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{{#Wiki_filter:NRC FORM 618                                                                                                     U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
{{#Wiki_filter:NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
: 1. a. CERTIFICATE NUMBER                           b. REVISION NUMBER     c. DOCKET NUMBER       d. PACKAGE IDENTIFICATION NUMBER     PAGE         PAGES 9294                                   9                 71-9294               USA/9294/AF-96                       1   OF     4
: 1.
: 2. PREAMBLE
: a. CERTIFICATE NUMBER
: b. REVISION NUMBER
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9
71-9294 USA/9294/AF-96 1
OF 4
: 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.
: 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.
: b.
: 3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PACKAGE DESIGN OR APPLICATION
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.
: a. ISSUED TO (Name and Address)                                             b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Global Nuclear Fuel - Americas, LLC                                       Global Nuclear Fuel - Americas, LLC, application dated P.O. Box 780                                                              December 12, 2019.
: 3.
Wilmington, NC 28402
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 P.O. Box 780 Wilmington, NC 28402 Global Nuclear Fuel - Americas, LLC, application dated December 12, 2019.
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
5.(a)       Packaging (1)       Model No.: NPC (2)       Description A cubic stainless steel and foam outer packaging with nine cylindrical containment vessels for the transport of type A quantities of low-enriched uranium oxide powder, pellets, and compounds of uranium as defined in 5(b). The overall package dimensions are approximately 45 inches wide, 45 inches deep, and 44 inches high.
5.(a)
Packaging (1)
Model No.: NPC (2)
Description A cubic stainless steel and foam outer packaging with nine cylindrical containment vessels for the transport of type A quantities of low-enriched uranium oxide powder, pellets, and compounds of uranium as defined in 5(b). The overall package dimensions are approximately 45 inches wide, 45 inches deep, and 44 inches high.
The outer packaging consists of a 10-gage stainless steel outer shell with a ceramic fiber board liner and rigid polyurethane foam filler. The foam filler has a three-by-three array of vertical cylindrical cutouts that accommodate stainless steel sleeves for placement of the containment vessels. The outer packaging is equipped with a top cover that is secured to the outer packaging body by a combination of 16 closure cap screws and four closure strips secured by 24 bolts.
The outer packaging consists of a 10-gage stainless steel outer shell with a ceramic fiber board liner and rigid polyurethane foam filler. The foam filler has a three-by-three array of vertical cylindrical cutouts that accommodate stainless steel sleeves for placement of the containment vessels. The outer packaging is equipped with a top cover that is secured to the outer packaging body by a combination of 16 closure cap screws and four closure strips secured by 24 bolts.
The containment vessel is a maximum 8.515 inches in inner diameter and approximately 32 inches in overall length. The containment vessel is constructed of 18-gage stainless steel, surrounded by a cadmium sheet and polyethylene wrap within a 24-gage stainless steel jacket. The containment vessel is closed by a 16-gage closure lid, a silicone rubber gasket, and a band clamp assembly, which is composed of a 0.063-inch thick strap and retainer, a T-bolt, and a nut.
The containment vessel is a maximum 8.515 inches in inner diameter and approximately 32 inches in overall length. The containment vessel is constructed of 18-gage stainless steel, surrounded by a cadmium sheet and polyethylene wrap within a 24-gage stainless steel jacket. The containment vessel is closed by a 16-gage closure lid, a silicone rubber gasket, and a band clamp assembly, which is composed of a 0.063-inch thick strap and retainer, a T-bolt, and a nut.
The gross weight of the package (packaging and contents) is 1,302 kg (2,870 pounds). The maximum weight of the contents is 540 kg (1,190 pounds).
The gross weight of the package (packaging and contents) is 1,302 kg (2,870 pounds). The maximum weight of the contents is 540 kg (1,190 pounds).
5.(a)       (3)       Drawings
5.(a)
(3)
Drawings  


NRC FORM 618                                                                                     U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
: 1. a. CERTIFICATE NUMBER               b. REVISION NUMBER     c. DOCKET NUMBER   d. PACKAGE IDENTIFICATION NUMBER   PAGE         PAGES 9294                         9                 71-9294           USA/9294/AF-96                     2   OF     4 The packaging is fabricated and assembled in accordance with the following Global Nuclear Fuel - Americas, LLC, Drawing Nos.:
: 1.
177D4970, Sheet 1, Revision 1 177D4970, Sheet 2, Revision 0 177D4970, Sheet 3, Revision 0 177D4970, Sheet 4, Revision 0 177D4970, Sheet 5, Revision 0 177D4970, Sheet 6, Revision 0 177D4970, Sheet 7, Revision 0 177D4970, Sheet 8, Revision 1 SK105E4037, Sheet 2, Revision 1 (b)     Contents Table 1: Type, Form, and Maximum Quantity of Material Per Package Material Form                       Particle Size          Maximum Loading                Maximum Loading (5.00 wt.% U-235)                     Restriction:             per ICCA (kgs)                   per NPC (kgs)
: a. CERTIFICATE NUMBER
Minimum OD (Inches)            Net         Uranium             Net       Uranium Homogenous Uranium Compounds                           N/A               60.0           52.89           540.0       476.1 Heterogenous UO2 Pellets (BWR)                       0.342             60.0           48.48           540.0       436.3 Heterogenous UO2 Pellets(PWR)                       0.300             60.0           46.71           540.0       420.4 Unrestricted           60.0           40.54           540.0       364.8 Heterogenous Uranium Compounds particle size The Material Form Column must comply with the following constraints:
: b. REVISION NUMBER
* Neither solutions, free liquids, uranium metal nor uranium metal alloys are authorized and shall not be present. Homogenous and heterogenous uranium compounds may be mixed with other non-fissionable diluent materials (e.g., sand, iron, iron hydroxide, silica, carbon from ash, etc.) except for deuterium, tritium and beryllium.
: c. DOCKET NUMBER
* The solid form material within any individual NPC must be the same.
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9
* Homogeneous and heterogeneous uranium materials are limited to solid form.
71-9294 USA/9294/AF-96 2
* For purposes of determining if the homogenous or heterogeneous criteria apply: if the particle size distribution is such that a majority of the particles are 1730 µm or greater, then the heterogenous payload criteria of Table 1 applies. If a majority of the particle size distribution is below 1730 m, the homogenous payload criteria of Table 1 apply.
OF 4
* The maximum mass of any Inner Containment Canister Assembly (ICCA) inner packaging materials (e.g., plastic bags or bottles) is unrestricted provided the mean hydrogen atom density of the packaging materials to be shipped inside the inner volume of each ICCA is not greater than water.
The packaging is fabricated and assembled in accordance with the following Global Nuclear Fuel - Americas, LLC, Drawing Nos.:
177D4970, Sheet 1, Revision 1 177D4970, Sheet 2, Revision 0 177D4970, Sheet 3, Revision 0 177D4970, Sheet 4, Revision 0 177D4970, Sheet 5, Revision 0 177D4970, Sheet 6, Revision 0 177D4970, Sheet 7, Revision 0 177D4970, Sheet 8, Revision 1 SK105E4037, Sheet 2, Revision 1 (b)
Contents Table 1: Type, Form, and Maximum Quantity of Material Per Package Material Form (5.00 wt.% U-235)
Particle Size Restriction:
Minimum OD (Inches)
Maximum Loading per ICCA (kgs)
Maximum Loading per NPC (kgs)
Net Uranium Net Uranium Homogenous Uranium Compounds N/A 60.0 52.89 540.0 476.1 Heterogenous UO2 Pellets (BWR) 0.342 60.0 48.48 540.0 436.3 Heterogenous UO2 Pellets(PWR) 0.300 60.0 46.71 540.0 420.4 Heterogenous Uranium Compounds Unrestricted particle size 60.0 40.54 540.0 364.8 The Material Form Column must comply with the following constraints:
Neither solutions, free liquids, uranium metal nor uranium metal alloys are authorized and shall not be present. Homogenous and heterogenous uranium compounds may be mixed with other non-fissionable diluent materials (e.g., sand, iron, iron hydroxide, silica, carbon from ash, etc.) except for deuterium, tritium and beryllium.
The solid form material within any individual NPC must be the same.
Homogeneous and heterogeneous uranium materials are limited to solid form.
For purposes of determining if the homogenous or heterogeneous criteria apply: if the particle size distribution is such that a majority of the particles are 1730 µm or greater, then the heterogenous payload criteria of Table 1 applies. If a majority of the particle size distribution is below 1730 m, the homogenous payload criteria of Table 1 apply.
The maximum mass of any Inner Containment Canister Assembly (ICCA) inner packaging materials (e.g., plastic bags or bottles) is unrestricted provided the mean hydrogen atom density of the packaging materials to be shipped inside the inner volume of each ICCA is not greater than water.  


NRC FORM 618                                                                                   U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
: 1. a. CERTIFICATE NUMBER               b. REVISION NUMBER c. DOCKET NUMBER     d. PACKAGE IDENTIFICATION NUMBER PAGE     PAGES 9294                         9             71-9294             USA/9294/AF-96                 3 OF   4
: 1.
* Authorized materials also include UO2 pellets present in standard PWR and BWR reactor fuel assembly lattice designs (e.g., 17X17 PWR fuel assemblies, 10X10, 9X9, 8X8 BWR fuel assemblies).
: a. CERTIFICATE NUMBER
* The payload within an NPC may be distributed in any ratio within the nine ICCAs, provided that the Maximum Loading per ICCA and the Maximum Loading per NPC requirements of Table 1 are met. The payload within an ICCA can be enclosed in plastic poly bottle receptacles (e.g., bags, poly bottles, etc.).
: b. REVISION NUMBER
* The Material Form Column homogeneous and heterogeneous uranium compounds are dry solids resulting from scrap recovery and waste incineration processes. Example compounds include:
: c. DOCKET NUMBER
* uranium oxides (UO2, U3O8, or UOx x>2)
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9
* dried calcium (Ca) uranium
71-9294 USA/9294/AF-96 3
* uranyl nitrate (UN, UO2(NO3)2)                               compounds/mixtures/sludges/ash, (e.g.,
OF 4
* uranyl nitrate hexahydrate                                    CaUO3, CaUO4, Ca2UO5, Ca2UO4, Ca3UO6, (UNH, UO2(NO3) 2*6H2O)                                      CaU3O10*4H2O, CaU6O19*11H2O and
Authorized materials also include UO2 pellets present in standard PWR and BWR reactor fuel assembly lattice designs (e.g., 17X17 PWR fuel assemblies, 10X10, 9X9, 8X8 BWR fuel assemblies).
* uranium tetrafluoride (UF4)                                  CaU6O19*10H2O)
The payload within an NPC may be distributed in any ratio within the nine ICCAs, provided that the Maximum Loading per ICCA and the Maximum Loading per NPC requirements of Table 1 are met. The payload within an ICCA can be enclosed in plastic poly bottle receptacles (e.g., bags, poly bottles, etc.).
* sodium uranate (Na2UO4)
The Material Form Column homogeneous and heterogeneous uranium compounds are dry solids resulting from scrap recovery and waste incineration processes. Example compounds include:
* dried sodium (Na) uranium
uranium oxides (UO2, U3O8, or UOx x>2) uranyl nitrate (UN, UO2(NO3)2) uranyl nitrate hexahydrate (UNH, UO2(NO3) 2*6H2O) uranium tetrafluoride (UF4) dried calcium (Ca) uranium compounds/mixtures/sludges/ash, (e.g.,
* sodium diuranate (Na2U2O7)                                   compounds/mixtures/sludges/ash, (e.g.,
CaUO3, CaUO4, Ca2UO5, Ca2UO4, Ca3UO6, CaU3O10*4H2O, CaU6O19*11H2O and CaU6O19*10H2O) sodium uranate (Na2UO4) sodium diuranate (Na2U2O7) sodium diuranate hexahydrate (Na2U2O7*6H2O) dried sodium (Na) uranium compounds/mixtures/sludges/ash, (e.g.,
* sodium diuranate hexahydrate (Na2U2O7*6H2O)                  Na2U2O7*3H2O and Na2U2O7*H2O)
Na2U2O7*3H2O and Na2U2O7*H2O) ammonium diuranate (ADU, 3UO3*2NH3*4H2O) dried iron (Fe) uranium compounds/mixtures/sludges/ash ammonium uranyl carbonate (AUC, (NH4)4*UO2*(CO3)3) 5.(c)
* ammonium diuranate
Criticality Safety Index 0.7
* dried iron (Fe) uranium (ADU, 3UO3*2NH3*4H2O)                                         compounds/mixtures/sludges/ash
: 6.
* ammonium uranyl carbonate (AUC, (NH4)4*UO2*(CO3)3) 5.(c)     Criticality Safety Index                                   0.7
In addition to the requirements of Subpart G of 10 CFR Part 71:
: 6.         In addition to the requirements of Subpart G of 10 CFR Part 71:
(a)
(a)       The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the application, as supplemented. Within each ICCA, the contents and secondary packaging (i.e., dunnage) must provide a snug fit.
The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the application, as supplemented. Within each ICCA, the contents and secondary packaging (i.e., dunnage) must provide a snug fit.
(b)       Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the application.
(b)
: 7.         The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the application.
: 8.         Transport by air of fissile material is not authorized.
: 7.
: 9.         Revision No. 8 of this certificate may be used until June 30, 2021.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
: 10.       Expiration date: November 30, 2025.
: 8.
Transport by air of fissile material is not authorized.
: 9.
Revision No. 8 of this certificate may be used until June 30, 2021.
: 10.
Expiration date: November 30, 2025.  


NRC FORM 618                                                                           U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
: 1. a. CERTIFICATE NUMBER       b. REVISION NUMBER   c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE       PAGES 9294                 9                 71-9294         USA/9294/AF-96                 4   OF   4 REFERENCES Global Nuclear Fuel - Americas, LLC, application dated December 12, 2019.
: 1.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION John B.                           Digitally signed by John B.
: a. CERTIFICATE NUMBER
McKirgan McKirgan                          Date: 2020.06.19 20:38:33
: b. REVISION NUMBER
                                                                                        -04'00' John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: June 19, 2020}}
: c. DOCKET NUMBER
: d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9
71-9294 USA/9294/AF-96 4
OF 4
REFERENCES Global Nuclear Fuel - Americas, LLC, application dated December 12, 2019.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: June 19, 2020 John B.
McKirgan Digitally signed by John B.
McKirgan Date: 2020.06.19 20:38:33  
-04'00'}}

Latest revision as of 20:43, 10 December 2024

Certificate of Compliance No. 9294, Revision No. 9, for the Model No. New Powder Container Package
ML20157A251
Person / Time
Site: 07109294
Issue date: 06/19/2020
From: John Mckirgan
Office of Nuclear Material Safety and Safeguards
To:
Global Nuclear Fuel
WCAllen NMSS/DFM/STL 415.6877
Shared Package
ML20157A248 List:
References
EPID L-2019-LLA-0275
Download: ML20157A251 (4)


Text

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

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9

71-9294 USA/9294/AF-96 1

OF 4

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 P.O. Box 780 Wilmington, NC 28402 Global Nuclear Fuel - Americas, LLC, application dated December 12, 2019.

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

5.(a)

Packaging (1)

Model No.: NPC (2)

Description A cubic stainless steel and foam outer packaging with nine cylindrical containment vessels for the transport of type A quantities of low-enriched uranium oxide powder, pellets, and compounds of uranium as defined in 5(b). The overall package dimensions are approximately 45 inches wide, 45 inches deep, and 44 inches high.

The outer packaging consists of a 10-gage stainless steel outer shell with a ceramic fiber board liner and rigid polyurethane foam filler. The foam filler has a three-by-three array of vertical cylindrical cutouts that accommodate stainless steel sleeves for placement of the containment vessels. The outer packaging is equipped with a top cover that is secured to the outer packaging body by a combination of 16 closure cap screws and four closure strips secured by 24 bolts.

The containment vessel is a maximum 8.515 inches in inner diameter and approximately 32 inches in overall length. The containment vessel is constructed of 18-gage stainless steel, surrounded by a cadmium sheet and polyethylene wrap within a 24-gage stainless steel jacket. The containment vessel is closed by a 16-gage closure lid, a silicone rubber gasket, and a band clamp assembly, which is composed of a 0.063-inch thick strap and retainer, a T-bolt, and a nut.

The gross weight of the package (packaging and contents) is 1,302 kg (2,870 pounds). The maximum weight of the contents is 540 kg (1,190 pounds).

5.(a)

(3)

Drawings

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

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9

71-9294 USA/9294/AF-96 2

OF 4

The packaging is fabricated and assembled in accordance with the following Global Nuclear Fuel - Americas, LLC, Drawing Nos.:

177D4970, Sheet 1, Revision 1 177D4970, Sheet 2, Revision 0 177D4970, Sheet 3, Revision 0 177D4970, Sheet 4, Revision 0 177D4970, Sheet 5, Revision 0 177D4970, Sheet 6, Revision 0 177D4970, Sheet 7, Revision 0 177D4970, Sheet 8, Revision 1 SK105E4037, Sheet 2, Revision 1 (b)

Contents Table 1: Type, Form, and Maximum Quantity of Material Per Package Material Form (5.00 wt.% U-235)

Particle Size Restriction:

Minimum OD (Inches)

Maximum Loading per ICCA (kgs)

Maximum Loading per NPC (kgs)

Net Uranium Net Uranium Homogenous Uranium Compounds N/A 60.0 52.89 540.0 476.1 Heterogenous UO2 Pellets (BWR) 0.342 60.0 48.48 540.0 436.3 Heterogenous UO2 Pellets(PWR) 0.300 60.0 46.71 540.0 420.4 Heterogenous Uranium Compounds Unrestricted particle size 60.0 40.54 540.0 364.8 The Material Form Column must comply with the following constraints:

Neither solutions, free liquids, uranium metal nor uranium metal alloys are authorized and shall not be present. Homogenous and heterogenous uranium compounds may be mixed with other non-fissionable diluent materials (e.g., sand, iron, iron hydroxide, silica, carbon from ash, etc.) except for deuterium, tritium and beryllium.

The solid form material within any individual NPC must be the same.

Homogeneous and heterogeneous uranium materials are limited to solid form.

For purposes of determining if the homogenous or heterogeneous criteria apply: if the particle size distribution is such that a majority of the particles are 1730 µm or greater, then the heterogenous payload criteria of Table 1 applies. If a majority of the particle size distribution is below 1730 m, the homogenous payload criteria of Table 1 apply.

The maximum mass of any Inner Containment Canister Assembly (ICCA) inner packaging materials (e.g., plastic bags or bottles) is unrestricted provided the mean hydrogen atom density of the packaging materials to be shipped inside the inner volume of each ICCA is not greater than water.

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

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9

71-9294 USA/9294/AF-96 3

OF 4

Authorized materials also include UO2 pellets present in standard PWR and BWR reactor fuel assembly lattice designs (e.g., 17X17 PWR fuel assemblies, 10X10, 9X9, 8X8 BWR fuel assemblies).

The payload within an NPC may be distributed in any ratio within the nine ICCAs, provided that the Maximum Loading per ICCA and the Maximum Loading per NPC requirements of Table 1 are met. The payload within an ICCA can be enclosed in plastic poly bottle receptacles (e.g., bags, poly bottles, etc.).

The Material Form Column homogeneous and heterogeneous uranium compounds are dry solids resulting from scrap recovery and waste incineration processes. Example compounds include:

uranium oxides (UO2, U3O8, or UOx x>2) uranyl nitrate (UN, UO2(NO3)2) uranyl nitrate hexahydrate (UNH, UO2(NO3) 2*6H2O) uranium tetrafluoride (UF4) dried calcium (Ca) uranium compounds/mixtures/sludges/ash, (e.g.,

CaUO3, CaUO4, Ca2UO5, Ca2UO4, Ca3UO6, CaU3O10*4H2O, CaU6O19*11H2O and CaU6O19*10H2O) sodium uranate (Na2UO4) sodium diuranate (Na2U2O7) sodium diuranate hexahydrate (Na2U2O7*6H2O) dried sodium (Na) uranium compounds/mixtures/sludges/ash, (e.g.,

Na2U2O7*3H2O and Na2U2O7*H2O) ammonium diuranate (ADU, 3UO3*2NH3*4H2O) dried iron (Fe) uranium compounds/mixtures/sludges/ash ammonium uranyl carbonate (AUC, (NH4)4*UO2*(CO3)3) 5.(c)

Criticality Safety Index 0.7

6.

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

(a)

The package must be prepared for shipment and operated in accordance with the Operating Procedures in Chapter 7 of the application, as supplemented. Within each ICCA, the contents and secondary packaging (i.e., dunnage) must provide a snug fit.

(b)

Each packaging must be acceptance tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Chapter 8 of the application.

7.

The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.

8.

Transport by air of fissile material is not authorized.

9.

Revision No. 8 of this certificate may be used until June 30, 2021.

10.

Expiration date: November 30, 2025.

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

1.
a. CERTIFICATE NUMBER
b. REVISION NUMBER
c. DOCKET NUMBER
d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9294 9

71-9294 USA/9294/AF-96 4

OF 4

REFERENCES Global Nuclear Fuel - Americas, LLC, application dated December 12, 2019.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: June 19, 2020 John B.

McKirgan Digitally signed by John B.

McKirgan Date: 2020.06.19 20:38:33

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