ML22271A474

E-61283 Enclosure 4, DOS-19-021165-001-NPV, Version 2.0, Chapter 1.2, Administrative Information (Public)

ML22271A474
Person / Time
Site:	Orano USA
Issue date:	05/16/2022
From:	Shaw D TN Americas LLC
To:	Division of Fuel Management
Garcia-Santos N
Shared Package
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References
A33010, L-2022-DOT-0007
Download: ML22271A474 (7)

Text

Unrestricted Orano Orano NPS SAFETY ANALYSIS CHAPTER 1.2 REPORT ADMINISTRATIVE INFORMATION

Prepared by 0 orano

FCC3 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

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Status of revision

Version Date Purpose and record of revisions Prepared by / Verified by

Old reference: DOS-13-00081779-020

Initial issue:

0 04/2012 - Revision of summary note TFXDC 2159 rev. G with sections 1, 4.4, 4.5 and 4.6

- Reference to applicable regulations

- Applicable regulation updated

- Deletion of the exclusive use transport requirement 1 10/2016 - 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 Update of the applicable regulation page Replacement of term radiation intensity by dose rate

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1. Purpose The purpose of this document is to provide adminis trative 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 nee d 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 assemb lies 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 shel ls formerly used by the "RCC3" packaging, but incorporates a new internal equipment system whic h 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 m ade 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 A 2 for the transportation of ENU (§ 4.2 of Chapter 1.3).

The package can be defined as a type A package.

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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 va lue of the criticality safety index (CSI) by the formula CSI = 50 / N. The following t able presents the CSI values obtained from Chapter 2.5:

Content Number of packages CSI

Non assembled rods all types Infinite 0 14x14 Infinite 0 Assemblies 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 measuremen ts 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 Ar ticle 529 of reference [1], reproduced in the table below, indicate the package categor ies 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 More than 0.005 mSV/h but no more than than 1 0.5 mSV/h II-YELLOW More than 1 but no more More than 0.5 mSV/h but no more than than 10 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".

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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 A 2 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 Radioacti ve 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 Ca rriage 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.

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List of appendices

Appendix Title No. of pages

1.2-1 Radiological inspection report 1

TOTAL 1

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Appendix 1.2-1

RADIOLOGICAL INSPECTION REPORT

4

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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 4l6

-- *-* COUCM AU CONTACT 100 110

,uat!MllAGECOUCHEAflCM " N Ml~COUCffAfOOCII 10 12

. - * -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: TEMPERTON Ronny

VISA: 0 \\ j * ---VISA:

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