ML22271A7932022-08-0303 August 2022 E-61283 Enclosure 4, 013 Chapter 2.5, Version 1, Document No. DOS-19-021165-014-NPV, Safety Analysis Report-Criticality-Safety Analysis (Public) Project stage: Other 2013-04-30
[Table View] |
Text
Non-prorietary version Formulaire : PM04-4-MO-6 rév. 03 Orano NPS SAFETY ANALYSIS REPORT Unrestricted Orano CHAPTER 1.2 ADMINISTRATIVE INFORMATION FCC3 Prepared by Checked by Identification :
DOS-19-021165-001-NPV Vers. 2.0 Page 1 / 7 Tableofcontents Statusofrevision 2
- 1. Purpose 3
- 2. Packagedesigner 3
- 3. Description 3
- 4. Requirementsfortransportation 3
- 5. Markingandlabelling 5
- 6. Modesoftransport 5
- 7. Applicablecodesandregulations 5
- 8. References 5
Listofappendices 6
0 orano
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification :
DOS-19-021165-001-NPV Vers.
2.0 Page 2 of 7 Non-proprietary version Status of revision Version Date Purpose and record of revisions Prepared by / Verified by Old reference: DOS-13-00081779-020 0
04/2012 Initial issue:
Revision of summary note TFXDC 2159 rev. G with sections 1, 4.4, 4.5 and 4.6 Reference to applicable regulations 1
10/2016 Applicable regulation updated Deletion of the exclusive use transport requirement Replacement in French original of the term "conteneur" (container) by "emballage" (packaging).
Deletion of Conclusion paragraph - 4.2.1 New reference: DOS-19-021165-001 1.0 02/2019 Added possibility to define the package as type A 2.0 See 1st page Update of the applicable regulation Replacement of term radiation intensity by dose rate
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification :
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2.0 Page 3 of 7 Non-proprietary version
- 1.
Purpose The purpose of this document is to provide administrative information relating to the FCC3 package model.
- 2.
Package designer The designer of the FCC3 package model is:
Framatome 10, rue Juliette Récamier 69456 LYON CEDEX 06 The applicant is:
Orano NPS 1, rue des Hérons 78180 MONTIGNY-LE-BRETONNEUX
- 3.
Description The fresh nuclear fuel for use in powering PWR nuclear power plants is made up of fuel rods assembled to form an array. These products need to be transported between various production sites (factories) and/or points of use (nuclear power plants) either in the form of fuel assemblies or in the form of non-assembled rods.
The Safety Analysis Report covers the transportation of the following contents:
fuel assemblies with a nominal active length of 8, 10 or 12 feet. Fuel assemblies with a length of 12 feet may or may not be provided with rod clusters, non-assembled rods for assemblies with a nominal active length of 8, 10 and 12 feet, in packagings designated throughout this document by the term "FCC3".
This "FCC3" packaging uses the shells formerly used by the "RCC3" packaging, but incorporates a new internal equipment system which is available in two versions depending on the content envisaged:
Version 1: for fuel assemblies composed of a 17x17 or 15x15 square fuel rod array or for non-assembled fuel rods grouped in channels, Version 2: for fuel assemblies composed of a 14x14 square fuel rod array (8 or 10-foot).
The rods in either of these versions can be made from Enriched Natural Uranium (ENU) or from Enriched Reprocessed Uranium (ERU).
- 4.
Requirements for transportation 4.1.
Requirements for transportation of LSA materials in industrial packages Radioactive fissile materials are classified LSA II or LSA III in accordance with reference [1]
for the transportation of ENU (§ 4.2 of Chapter 1.3) and ERU (§ 4.3 of Chapter 1.3).
The package can be defined as a Type 2 Fissile Industrial Package (IP-2).
4.2.
Requirements for transportation of LSA materials in type A packages The activity of radioactive materials contained in the FCC3 is no more than 1 A2 for the transportation of ENU (§ 4.2 of Chapter 1.3).
The package can be defined as a type A package.
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification :
DOS-19-021165-001-NPV Vers.
2.0 Page 4 of 7 Non-proprietary version 4.3.
Determination of transport indices 4.3.1.
Transport index for radiation exposure monitoring Radiological monitoring measurements are taken prior to any shipment to enable the transport index to be calculated.
4.3.2.
Determination of Criticality-Safety Index The criticality safety index is calculated in accordance with Articles 525 and 686 of the Regulation reference [1], covered in Chapter 2.5.
Depending on the type of assembly, the number N of packages taken into account in accordance with Articles 684 and 685 varies. This number of packages N calculated in the criticality studies is used to determine the value of the criticality safety index (CSI) by the formula CSI = 50 / N. The following table presents the CSI values obtained from Chapter 2.5:
Content Number of packages CSI Non assembled rods all types Infinite 0
Assemblies 14x14 Infinite 0
15x15 80 0.625 17x17 80 0.625 4.4.
Determination of package category As stated in § 4 of Chapter 1.3, the FCC3 packaging is designed and fabricated for the exclusive shipment of Low Specific Activity radioactive fissile materials (LSA II or LSA III according to reference [1] for ENU and ERU).
Radiological monitoring measurements are taken prior to any shipment to enable the transport index to be calculated (See Paragraph 4.3.1).
When a packaging is loaded to maximum capacity, the maximum dose rate at any point on its outer surface is in the order of:
28 Sv/h with ERU-based assemblies (4.25%) - (see Appendix 1.2-1)
The package category is determined from the Transport Index (TI - see § 4.3.1) and the measured maximum dose rate. The tables in Article 529 of reference [1], reproduced in the table below, indicate the package categories according to these parameters.
Transport index Maximum dose rate at any point on the outer surface Category 0(1)
No more than 0.005 mSv/h I-WHITE More than 0 but no more than 1 More than 0.005 mSV/h but no more than 0.5 mSV/h II-YELLOW More than 1 but no more than 10 More than 0.5 mSV/h but no more than 2 mSV/h III-YELLOW More than 10 More than 2 mSV/h but less than 10 mSV/h III-YELLOW (2)
(1) If the measured TI is not over 0.05, its value may be reduced to zero in accordance with paragraph c) of Article 523 of reference [1].
(2) Packages in this category must be transported under "exclusive use".
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification :
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2.0 Page 5 of 7 Non-proprietary version 4.5.
Empty packaging The packaging may be transported as an excepted package subject to compliance with the conditions of Article 427 of reference [1].
- 5.
Marking and labelling Marking and labelling must conform to the requirements of the Regulations per reference [1]. The conformity of marking and labelling must be checked before shipment as indicated in the Chapter 1.7 of this document.
- 6.
Modes of transport Authorised modes of transport for the FCC3 packaging are transportation by road, rail, river and/or sea, for which the applicable regulations are defined in § 7.
In the case of river transport, a limit of 100 A2 per hold or compartment of the vessel is imposed for LSA II or LSA III materials (Table 6 of reference [1]).
- 7.
Applicable codes and regulations As a type IP-2 or a type A container loaded with fissile materials, the FCC3 packaging and its content are compliant with the requirements, regulations, agreements or recommendations enumerated below:
Regulations for the Safe Transport of Radioactive Material, Specific Safety Requirements, No.
SSR-6 (Rev. 1), 2018 Edition; European agreement concerning the International Carriage of Dangerous Goods by Road (ADR);
Regulations concerning the International Carriage of Dangerous Goods by Rail (RID);
European Agreement concerning the International Carriage of Dangerous Goods by Inland Waterways (ADN);
International Maritime Dangerous Goods Code (IMDG code published by the IMO);
Order of 29 May 2009 concerning the Carriage of Dangerous Goods by Terrestrial Routes (TMD Order);
Order of 23 November 1987 (amended) concerning the Safety of Shipping, Division 411 of the attached Regulations (RSN Order).
The above Regulations repeat in their entirety the requirements set forth in the IAEA Transport Regulation, reference [1], governing radioactive materials, containers, packages and testing.
Proof of compliance of the package is presented in Chapter 1.6 with reference to the IAEA Regulation.
- 8.
References
[1] Regulations for the Safe Transport of Radioactive Material, IAEA Specific Safety Requirements, No. SSR-6 (Rev. 1), 2018 Edition.
[2] Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material, Safety Guide, No. SSG-26, 2012 Edition.
Formulaire : PM04-4-MO-6 rev. 03 Unrestricted Orano Orano NPS Identification :
DOS-19-021165-001-NPV Vers.
2.0 Page 6 of 7 Non-proprietary version List of appendices Appendix Title No. of pages 1.2-1 Radiological inspection report 1
TOTAL 1
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2.0 Page 7 of 7 Non-proprietary version Appendix 1.2-1 RADIOLOGICAL INSPECTION REPORT
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4 INSTALLATION: ASSEMBLAGE Ml.,. t APPAREIL UTILISE: BabyUne Rev. I DATE DU CONTROLE: 2110&IH DEIIANDEUR: Mme ROBIN CON I ROLt: OU Dl:.811 IJt_ DOSt. ABSOR8lt CONCERNANT N ASSlM81...AGl URl 01r.A N* ~U1ljj_
RESULTAT: an uGy/h,Facteur de qualit6:1.
IS1 Brull de fond 4
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- -1 COOCHI A 11 CM AVK PAOTKTION 21 21 iAUnla.&DII! COUCHe A 1.. CM AWC PRCn'IC110N 7
IMSPUN.AOE COUCHE A,o CM AVK l"flOTK'l10H 10 12 OBSERVATION :
DIFFUSION: Mme ROBIN Mr TEMPERTON SPR.
RESPONSABLE SPR BOURDIN Gilbert NOM:
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