ML23191A149

Certificate of Compliance No. 9309, Revision No. 13

ML23191A149
Person / Time
Site:	07109309
Issue date:	07/14/2023
From:	Yoira Diaz-Sanabria Storage and Transportation Licensing Branch
To:	Global Nuclear Fuel
Shared Package
ML23191A147	List: ML23191A148 ML23191A149 ML23191A150
References
EPID L-2022-LLA-0015, CoC No. 9309
Download: ML23191A149 (1)

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 N UMBER PAGE PAGES 9309 13 71 - 9309 USA/9309/B(U)F - 96 1 OF 10

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 Global Nuclear Fuel - Americas, LLC NEDO - 33869, Revision 1 1, Global Nuclear Fuel -

P.O. Box 780 Americas, LLC, application dated September 2022, as Wilmington, NC 28402 supplemented.

4. CONDITIONS

This certificate is cond itional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.

5.

(a) Packaging

(1) Model No.: RAJ - II

(2) Description

The RAJ - II package is a rectangular box that is 742 millimeters ( mm) (29.21 inches (in. )) high by 720 mm (28.35 in. ) wide by 5,068 mm (199.53 in) long to transport a maximum of two Boiling Water Reactor (BWR) fuel assemblies or individual rods that meet the ASTM C996 standard of enriched commercial grade uranium, enriched reprocessed uranium, uranium oxide generic pressurized water reactor (PWR) or uranium carbide loose fuel rods in a 5-inch diameter stainless steel pipe.

The RAJ - II packaging is comprised of one inner container and one outer container both made of stainless steel. The inner container is comprised of a double-wall stainless steel sheet structure with alumina silicate thermal insulator filling the gap between the two walls to reduce the heat flowing into the contents in the event of a fire. P ol yethylene foam 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. The i nner container clamps are installed inside the outer container with a vibro-isolating device between to alleviate vibration occurring during transportation. Wood and honeycomb resin impregnated kraft paper or aluminum are placed as shock absorbers to reduce shock in the event of a drop o f the package. The fuel r od cladding and welded end plugs provide primary containment of the radioactive material. The radioactive material is bound in ceramic pellets with limited solubility and minimal propensity to suspend in air.

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. REVIS ION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F - 96 2 OF 10

5.(a)(2) Description (continued)

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

Maximum gross shipping weight 1,614 kilograms (kg) (3,558 pounds (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.)

Loose rods pipe nominal mass per 106 kg (234 lbs.)

component Protective case nominal mass per 87 kg (192 lbs.)

component 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 following Global Nuclear Fuel (GNF)

Drawing Nos.:

(i) Outer Container Drawings 105E3737, Rev. 9 105E3738, Sheet 1, Rev. 11 105E3738, Sheet s 2-3, Rev. 10 105E3739, Rev. 6 105E3740, Rev. 7 105E3741, Rev. 4 105E3742, Rev. 5 105E3743, Rev. 7 105E3744, Rev. 8

(ii) Inner Container Drawings 105E3745, Sheets 1-4, Rev. 11 105E3746, Rev. 4 105E3747, Rev. 6 105E3748, Rev. 4 105E3749, Rev. 8 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. REVIS ION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F - 96 3 OF 10

5.(a) (3) Drawings (Continued)

(iii) Contents Containers 105E3773, Rev. 2 0028B98, Rev. 2

5.(b) Contents

(1) Type and form of material

Enriched commercial grade uranium or slightly contaminated uranium with trace quantities limits, as defined in ASTM C996, uranium oxide or uranium carbide fuel rods enriched to no more than 8.0 weight percent in 235U, with limits specified in Tables 1 and 2 below. 238U, not listed in Table 2, is assumed to be the remainder of the uranium concentration.

Table 1. Maximum Weight of U ranium Dioxide Pellets per F uel Assembly Type 8x8 fuel Type 9x9 fuel Type 10x10 fuel assembly assembly assembly

235 kg 240 kg 275 kg

Table 2. Maximum Authoriz ed Concentrations

Isotope Maximum content for Maximum content for 5.0 wt% 235U 8.0 wt% 235U

232U 5.00 x 10-8 g/gU 5.00 x 10-8 g/gU

234U 2.00 x 10-3 g/gU 2.00 x 10-3 g/gU

235U 5.00 x 10-2 g/gU 8.00 x 10-2 g/gU

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

237Np 1.66 x 10-6 g/gU 1.66 x 10-6 g/gU

238Pu 6.20 x 10-11 g/gU 6.20 x 10-11 g/gU

239Pu 3.04 x 10-9 g/gU 3.04 x 10-9 g/gU

240Pu 3.04 x 10-9 g/gU 3.04 x 10-9 g/gU

Gamma 4.4 x 105 MeV - Bq/kgU 4.4 x 105 MeV - Bq/kgU Emitters 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. REVI SION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 -9309 USA/9309/B(U)F - 96 4 OF 10

5.(b) (1) Type and form of material (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 specifications, and poison rod specification are in accordance with Table 3 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 diamet er, minimum clad thickness, rod pitch, water rod specifications, and poison rod specification are in accordance with Table 3 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 c m. The maximum pellet diameter, minimum clad thickness, rod pitch, water rod specifications, and poison rod specification are in accordance with Table 3 below.

(iv) GNF 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 specifications, and poison rod specification are in accordance with Table 4 below.

(v) Uranium oxide fuel rods configured loose, in a 5-in. diameter schedule 40 stainless steel pipe/protective case or strapped together. The maximum pellet diameter, minimum clad thickness, and rod specifications are in accordance with Table 5 below.

(vi) Uranium carbide or generic PWR uranium oxide fuel rods configured loose, in a 5-in.

diameter schedule 40 st ainless steel pipe. The maximum pellet diameter, minimum clad thickness, and rod specifications are in accordance with Table 5 below.

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. REVIS ION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F - 96 5 OF 10

5.(b) (1) Type and form of material (continued)

Table 3. Fuel Assembly Parameters (CSI=1.0)

Parameter Units Type Type Type Type Fuel Assembly Type Rods 8 x 8 9 x 9 FANP 10 x 10 GNF 10 x 10 UO2 Density % Theoretical Nber w rods tat rods 2 x 2 2-2 x 2 2-2 x 2 2-2 x 2 ee Cti off -center off -center off -center diag onal, 3x3, diagonal, 3x3 diagonal, 3x3 1 -axially varying centered Number of fuel rods Number 60 - 64 72 - 8 1 91 - 100 Fuel Rod OD cm 17S 09P 000 010 cuel Pellet 895 Cl Ty N/A wirconi Alloy 9PP 9P4 Cl Tckness 0P8 0PS 0PP 0P8 Acte fuel lh P81 P85 cuel d Pch 1.692 1.363 2P5r Pl Eicent wt% 5.0 8.0 Lattice Average Enrichment wt% 5. 0 8.0 Channel Thickness a cm 0.17 - 0.3048 Any Partial Length Fuel Rods Fuel Rods None 12 14 16 Gia o rents Lattice Average Enrichment (CSI=1.0) b #

< 5.0 wt % 235 U @ wt% Gd 2 O 3 7 @ 2 wt % 10 @ 2 wt % 12 @ 2 wt % 12 @ 2 wt %

< 4.9 wt % 235 U 7 @ 2 wt % 1 0 @ 2 wt % 12 @ 2 wt % 11 @ 2 wt %

< 4.7 wt % 235 U 6 @ 2 wt % 8 @ 2 wt % 12 @ 2 wt % 11 @ 2 wt %

< 4.6 wt % 235 U 6 @ 2 wt % 8 @ 2 wt % 10 @ 2 wt % 10 @ 2 wt %

< 4.5 wt % 235 U 6 @ 2 wt % 8 @ 2 wt % 10 @ 2 wt % 9 @ 2 wt %

< 4.3 wt % 235 U 6 @ 2 wt % 8 @ 2 wt % 9 @ 2 wt % 9 @ 2 wt %

< 4.2 wt % 235 U 6 @ 2 wt % 6 @ 2 wt % 8 @ 2 wt % 8 @ 2 wt %

< 4.1 wt % 235 U 4 @ 2 wt % 6 @ 2 wt % 8 @ 2 wt % 8 @ 2 wt %

< 3.9 wt % 235 U 4 @ 2 wt % 6 @ 2 wt % 6 @ 2 wt % 7 @ 2 wt %

< 3.8 wt % 23 5U 4 @ 2 wt % 4 @ 2 wt % 6 @ 2 wt % 7 @ 2 wt %

< 3.7 wt % 235 U 2 @ 2 wt % 4 @ 2 wt % 6 @ 2 wt % 6 @ 2 wt %

< 3.6 w t % 235 U 2 @ 2 wt % 4 @ 2 wt % 4 @ 2 wt % 5 @ 2 wt %

< 3.4 wt % 235 U 2 @ 2 wt % 2 @ 2 wt % 4 @ 2 wt % 4 @ 2 wt %

< 3.3 wt % 235 U 2 @ 2 wt % 2 @ 2 wt % 2 @ 2 wt % 3 @ 2 wt %

< 3.2 wt % 235 U 2 @ 2 wt % 2 @ 2 wt % 2 @ 2 wt % 2 @ 2 wt %

< 3.1 wt % 235 U None 2 @ 2 wt % 2 @ 2 wt % 1 @ 2 wt %

< 2.9 wt % 235 U None None None None

Polyethylene Equivalent Mass per kg 11 10.2 assembly c Thermal Performance Criteriad MPa r/t (Pf 921/293 - P a) 31.1 MPa (4,514 psi)

a. Transport with or without channels is acceptable.

b. Required gadolinia rods must be distributed symmetrically about the major diagonal. Minimum required number of gadolinia rods applies for full-length rod locations, excluding the lattice peripheral locations. Additional gadolinia rods in other locations are allowed as long as the minimum is met. After seven (7) gadolinia rods, there must be at least one (1) gadolinia rod in at least two out of the four quadrants of the fuel rod array (refer to Section 6.3.4.2, Fuel Assembly Gadolinia Rod Study (2N=448), of the application).

c. Polyethylene equivalent mass calculation (refer to Section 6.3.2.2, Material Specification, of the application)

d. r/t is the fuel rod inner radius to thickness ratio, Pf is the absolute fill pressure, and Pa is atmospheric pressure (refer to Section 3.4.4 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. REVIS ION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F - 96 6 OF 10

5.(b) (1) Type and form of material (continued)

Table 4. Fuel Assembly Parameters (CSI=1.6)

Parameter Units Type Type Type Type Fuel Assembly Type Rods 8 x 8 9 x 9 FANP 10 x 10 GNF 10 x 10 UO2 Density % Theoretical Nber w rods tat rods 2 x 2 2-2 x 2 2-2 x 2 2-2 x 2 ee Cti off -center off -center off -center diag onal, 3x3, diagonal, 3x3 diagonal, 3x3 1 -axially varying centered Number of fuel rods Number 60 - 64 72 - 81 91 - 100 Fuel Rod OD cm 17S 09P 000 010 cuel Pellet 895 Cl Ty N/A wirconi Alloy 9PP 9P4 Cl Tckness 0P8 0PS 0PP 0P8 Acte fuel lh P81 P85 cuel d Pch 1.692 1.363 2P5r Pl Eicent wt% 5.0 8.0 Lattice Average Enrichment wt% 5. 0 8.0 Channel Thickness a cm 0.17 - 0.3048 Any Partial Length Fuel Rods Fuel Rods None 12 14 16 Gia orents Lattice Average Enrichment (CSI=1.6) b #

< 8.0 wt % 235 U @ wt% Gd 2 O 3 N/A N/A N/A 22 @ 2 wt %

< 7.9 wt % 235 U N/A N/A N/A 21 @ 2 wt %

< 7.6 wt % 235 U N/A N/A N/A 20 @ 2 wt %

< 7.3 wt % 235 U N/A N/A N/A 19 @ 2 wt %

< 7.0 wt % 235 U N/A N/A N/A 18 @ 2 wt %

< 6.7 wt % 235 U N/A N/A N/A 17 @ 2 wt %

< 6.5 wt % 235 U N/A N/A N/A 16 @ 2 wt %

< 6.3 wt % 235 U N/A N/A N/A 15 @ 2 wt %

< 6.0 wt % 235 U N/A N/A N/A 14 @ 2 wt %

< 5.8 wt % 235 U N/A N/A N/A 13 @ 2 wt %

< 5.5 wt % 235 U N/A N/A N/A 12 @ 2 wt %

< 5.0 wt % 235 U (CSI=1.6) b Same as to CSI=1.0

< 3.3 wt % 235 U Requirements

< 3.2 wt % 235 U None

< 3.1 wt % 235 U None

< 2.9 wt % 235 U None Same as CSI=1.0 Requirements

Polyethylene Equivalent Mass per kg 11 10.2 ass em bly c Thermal Performance Criteriad MPa r/t (Pf 921/293 - Pa) P1 a(4,514 i)

) Transportititss acceptable.

) oria rods mt be distrited symmetricly about the m di Mimrber gadolirs a pplies fl -

lh rocis, excluditiceiocis. Additiia rodsn otherocio arl ong as tim is

m. Aft sia rs thermt be at least ga dol ia rod iatst twof tour quadrants ofuelrrr tpection S,cuelssemy Gia ood pty=, application).

) Pyetlene vtscion (rption S.2, Mipecif ici o applicion)

) r/ts tueladius to thicknessi P f ishe absole fill prs P a is atmic prse (rpecti P.4 ofh icion)

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. REVIS ION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F - 96 7 OF 10

5.(b) (1) Type and form of material (continued)

Table 5. Fuel Rod Parameters Parameter Units Type Fuel Assembly N/A 8 x 8 9 x 9 10 x 10 CANDU-14 CANDU-25 Generic Type (UO 2) (UO 2) (UO 2) (UC) (UC) PWR (UO 2)

Fuel Density % theoretical 98 97 100 Fuel rod OD cm > 1.10 > 1.02 > 1.00 > 1.340 > 0.996 > 1.118 Fuel Pellet OD cm < 1.05 < 0.96 < 0.90 < 1.254 < 0.950 < 0.98 Cladding Type N/A Zirconium Alloy Zirconium Alloy or SS Cladding ID cm < 1.10 < 1.02 < 1.00 < 1.267 < 0.951 < 1.004 Cladding cm > 0.038 > 0.036 > 0.038 > 0.033 Thickness Active Fuel Length cm < 381 < 385 < 47.752 < 40.013 < 450 235U Pellet Enrichment wt.% < 5.0 8.0 5.0

Average Fuel Rod wt.% < 5.0 8.0 5.0 Enrichment Polyethylene Protective Sleeves: P Equivalent Massa kg Unlimited l her cki matisW <.5 within per Compartment b pe,imitsidpi Polylen ProtectivelvWit Protective Sleeves: 2.3 Equives a per Cpartment b Within SS Pipe: Unlimited Within SS Within SS Within SS Pipe: 27.5 Pipe: 5.0 Pipe:

wt%: Unlimited Unlimited / >

5.0 wt% and 8.0 wt%:

32.1

All Other Packing Materials: Unlimited All Other Packing Materials: Unlimited

Reference Density for Polyethylene g/cm3 Protective Sleeves: 0.925 Protective Sleeves: 1.005 Equivalent Massa All Other Packaging Materials: 0.08 All Other Packing Materials: 0.70 Calculationb Thermal Performance MPa r/t (Pf 921/293 - P a) 31.1 MPa r/t (Pf 921/293 - P a) 56.3 MPa Criteriaf Loose Rod N/A Maximum Number of Rods per Compartment based on the Maximum Active Fuel Length Configuration Freely Loose < 25 N/A Packed in 5-in. SS No. of fuel Pipe or Protective rods < 22 < 26 < 30 < 695d,e < 1,458d,e < 105d Casec Strapped Together < 25 N/A 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. REVI SION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 -9309 USA/9309/B(U)F -96 8 OF 10

a. Polyethylene equivalent mass for packing materials (refer to Section 6.3.2.2 of the application).

b. Polyethylene packing materials examples: protective sleeves, end caps, and cushioning foam.

c. Protective case consists of st ainless steel (SS) box with lid.

d. Only in 5-inch SS pipes. Including partial rods: applying dense packing of congruent rods in the pipe will result in maximum number of rods that can physically fit within the pipe to be less than the number provided in the table above.

e. Allows for dense loading of the relatively short UC rods axially along the length of the component.

f. r/t is the fuel rod inner radius to thickness ratio, Pf is the absolute fill pressure, and Pa is atmospheric pressure (refer to Section 3.4.4 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. REVI SION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F - 96 9 OF 10

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 (1, 508 pounds). The m aximum uranium payload is 484 kg (1,069 pounds).

(i) For the contents 5.0 wt% and described in 5(b)(1)(i), 5(b)(1)(ii), and 5(b)(1)(iii): two fuel assemblies.

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

(iii) For the contents > 5.0 wt% and 8.0 wt% 235U described in 5(b)(1)(iv): two fuel assemblies.

(c) Criticality Safety Index:

For contents described in 5(b)(1)(i ), 5(b)(1)(ii), 5(b)(1 )(iii) and limited in 5(b)(2)(i) 1.0

For contents described in 5(b)(1)( v) and 5(b)(1)(v i) and limited in 5(b)(2)(ii) 1.6

For contents described in 5(b)(1)(iv) and limited in 5(b)(2) (iii) 1.6

6. In addition to the requirements of Subpart G of 10 CFR Part 71:

(a) The package shal l be prepared for shipment and operated in accordance with the Package Operations of 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 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, the ends must be assured to be open during the shipment in the package.

7. Cluster separators are optional and may be comprised of polyethylene or other plastics. Polyethylene or plastic mass limits shall be determined in accordance with Section 6.3. 2.2, Material Specifications, 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. REVIS ION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION N UMBER PAGE PAGES

9309 13 71 - 9309 USA/9309/B(U)F -96 10 OF 10

8. Water rods are limited as shown in Table 3 and Table 4 above.

For 8 x 8 fuel assembly designs, there can be either 0 or 1 water rod, and the water rod location occupies a space equivalent to 2 x 2 fuel rods. This is designated as 0, 2 x 2 in Table 3 and Table 4.

For 9 x 9 and 10 x 10 fuel assembly designs, there can be either 0, 1, or 2 water rods in the assembly, and the water rod location occupies a space equivalent to (a) two 2 x 2 fuel rod equ ivalent spaces on a diagonal at the center of the assembly, or (b) 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 - 2 x 2 off-center diagonal, 3 x 3 in Table 3 and Table 4. Additionally, f or GNF 10 x 10 fuel assembly designs, the water rod can occupy a space equivalent to a single 2 x 2 fuel rod equivalent at the bottom of the assembly and expanded at the top; this configuration is designated as 1-axially varying centered in Table 3 and Table 4.

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. Revision No. 12 of this certificate may be used until January 31, 20 24.

12. Expiration date: January 31, 2029.

REFERENCES

NEDO-33869, Revision 11, Global Nuclear Fuel - Americas, LLC, application dated September 2022

Supplement dated June 12, 2023.

FOR THE U.S. NUCLEAR REGULATORY C OMMISSION

Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and S afeguards

Date: July 14, 2023