ML24156A103

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Enclosure 1 - Certificate of Compliance No. 9372, Rev. 5, for the Model No. TN-B1 Package
ML24156A103
Person / Time
Site: 07109372
Issue date: 06/06/2024
From: Yoira Diaz-Sanabria
Storage and Transportation Licensing Branch
To:
Framatome
Shared Package
ML24156A102 List:
References
Download: ML24156A103 (1)
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Text

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 1 OF 13
2. PREAMBLE
a. This certificate is issued to certify that the package (packaging and contents) described in Item 5 below meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 71, Packaging and Transportation of Radioactive Material.
b. This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
a. ISSUED TO (Name and Address) b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Framatome, Inc. Framatome TN - B1 Safety Analysis Report, FS1 -

2101 Horn Rapids Rd. 0014159, Revision No. 1 1, dated January 31, 202 3, as Richland, WA 99354 supplemented.

4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specifi ed below.

5.

(a) Packaging

(1) Model No.: TN - B1

(2) Description

The Model No. TN - B1 package is a rectangular box, 742 mm (29.21 in) high by 720 mm (28.35 in) wide by 5,068 mm (199.53 in) long, designed for the transport of unirradiated fuel assemblies or individual fuel rods with an enrichment up to 8.0 weight percent U - 235. The package carries a maximum of (i) two Boiling Water Reactor (BWR) fuel assemblies or individual rods, containing enriched commercial grade uranium or of uranium with a trace amount of material s as defined in Table 2 of this CoC, or (ii) uranium oxide generic pressurized water reactor (PWR), or uranium carbide loose fuel rods in a 5 inch diameter stainless steel pipe.

The package is comprised of one inner container and one outer container both made of stainless steel. The inner container has a double-wall stainless steel sheet structure with an alumina silicate thermal insulator, filling the gap between the two walls, to reduce the flow of the heat into the contents in the event of a fire. Foam polyethylene or rubber cushioning material is placed on the inside of the inner container for protection of the fuel assembly.

The outer container is comprised of a stainless - steel angular framework covered with stainless steel plates. Inner container clamps are installed inside the outer container with damping devices to minimize vibrations during transport. Wood and honeycomb resin-impregnated kraft paper act as shock absorbers. The fuel rod clad and ceramic nature of the fuel pellets provide primary containment of the radioactive material.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 2 OF 13

5.(a)(2) continued

The approximate dimensions and weights of the package are as follows:

Maximum gross shipping weight 1,614 kg (3,558 lbs)

Maximum weight of inner container 308 kg (679 lbs)

Maximum weight of outer container 622 kg (1,371 lbs)

Maximum weight of packaging 930 kg (2,050 lbs)

Dimensions of inner container Length 4,686 mm (184.49 in)

Width 459 mm (18.07 in)

Height 286 mm (11.26 in)

Dimensions of outer container Length 5,068 mm (199.53 in)

Width 720 mm (28.35 in)

Height 742 mm (29.21 in)

(3) Drawings

This packaging is constructed in accordance with the TN-B1 Drawing Nos.:

Outer Container Drawings 105E3737, Rev. 6 FS1-0042698, Rev. 1 FS1-0042699, Rev. 1 FS1-0042700, Rev. 2 105E3741, Rev. 1 105E3742, Rev. 3 FS1-0042703, Rev. 1 02-9162717, Rev. 1

Inner Container Drawings Contents Containers FS1-0042705, Rev. 2 105E3773, Rev. 1 105E3746, Rev. 1 0028B98, Rev. 1 FS1-0042707, Rev. 1 FS1-0042708, Rev. 1 02-9162722, Rev. 1 NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 3 OF 13

5.(b) Contents

(1) Type and form of material

(i) 5.0 weight percent U-235

Enriched commercial grade uranium, or slightly contaminated uranium with trace quantities limits, as specified in Table 2 below. Uranium oxide or uranium carbide fuel rods enriched to no more than 5.0 weight percent U-235, with weight limits specified in Table 1 below.

(ii) > 5.0 to 8.0 w eight percent U-235

Enriched commercial grade uranium, or slightly contaminated uranium with trace quantities limits, as specified in Table 3 below. Uranium oxide or uranium carbide fuel rods enriched to no more than 8.0 weight percent U -235, with weight limits specified in Table 1 below.

Table 1: Maximum weight of uranium dioxide pellets per fuel assembly

Type 8x8 fuel Type 9x9 fuel Type 10x10 fuel Type 11x11 fuel assembly assembly assembly assembly

235 kg 240 kg 275 kg 281 kg

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 4 OF 13

5.(b)(1) continued

Table 2: Maximum Concentrations of Authorized Contamination Material for 5.0 weight percent U -235

Isotope Maximum content U-232 2.00 x 10-9 g/gU

U-234 2.00 x 10-3 g/gU

U-235 5.00 x 10-2 g/gU U-236 2.50 x 10-2 g/gU

U-238 Balance of Uranium Np-237 1.66 x 10-6 g/gU

Pu-238 6.20 x 10-11 g/gU Pu-239 3.04 x 10 -9 g/gU

Pu-240 3.04 x 10 -9 g/gU Gamma 5.18 x 105 MeV -

Emitters Bq/kgU

Maximum content of U-238 is 9.23 x 10-1g/gU for a maximum U-235 concentration of 5%.

Since, for concentrations less than 5%, the U238 value will be higher, it is shown as Balance of Uranium in Table 2.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 5 OF 13

5.(b)(1) continued

Table 3: Maximum Concentrations of Authorized Contamination Material for > 5.0 to 8.0 weight percent U -235

Isotope Maximum content U-232 1.10 x 10-7 g/gU

U-234 7.65 x 10 -3 g/gU

U-235 8.00 x 10-2 g/gU U-236 2.50 x 10-2 g/gU

U-238 Balance of Uranium Np-237 1.66 x 10-6 g/gU

Pu-238 6.20 x 10-11 g/gU Pu-239 3.04 x 10 -9 g/ gU

Pu-240 3.04 x 10 -9 g/gU Gamma 5.18 x 105 MeV -

Emitters Bq/kgU

Maximum content of U-238 is 8.87 x 10-1g/gU for a maximum U-235 concentration of 8%. Since, for concentrations less than 8%, the U238 value will be higher, it is shown as Balance of Uranium in Table 3.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 6 OF 13

5.(b)(1) continued

(i) 8 x 8 fuel assemblies comprised of 60 to 64 rods in a square array with a maximum active fuel rod length of 381 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications are in accordance with Table 4 below.

(ii) 9 x 9 fuel assemblies comprised of 72 to 81 rods in a square array with a maximum active fuel rod length of 381 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications are in accordance with Table 4 below.

(iii) 10 x 10 fuel assemblies comprised of 91 to 100 rods in a square array with a maximum active fuel rod length of 385 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications are in accordance with Table 4 below.

(iv) 11 x 11 fuel assemblies comprised of 112 rods in a square array with a maximum active fuel rod length of 385 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications are in accordance with Table 5 below for 5.0 weight percent U-235.

(v) 11 x 11 fuel assemblies comprised of 112 rods in a square array with a maximum active fuel rod length of 385 cm. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod and poison rod specifications are in accordance with Table 6 below for > 5.0 to 8.0 weight percent U-235.

(vi) Uranium oxide fuel rods configured loose, in a 5-inch diameter schedule 40 stainless steel pipe/protective case or strapped together. When fuel rods are placed in polyethylene sleeves, each polyethylene sleeve shall not exceed 0.0152 cm in thickness. The maximum pellet diameter, minimum clad thickness, and rod specifications are in accordance with Table 7 below for 5.0 weight percent U-235.

(vii) Uranium carbide or generic PWR uranium oxide fuel rods configured loose, in a 5-inch diameter schedule 40 stainless steel pipe/protective case. When fuel rods are placed in polyethylene sleeves, each polyethylene sleeve shall not exceed 0.0152 cm in thickness.

The maximum pellet diameter, minimum clad thickness, and rod specifications are in accordance with Table 7 below for 5.0 weight percent U-235.

(viii) Uranium oxide fuel rods or 17x17 PWR uranium oxide fuel rods configured loose, in a 5-inch diameter schedule 40 stainless steel pipe. When fuel rods are placed in polyethylene sleeves, each polyethylene sleeve shall not exceed 0.0152 cm in thickness. The maximum pellet diameter, minimum clad thickness, and rod specifications are in accordance with Table 8 below for > 5.0 to 8.0 w eight percent U-235.

Fuel rods, assembled into fuel assemblies, contain sintered pellets of uranium oxides and/or sintered pellets of uranium oxides mixed with various additives such as chromia, gadolinia, and silica.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 7 OF 13

5.(b)(1) continued Table 4: Fuel Assembly Parameters (8x8, 9x9, 10x10) for 5.0 weight percent U -235.

Parameter Units Type Type Type Type Fuel Assembly Type Rods 8x8 9x9 FANP 10x10 GNF 10x10 UO2 Density % 98% 98% 98% 98%

Tetic Tetic T ical Tetic Nber s a # 2x2 0, 2-2 0, 2-2 0, 2-2 o-ce o-ce o-ce agonal, PxP agonal, PxP agonal, PxP Nber uods # 60 - T2 - 91 - 1 91 - 1 cuelod la 1.176 1.093 1.000 1.010 cuelleta 1.05 0.96 0.895 0.895 Cly wircioy wircioy wircioy wircioy Cla 1.10 1.02 0.933 0.934 Clckss 0.038 0.036 0.033 0.038 Acti fuh 381 381 385 385 Ninuelod mitch 1.45 1.30 r -2PR mlicent % 5 5 5 5 Mimumtice Avaicent % 5 5 5 5 Channelhickss b 17 3048 17 3 8 17 3048 17 3048 Ptih Fuelos (3 toug3m lh) x # None Ginia Requires Lattice Avaichmt c

< 0 wt% U -235 7 @t t% t% t%

< 7 wt% U -235 % 6 @t 8 @t t% t%

< 6 wt% U -235 G 2O 3 6 @t 8 @t t% t%

< 3 wt% U -235 6 @t 8 @t 9 @t 9 @t

< 2 wt% U -235 6 @t 6 @t 8 @t 8 @t

< 1 wt% U -235 4 @t 6 @t 8 wt% 8 wt%

< 9 wt% U -235 4 @t 6 @t 6 @t 6 @t

< 8 wt% U -235 4 @t 4 @t 6 @t 6 @t

< 7 wt% U -235 2 @t 4 @t 6 @t 6 @t

< 6 wt% U -235 2 @t 4 @t 4 @t 4 @t

< 5 wt% U -235 2 @t 2 @t 4 @t 4 @t

< 3 wt% U -235 2 @t 2 @t 2 @t 2 @t

< 1 wt% U -235 None 2 @t 2 @t 2 @t

< 0 wt% U -235 None None 2 @t 2 @t

< 9 wt% U -235 None None None None Pyetle Eivalentass (xim persl 10.2 10.2

a. For 8 x 8 fuel assembly designs, there can be either 0 or 1 water rod; the water rod location occupies a space equivalent to 2 x 2 fuel rods. This is designated as 0, 2 x 2 in the table. For 9 x 9 and 10 x 10 fuel assembly designs, there can be either 0, 1, or 2 water rods in the assembly; the water rod location occupies a space equivalent to (i) two 2 x 2 fuel rod equivalent spaces on a diagonal at the center of the assembly, or (ii) one 3 x 3 fuel rod equivalent space (9 fuel rods space) in the center of the assembly.

These configurations are designated as 0, 2 - 2x2 off-center diagonal, 3x3 in the table.

b. Transport with or without channels is acceptable
c. Required gadolinia rods must be distributed symmetrically along the major diagonal.
d. Polyethylene equivalent mass calculation per Section 6.3.2.2 of the application.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 8 OF 13

5.(b)(1) continued Table 5: Fuel Assembly Parameters (11x11) for 5.0 weight percent U-235.

Parameter Units Value Fuel Assembly Type Rods 11x11 UO 2 Density a g/cm 3 10.763

Nber s # P cent Nber uods # 112 cuela 0.930 cuelleta 0.820 Cly wircio y Cla 0.840 Clckss 0.045 bquiveomiluomitch 1.195

r -2PR mlicent % 5.0 Mimumtice Avage % 5.0 bnrice cuelhannickss b 0.P20

cl th cuelo nuant y #

Activth 385 phortt ienh cuelods nity #

Activeh 155.1 t iengthls nity # U Activeh 236.8 dinia o equirestic Ave bichment c

5.0 wt% U-R t%

4.8 wt% U-R t%

4.6 wt% U-R t%

4.4 wt% U-R t%

4.2 wt% U-R 9 wt%

4.1 wt% U-R U wt%

3.9 wt% U-R # @ wt% T wt%

3.8 wt% U-R dd 2l P 6 wt%

3.6 wt% U-R R wt%

3.5 wt% U-R 4 wt%

3.3 wt% U-R P wt%

3.2 wt% U-R 2 wt%

2.9 wt% U-R None

myetle bivalentass 10.2 (xim persl d

a. Density based on a pellet modeled as a right circular cylinder
b. Transport with or without channels is acceptable.
c. Required gadolinia rods must be distributed symmetrically along the major diagonal and shall not be placed on the periphery.
d. Refer to Section 6.3.2.2 of the application.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 9 OF 13

5.(b)(1) continued Table 6: Fuel Assembly Parameters (11x11) for > 5.0 to 8.0 weight percent U-235.

Parameter Units Value Fuel Assembly Type Rods 11x11 UO2 Densitya g/cm3 10.763 Number of water rods # 3x3 center Number of fuel rods # 112 Fuel rod OD cm 0.930 cuel mella 0.820 Cly wirconiu Aly Cla 0.840 Clhickness 0.045 biventin cuod 1.195 mch U-235 Pellet Enrichment wt% U Maximtice Avage w 8.0 bichment Fuel Channel Side Thicknessb cm 0.320 cl ienh clo nity #

Active iength 385 phort mt ienh clods nity #

Active iength 155.1 t iengthlods antity # U Active iength 236.8 dinia ores iattice Avage bichment c 8.0 wt% U-235 21 @ 4 wt%

7.5 wt% U-235 # @ wt% 19 @ 4 wt%

7.0 wt% U-235 17 @ 4 wt%

6.5 wt% U-235 Gd2O3 15 @ 4 wt%

6.1 wt% U-235 13 @ 4 wt%

5.8 wt% U-235 13 @ 2 wt%

Polyethylene Equivalent kg 10.2 Mass (Maximum per d Assembly)

a. Density based on a pellet modeled as a right circular cylinder
b. Transport with or without channels is acceptable.
c. Required gadolinia rods must be distributed symmetrically along the major diagonal and shall not be placed on the periphery.
d. Refer to Section 6.3.2.2 of the application.

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 10 OF 13

5.(b)(1) continued

Table 7: Fuel Rod Parameters for 5.0 weight percent U-235

Parameter Units Type CANDU-CANDU-Fuel Assembly 9x9 10x10 11x11 14 25 Generic Type 8x8 (UO2) (UO2) (UO2) (UO2) (UC) (UC) PWR (UO2)

UO2 or UC g/cm 10.74 10.74 10.74 10.763 13.36 13.36 10.74 Fuel Densitya 3 Fuel rod OD cm >1.10 >1.02 >1.00 >0.930 >1.340 >0.996 >1.118 Fuel Pellet OD cm <1.05 <0.96 <0.90 0.820 <1.254 <0.950 <0.98 Zirc. Zirc. Zirc. Alloy Cladding Type Zirc. Alloy Zirc. Alloy Zirc. Alloy Zirc. Alloy Alloy Alloy or SS or SS or SS Cladding ID cm <1.10 <1.02 <1.00 0.930 <1.267 <0.951 <1.004 Cladding cm >0.038 >0.036 >0.038 0.045 >0.033 >0.033 >0.033 Thickness Active fuel cm <381 <381 <385 385 <47.752 <40.013 <450 Length Maximum U-235 Pellet wt.% <5.0 <5.0 <5.0 5.0 <5.0 <5.0 <5.0 Enrichment Maximum Average fuel wt.% <5.0 <5.0 <5.0 5.0 <5.0 <5.0 <5.0 rod Enrichment Loose Rod Configuration Freely Loose or Strapped # < 25 < 25 < 25 < 25 N/A N/A N/A Together Packed in 5 SS Pipe or protective # < 22 < 26 < 30 <30 < 74 b < 130b < 105b Case, i.e., SS Box with Lid

a. Density based on a pellet modeled as a right circular cylinder.
b. Including partial rods using dense packing of congruent rods- - in the 5 SS pipe

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 11 OF 13

5.(b)(1) continued

Table 8: Fuel Rod Parameters for > 5.0 to 8.0 weight percent U -235.

Parameter Units Type

Fuel Assembly 11x11 17x17 PWR Type (UO2) (UO2)

UO2 or UC a 3 10.763 10.763 Fuel Density g/cm

Fuel rod OD cm >0.930 >0.945

Fuel Pellet OD cm 0.820 <0.827 Cladding Type Zirc. Alloy Zirc. Alloy or SS Cladding ID cm 0.930 <0.841 Cladding cm 0.045 >0.033 Thickness Active fuel Length cm 385 <381 Maximum U-235 wt.% 8.0 <8.0 Pellet Enrichment Maximum Average <8.0 fuel rod Enrichment wt.% 8.0

Loose Rod Configuration Freely Loose or # < 25 < 25 Strapped Together Packed in 5 SS Pipe or protective # < 30 < 30 Case, i.e., SS Box with Lid

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 12 OF 13

5.(b)(2) Maximum quantity of material per package

Total weight of payload contents (fuel assemblies, or fuel rods, and rod shipping containers) not to exceed 684 kg (1508 pounds).

(i) For the contents described in 5(b)(1 )(i), 5(b)(1 )(ii), 5(b)(1 )(iii), 5(b)(1 )(iv), and 5(b)(1 )(v): two fuel assemblies.

(ii) For the contents described in 5(b)(1)(vi), 5(b)(1)(vii), and 5(b)(1)(viii): allowable number of fuel rods per compartment (2 compartments per package).

5.(c) Criticality Safety Index, for each content, as described in Table 9 below:

Table 9: Criticality Safety Index

Contents Type and Limits Enrichment CSI wt.% U-235 5(b)(1)(i) 8x8, 9x9, 10x10 Fuel 5(b)(1)(ii) Assemblies 5(b)(2)(i), <5.0 1.0 5(b)(1)(iii) or 5(b)(1)(vi) BWR Rods 5(b)(2)(ii) 5(b)(1)(iv) 11x11 Fuel <5.0 1.5 Assemblies 5(b)(2)(i) 5(b)(1)(v) 11x11 Fuel <8.0 3.2 Assemblies 5(b)(2)(i)

Loose or Bundled or 5(b)(1)(vii) Rods in a Protective <5.0 2.1 Carrier, 5(b)(2)(ii)

Loose or Bundled 5(b)(1)(viii) Rods, 11x11 or 17x17 <8.0 1.0 PWR, 5(b)(2)(ii)

Rods in Protective 5(b)(1)(viii) Carrier, 11x11, <8.0 2.3 5(b)(2)(ii)

Rods in Protective 5(b)(1)(viii) Carrier, 17x17 PWR, <8.0 2.5 5(b)(2)(ii)

NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

FOR RADIOACTIVE MATERIAL PACKAGES

1. a. CERTIFICATE NUMBER b. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 5 71 -9372 USA/9 372 /B(U) F-96 13 OF 13
6. In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) The package shall be prepared for shipment and operated in accordance with Chapter 7 of the application.

(b) The packaging must meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application.

(c) Prior to each shipment, the fuel rods shall conform to the leak tests and specific inspection techniques used for qualification and in-process inspections as defined in Chapter 8. Stainless steel components of the packaging must be visually inspected. Packages in which stainless steel components show pitting corrosion, cracking, or pinholes, are not authorized for transport.

(d) If wrapping is used on the unirradiated fuel assemblies, their ends must be assured to be open during transport.

7. All fuel to be shipped must meet the maximum P(r/t) criterion-product of the pre pressure and of the maximum Inside Radius/Thickness-of 10.18653 MPa. Shipment of 11x11 fuel designs manufactured by other suppliers than Framatome is not authorized.
8. Cluster separators are optional and may be comprised of polyethylene or other plastics with mass limits determined in accordance with Section 6.3.2.2 (Material Specifications) of the application.
9. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
10. Transport by air of fissile material is not authorized.
11. Expiration date: June 30, 2029.

REFERENCES

Framatome TN-B1 Safety Analysis Report, FS1- 0014159, Revision 11, dated January 31, 2023.

Supplements dated October 9, 2023; March 22, 2024.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

Yoira Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards

Date: June 6, 2024

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