ML20189A609

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Orano Cover Letter, Rsi Response, FCC-4 Revalidation
ML20189A609
Person / Time
Site: 07103097
Issue date: 06/26/2020
From: Shaw D
Orano USA, TN Americas LLC
To: Boyle R
Division of Fuel Management, US Dept of Transportation, Pipeline & Hazardous Materials Safety Admin
NGSantos NMSS/DFM/STL 415.6999
Shared Package
ML20189A606 List:
References
E-57013, EPID L-2020-NEW-0000
Download: ML20189A609 (10)
v • d • e


Text

June 26, 2020 E-57013 U.S. Department of Transportation Orano USA Columbia Office Attn: Mr. Richard W. Boyle, Chief 7135 Minstrel Way Pipeline & Hazardous Materials Safety Administration Columbia, MD 21045 Tel: (410) 910-6900 Radioactive Materials Branch

@Orano_USA 1200 New Jersey Avenue, S.E.

East Building, PHH-20 Washington, DC 20590

Subject:

Supplemental Information for Application for Validation of French Competent Authority Certificate F/348/AF-96 for Model No. FCC-4 Transport Package

Reference:

[1] NRC letter to U.S. DOT dated April 21, 2020,

Subject:

Application for the Model No. FCC-4 Transport Package - Supplemental Information Needed

[2] TN Americas LLC letter E-55607 dated December 12, 2019,

Subject:

Application for Validation of French Competent Authority Certificate F/348/AF-96 for Model No. FCC-4 Transport Package

[3] TNI letter COR-20-031142-000 version 2.0 dated June 9, 2020,

Subject:

Request for Supplemental Information and Observations

Dear Mr. Boyle:

TN Americas LLC, on behalf of TN International, submits the supplemental information requested by the NRC [1] to complete the review for acceptance of an application [2] for revalidation of French Competent Authority Certificate F/348/AF-96 for Model No. FCC-4, in accordance with §173.473.

Enclosure 1 provides supplemental information provided by TN International [4] that includes listing of drawing, standards and more generally all the written documents requested for the acceptance of the application. The TN Americas LLC affidavit provided with the original application [2] and an affidavit provided by Framatome with the supplemental information [3] provide the statements of proprietary information pursuant to 49 CFR 7.14, 49 CFR 105.30, and 10 CFR 2.390.

Enclosures transmitted herein contain SUNSI. When separated from enclosures, this transmittal document is decontrolled.

E-57013 June 25, 2020 Page 2 of 2 and 3 provide the drawings and standards listed in the supplemental information response [3]. The English version of the French Standard documents is intended for the exclusive and non-collective use by Orano for the U.S. Nuclear Regulatory commission (NRC) review of the application [2]. All network exploitation, reproduction and re-dissemination, even partial, whatever the form (hardcopy or other media), is strictly prohibited. TN Americas requests that access to French Standard documents be limited to only persons reviewing the application, and all copies deleted upon completion of the application review.

Should you have any questions or require additional information to support review of this application, please contact Peter Vescovi by telephone at 336-420-8325, or by e-mail at peter.vescovi@orano.group.

Sincerely, Don Shaw Licensing Manager TN Americas LLC cc: Michael Conroy, U.S. Department of Transportation Don Shaw, TN Americas LLC Laurence Labbe, TN Americas LLC Brigitte Latour, TN International Enclosure(s):

1. TNI letter COR-20-031142-000 (Non-proprietary)
2. RSI-MA-1.zip (Proprietary)
3. RSI-MA-2.zip (Proprietary)
4. Affidavit Pursuant to 10 CFR 2.390

Ref.: COR-20-031142-000 vers. 2.0 Montigny-le Bretonneux, Tuesday, June 9, 2020 Orano TN

Subject:

Request for Supplemental Information and Observations TN International U.S. Department of Transportation Sige Social 1 rue des Hérons Docket no. 71-3097 / EPID L-2020-NEW-0000 F-78180 Montigny-Le-Bretonneux Tél. : +33 (0)1 34 96 50 00 Fax : +33 (0)1 34 96 54 50 French Approval Certificate Number F/348/AF-96, Revision Fq RCS Versailles SIRET 602 039 299 00063 Model No. FCC-4 Package TN International PALOVA

Établissement Nord-Ouest ZA dArmanville Rue des Entrepreneurs F-50700 Valognes

References:

Tél. : +33 (0) 2 33 88 69 88 Fax : +33 (0) 2 33 88 69 99 [1] Safety Analysis Report of Package Model FCC4 - TN International -

RCS Cherbourg SIRET 602 039 299 00105 DOS-19-021166-1.0

[2] French Approval certificate - French Approval Certificate Number F/348/AF-96, TN International PALOMA Revision Fq, Model No FCC-4 transport package

Établissement Sud-Est [3] Request for Supplemental Information and Observations U.S. Department of CD 138B CODOLET BP 64182 Transportation - French Approval Certificate Number F/348/AF-96, Revision Fq F-30204 Bagnols-sur-Cze Cedex Tél. : +33 (0) 4 66 90 33 00 - Docket No. 71-3097 - Model No. FCC-4 Package Fax : +33 (0) 4 66 90 32 03 RCS Nmes SIRET 602 039 299 00097 Enclosed documents:

See in the responses to the requests Important note:

The Drawing, Standards and more generally all the written documents transmitted as well as all the attached documents and information shared are proprietary information and must not be made public or transmitted to a third party.

Additionally, regarding transmitted standards, only one copy is permitted for the U.S.

Nuclear Regulatory Commission (NRC).

TN International S.A au capital de 30 291 000 Euros SIREN 602 039 299 - APE 7112B N° Intracommunautaire :

FR 25 602 039 299 www.orano.group 1/6

REQUEST FOR SUPPLEMENTAL INFORMATION Materials Evaluation RSI-Ma-1 Provide the English translation of all design-basis drawings, package-contents drawings, and any other packaging design information provided as part of the application. Ensure all drawings are legible and define pertinent welding requirements consistent with the application.

Drawings in Chapters 1.3 and 1.4 and Appendices 1.3, 1.4, and 2.1 of the application were provided in French. The drawings, as well as any other supporting design-basis information related to the application, should be translated to English and provided as part of the application to allow the staff to perform an adequate safety review. Further, drawings of the transport contents, as provided in Chapter 1.3 of the application, are not legible and are in French. Ensure that all drawings identify the weld requirements for the packaging consistent with the design assumptions in the safety analysis.

This information is necessary to ensure compliance with the requirements in Paragraphs 607 and 640 of the IAEA SSR-6, Regulations for the Safe Transport of Radioactive Material, 2012 Edition.

Elements given, and information shared in this response are proprietary information.

See below, the answers given for each Chapter or Appendix concerned by the request:

  • Chapter 1.3 (Drawings)

Translation of the following drawings are available as an attachment:

Figure 1.3-1 FUEL ASSEMBLY TYPE 17X17 - 1300 MWE Figure 1.3-2 FUEL ASSEMBLY TYPE 17X17 - 1450 MWE Figure 1.3-3 FUEL ASSEMBLY TYPE 16X16 Figure 1.3-4 FUEL ASSEMBLY TYPE 18X18

  • Appendix 1.3-2 (Drawings)

Translation of the following drawings are available as an attachment.

47-0-01-99-01-00 sheet 2/2 index I: FCC4 rod box - Assembly 47-0-01-99-01-02 index J: Axial spacer 47-0-01-99-01-06 index F: Support plate length 2460 47-0-01-99-01-09 sheets 1 & 2 index G: Radial spacer length 2460 47-0-01-99-01-16 index E: support plate - fixed end 47-0-01-99-01-22 index A: Packing spacer - length 2460 - th. 5 PLA-16-00179264-300-00: FCC4 EPR rod box - Assembly drawing PLA-16-00179264-201-00: Safety drawing of the axial spacer for EPR rod boxes PLA-16-00179264-202-00: Safety drawing of the fixed end support plates of the EPR rod boxes PLA-16-00179264-203-00: Safety drawing for compensation spacers -

Th. 5, EPR rod boxes www.orano.group COR-20-031142-000 vers. 2.0 2/6

  • Chapter 1.4 Figure 1.4-4: Illustration of the FCC4 packaging This figure is an extract from the drawing 229 K 0400 index G given in Appendix 1.4-1 of the FCC4 Package SAR.

About the welds, the complete analysis is performed in Table 1.4-5 of Chapter 1.4 of the FCC4 Package SAR. This table regroups the welds important to the safety of the packaging and gives:

- the identification of the weld,

- the materials used,

- the type of weld,

- the control after manufacturing.

  • Appendices 1.4-1, 1.4-2, 1.4-3 (Drawings)

Each drawing is already provided with an English version: either in subtitles on the same sheet as the French version or on a separate sheet.

  • Appendix 2.1-2 Translation of the Chapter 2.1-2 is available as an attachment.

RSI-Ma-2 Provide the following references cited in the application. Ensure all documents are translated into English.

a. From Appendix 1.3-1, DOS-13-00081778-031_01:
i. Standard NF EN 10088-3 ii. Standard NF EN 485-2
b. From Appendix 1.3-3, FFDC05098 EN:
i. Standard NF EN 10045-1 ii. Reference to method developed by the CEA and AREVA NP and presented to the ASTM Conference at Annecy in June 2001.
c. From Chapter 1.4, DOS-1300081778-040_02:
i. CODAP - 2005 - Section I, Appendix I1.A1 and I1.A2, including Tables I1.A1-1 and I1.A1.2 for Category A.

ii. NF A 35-557 - Metallurgical Products - Special Steels suitable for thermal processing for high-performance external thread fixing components used in mechanical constructions.

iii. NF EN 10113 Hot-rolled weldable products in fine-grain structural steel. Part 1: General conditions for delivery (Classification index: A 36-201).

iv. NF EN 10025 - Hot rolled products in non-alloy structural steels -

Technical requirements for delivery (Classification index: A 35-501).

v. NF EN 10088 Stainless Steels - (Classification index: A 35-574),

Section 3: Technical Conditions relating to the delivery of part-finished products, bars, machined wires and profiles for general purpose use.

vi. NF EN 10028 Flat steel products for pressure vessels.

vii. NF A36-601 Forged steel components for boilers and pressure vessels. Carbon and carbon manganese steels.

www.orano.group COR-20-031142-000 vers. 2.0 3/6

viii. NF EN 10028 Flat steel products for pressure vessels. Stainless steels.

d. From Appendix 1.4-3, FFDC01079EN:
i. Standard 35501 ii. Standard EN 10025 iii. NF EN 10045-1
e. From Appendix 2.2-3, DOS-13-00081778-203_01:
i. AREVA NP document FS1-0004231, Revision 1.0: Volume calculations for different fuel rod designs - Transport problem ii. AREVA NP internal document FD-16-00285, Revision 1.0: Answers to questions by the ASN on EDGAR tests and the Zircaloy-4 model.

This information is necessary to ensure compliance with the requirements in Paragraphs 607 and 640 of the IAEA SSR-6, 2012 Edition.

Elements given, and information shared in this response are proprietary information.

Additionally, regarding transmitted standards, only one copy is permitted for the U.S.

Nuclear Regulatory Commission (NRC).

The references below are available as an attachment.

a. From Appendix 1.3-1, DOS-13-00081778-031_01:
i. NF EN 10088-3.

ii. NF EN 485-2+A1.

b. From Appendix 1.3-3, FFDC05098 EN:
i. NF EN 10045-1 is cancelled and replaced by NF EN ISO 148-1.

ii. Activated Slip Systems and Localized Straining of Irradiated Zr Alloys in Circumferential Loadings - C. Regnard, B. Verhaeghe, F. Lefebvre-Joud and C. Lemaignan

c. From Chapter 1.4, DOS-1300081778-040_02:
i. CODAP - 2005 - Section I, Appendix I1.A1 and I1.A2, including Tables I1.A1-1 and I1.A1.2 for Category A.

ii. NF A35-557.

iii. NF EN 10113-1 is cancelled and replaced by NF EN 10025:

NF EN 10025-1, NF EN 10025-2, NF EN 10025-3, NF EN 10025-4, NF EN 10025-5, NF EN 10025-6.

iv. For NF EN 10025 see section c.iii. above.

v. For NF EN 10088-3 see section a.i. above vi. NF EN 10028-3.

vii. NF A36-601 is cancelled and replaced by NF EN 10222:

NF EN 10222-1 NF EN 10222-2 NF EN 10222-3 NF EN 10222-4 NF EN 10222-5 viii. NF EN 10028-7.

www.orano.group COR-20-031142-000 vers. 2.0 4/6

d. From Appendix 1.4-3, FFDC01079EN:
i. It corresponds to Standard NF A35-501 equivalent to Standard NF EN 10025 given above in section cc.iv. iii.

ii. It corresponds to Standard NF EN 10025, see section c. iii.c.iv above.

iii. NF EN 10045-1 is cancelled and replaced by NF EN ISO 148-1, see section b.i. above.

e. From Appendix 2.2-3, DOS-13-00081778-203_01 (Please find an affidavit as an attachment for the two documents transmitted below):
i. AREVA NP document FS1-0004231, Revision 1.0: Volume Calculations of Various Fuel Rod Designs for Transport.

ii. AREVA NP internal document FD-16-00285, Revision 1.0: Answers to French Safety Authority (ASN) Questions on EDGAR Tests and the Associated Zircaloy-4 Model.

OBSERVATIONS Criticality Safety Evaluation OBS-Cr-1 Provide the chemical composition of the chromium oxides as well as the concentration that will be present within uranium dioxide (UO2).

Certificate of the French Competent Authority No. F/348/AF-96 (Revision Fq) for the Model No. FCC-4 packaging states that, for all contents, the UO2 pellets may contain chromium oxides. The application does not include more specific information about the chemical composition of the chromium oxides including concentrations that will exist within the UO2.

This information is needed to ensure compliance with the requirements in Paragraph 673 of the IAEA SSR-6, 2012 Edition Chromium oxide blended with UO2 is Chromium (III) oxide (or chromia) with the formula Cr2O3.

The nominal Cr concentration of 1600 ppm Cr2O3/UO2, or 1250 ppm Cr/U, is targeted with a small fabrication variability range caused by:

- quality check measurement precision and,

- some variability of the fraction of chromia that volatilizes during sintering.

As stated in the Topical Report (TR) ANP-10340P, chromium content will be maintained within a range of [1250 +150/-450] microgram chromium per gram of uranium (gCr/gU) for each pellet lot.

Ref. ANP-10340P, revision 0 Incorporation of chromia-doped fuel properties in AREVA approved methods - Approved by U.S. NRC - April 2018.

OBS-Cr-2 Justify that ignoring the inclusion of chromium oxide within the UO2 is conservative with respect to criticality safety.

The following criticality analysis files state that the chromium oxides are ignored in the criticality analysis:

  • 107 SUNSI Encl 3 FCC 4 Ap 2.5-1 FFDC00817 EN (175 PUBLIC Encl 4 FCC 4 Ap 2.5-3 FFDC01106EN NPV) that represents Contents Nos. 1, 2, 3, and 11 for the FCC-4, and www.orano.group COR-20-031142-000 vers. 2.0 5/6
  • 109 SUNSI Encl 3 FCC 4 Ap 2.5-2 FFDC01046EN.pdf (173 PUBLIC Encl 4 FCC 4 Ap 2.5-2 FFDC01046EN NPV) that represents Contents Nos. 4, 5, 6, 7, 8, 9, 10, and 12 for the FCC-4.

These files state the following:

The addition into the pellets of capturing compounds (chromium oxide for instance) in quantities close to those of the impurities is ignored in the study of criticality as their presence reduces the reactivity of the assemblies.

The staff has seen studies to support criticality safety analyses for other packages involving UO2 fuel with chromium oxides that show that the reactivity effect of a specific quantity of chromium oxide may be statistically insignificant for a small number of rods. However, the staff requests justification that the proposed level of chromium oxide reduces reactivity if all rods contain chromium oxides.

This information is needed to ensure compliance with the requirements in Paragraph 673 of the IAEA SSR-6, 2012 Edition.

The presence of Cr2O3 in the fuel pellets in the assembly will have a negative reactivity effect due to the chromium capturing feature.

As observed by your staff, the reactivity effect of a specific quantity of chromium oxide may be statistically insignificant for a small number of rods and difficult to be quantified. If all rods contain the nominal chromium oxides content, the reactivity reduction remains a small effect and can be quantified by calculation.

For example: the introduction of the nominal Cr2O3 content (1600 g/gUO2) in all pellets of all fuel rods in the assembly leads to a decrease of about 40 pcm on the assemblys k inf.

Containment Observation OBS-Co-1 Provide the material classification for the contents described in Appendix 1 of the approval certificate for the FCC-4 packaging.

The material classification for each of the contents in Appendices 2 through 13 (excluding Appendix 9 which was not provided) of the approval certificate for the FCC-4 packaging is described as an activity that is less than 1 A2; however, the material classification was not similarly provided for the contents in Appendix 1 of the approval certificate for the FCC-4 packaging.

This information is needed to determine compliance with SSR-6 paragraph 429.

We cant explain this difference between the appendix 1 and the other appendices in the French Approval certificate. However, it is specified in the Appendix 1 that Maximum activity level per packaging: The maximum activity of the content is less than 1 A2. Thus, it is implicit that the specification "Material classification: Activity less than 1 A2" is also available in this appendix.

www.orano.group COR-20-031142-000 vers. 2.0 6/6

Enclosure 4 to E-57013 AFFIDAVIT PURSUANT TO 10 CFR 2.390 TN Americas LLC )

State of Maryland ) SS.

County of Howard )

I, Prakash Narayanan, depose and say that I am Chief Technical Officer of TN Americas LLC, duly authorized to execute this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.390 of the Commissions regulations for withholding this information.

The documents to be withheld from public disclosure are listed below:

NF EN 10088-3.

NF EN 485-2+A1.

NF EN ISO 148-1.

NF A35-557.

NF EN 10025-1, NF EN 10025-2, NF EN 10025-3, NF EN 10025-4, NF EN 10025-5, NF EN 10025-6.

NF EN 10028-3.

FS1-0004231EN D-FD-16-00285-EN NF EN 10222-1 NF EN 10222-2 NF EN 10222-3 NF EN 10222-4 NF EN 10222-5 NF EN 10028-7.

47-0-01-99-01-00-2_I+A 47-0-01-99-01-02_J+A 47-0-01-99-01-06_F+A 47-0-01-99-01-09-1_G+A 47-0-01-99-01-09-2_G+A 47-0-01-99-01-16_E+A 47-0-01-99-01-22_A+A PLA-16-00179264-201-00 EN PLA-16-00179264-202-00 EN PLA-16-00179264-202-00 EN PLA-16-00179264-300-00 EN FFP_NEEL-F 2008 DC 118EN_B_FIN Translated FCC4 16x16 EN FCC4 17x17 1300MWe EN FCC4 17x17 1450MWe EN FCC4 18x18 EN Activated Slip Systems and Localized Straining of Irradiated Zr Alloys in Circumferential Loadings -

C. Regnard, et. al.

CODAP 2005 - Appendix I1.A1 - Visual inspection CODAP 2005 - Appendix I1.A2 - Dye penetrant test Page 1 of 2

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