ML22266A191

Enclosure 4 - Markup of Revision 12 of the Certificate of Compliance No. 9309

ML22266A191
Person / Time
Site:	07109309
Issue date:	09/04/2018
From:	Global Nuclear Fuel
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML22266A187	List: ML22266A188 ML22266A190 ML22266A191
References
M220123
Download: ML22266A191 (9)

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 9309 1213 71-9309 USA/9309/B(U)F-96 1 OF 8

2. PREAMBLE

a. This certificate is issued to c ertify 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, Packa ging 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 RE PORT 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 1011, Global Nuclear Fuel -

P.O. Box 780 Americas, LLC, application dated September 4, 2018, Wilmington, NC 28402 as supplemented.

4. CONDITIONS

This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specifie d 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 transpo rt a maximum of two Boiling Water Reactor (BWR) fuel assemblies or individual rods that mee t the ASTM C996 standard of enriched commercial grade uranium, enriched reprocessed uranium, uranium oxide generic pressurized water reactor (PWR) or uranium carbide loose fuel r ods in a 5-inch diameter stainless steel pipe.

The RAJ-II packaging is comprised of one inner container and on e 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. Polyethylene 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 s tainless steel plates. The inner 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 are placed as shock absorbers to reduce shock in th e event of a drop of the package. The fuel rod cladding and welded end plugs provide pr imary containment of the radioactive material. The radioactive material is bound in cer amic 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 2 OF 8

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

The approximate dimensions and weights of the package are as f ollows:

Maximum gross shipping weight 1,614 kilograms (kg) (3,558 pou nds (lbs.))

Maximumweightofinnercontainer 308 kg (679 lbs.)

Maximumweightofoutercontainer 622 kg (1,371 lbs.)

Maximumweightofpackaging 930 kg (2,050 lbs.)

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

com ponent Protectivecasenominalmassper 87kg( 192 lbs.)

com ponent 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. 89 105E3738, Sheets 1-3, Rev. 11 105E3738, Sheets 2-3, Rev. 10 105E3739, Rev. 6 105E3740, Rev. 67 105E3741, Rev. 34 105E3742, Rev. 5 105E3743, Rev. 7 105E3744, Rev. 8

(ii) Inner Container Drawings 105E3745, Sheets 1-4, Rev. 1011 105E3746, Rev. 34 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 3 OF 8

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 enriched reprocessed urani um, as defined in ASTM C996, uranium oxide or uranium carbide fuel rods enriched to no more than 5.08.0 weight percent (wt%) in the Uranium-235 ( 235U) isotope, with limits specified in Tables 1 and 2 below.

Table 1. Maximum Weight of Uranium Dioxide Pellets per Fuel Assembly

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

235 kg 240 kg 275 kg

Table 2. Maximum Authorized 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 4 OF 8

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

(i) 8 x 8 fuel assemblies comprised of 60 to 64 rods in a squar e 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 squa re 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.

(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 specifications, and poison rod specification are in accordance with Table 3 below.

(iv) Uranium oxide fuel rods configured loose, in a 5-in. diame ter 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 4 below.

(v) Uranium carbide or generic PWR uranium oxide fuel rods conf igured loose, in a 5-in.

diameter schedule 40 stainless steel pipe. The maximum pellet diameter, minimum clad thickness, and rod specifications are in accordance with Table 4 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 5 OF 8

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

Table 3. Fuel Assembly Parameters

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 98 Number of water rods Water rods 0, 2 x 2 0, 2-2 x 2 0, 2-2 x 2 0, 2-2 x 2 (See Condition 8) off-center off-center off-center diagonal, 3x3, diagonal, 3x3 diagonal, 3x3 1-axially varying centered Number of fuel rods Number 60 - 64 72 - 81 91 - 100 Fuel Rod OD cm 1.176 1.093 1.000 1.010 Fuel Pellet OD cm 1.05 0.96 0.895 Cladding Type N/A Zirconium Alloy Cladding ID cm 1.10 1.02 0.933 0.934 Cladding Thickness cm 0.038 0.036 0.033 0.038 Active fuel length cm 381 385 Fuel Rod Pitch cm 1.692 1.51 1.35 1.363 235U Pellet Enrichment wt% 5.0 8.0 Lattice Average Enrichment wt% 5.0 8.0 Channel Thicknessa cm 0.17 -0.3048 Any Partial Length Fuel Rods Fuel Rods None 12 14 16 Gadolinia Requirements Lattice Average Enrichment (CSI=1.0)b #

< 5.0 wt % 235U @ wt% Gd2O3 7 @ 2 wt % 10 @ 2 wt % 12 @ 2 wt % 12 @ 2 wt %

< 4.9 wt % 235U 7 @ 2 wt % 10 @ 2 wt % 12 @ 2 wt % 11 @ 2 wt %

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

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

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

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

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

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

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

< 3.8 wt % 235U 4 @ 2 wt % 4 @ 2 wt % 6 @ 2 wt % 7 @ 2 wt %

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

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

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

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

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

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

< 2.9 wt % 235U None None None None 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

9309 1213 71-9309 USA/9309/B(U)F-96 6 OF 8

Table 3. Fuel Assembly Parameters (continued)

Parameter Units Type Type Type Type Fuel Assembly Type Rods 8 x 8 9 x 9 FANP 10 x 10 GNF 10 x 10 Gadolinia Requirements Lattice Average Enrichment (CSI=1.6)b #

< 8.0 wt % 235U @ wt% Gd2O3 N/A N/A N/A 22 @ 2 wt %

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

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

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

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

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

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

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

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

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

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

< 3.3 - 5.05 wt % 235U Same as to CSI=1.0

< 3.3 wt % 235U Same as Requirements

< 3.2 wt % 235U CSI=1.0 Requirements None

< 3.1 wt % 235U None

< 2.9 wt % 235U None

Same as CSI=1.0 Requirements

Same as CSI=1.0 Requirements Polyethylene Equivalent Mass per assemblyc kg 11 10.2 Thermal Performance Criteriad MPa r/t (Pf 921/293 - Pa) 31.1 MPa (4,514 psi)

a. Transport with or without channels is acceptable.

b. Required gadolinia rods must be distributed symmetrically ab out the major diagonal. Minimum required number of gadolinia r ods applies for full-length rod locations, excluding the lattice peripheral locations. Additional gadolinia r ods 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, P f 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 7 OF 8

5.(b)(1) Typeandformofmaterial(continued)

Table 4. Fuel Rod Parameters

Parameter Units Type Fuel Assembly 9 x 9 10 x 10 CANDU-14 CANDU-25 Generic Type N/A 8 x 8 (UO2)(UO2)(UO2)(UC)(UC)PWR (UO2)

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 > 0.036 > 0.038 > 0.033 Thickness cm > 0.038 Active Fuel Length cm < 381< 385< 47.752 < 40.013< 450 235U Pellet Enrichment wt.% < 5.0 8.0 5.0 Average Fuel Rod 8.0 5.0 Enrichment wt.% < 5.0 Polyethylene Protective Sleeves: < 2.3 Equivalent Massa All other packing materials: < 27.5 within per Compartmentb kg Unlimited SS pipe, unlimited outside of SS pipe 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 - Pa) 31.1 MPa r/t (Pf 921/293 - Pa) 56.3 MPa Criteriaf Loose Rod Configuration N/A Maximum Number of Rods per Compartment based on the Maximum Active Fuel Length Freely Loose <25 N/A Packed in 5-in. SS No. of fuel Pipe or Protective rods < 26 < 30 < 695d,e < 1,458d,e < 105d Casec < 22 Strapped Together < 25N/A

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 stainless steel (SS) box with li d.

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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 8 OF 8

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 maximum uranium payload i s 484 kg (1,069 pounds).

(i) For the contents 5.0 wt% 235U described in 5(b)(1)(i), 5(b)(1)(ii), and 5(b)(1)(iii): two f uel assemblies.

(ii) For the contents described in 5(b)(1)(iv) and 5(b)(1)(v) : allowable number of fuel rods, as specified in Table 4, per compartment (2 compartments per packa ge).

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

(c) Criticality Safety Index, except for contents described in 5(b)(1)(i), 5(b)(1)(ii), and 5(b)(1)(iii) 5.(b)(1)(v) and limited in 5.(b)(2)(ii) 1.0

Criticality Safety Index for contents described in 5(b)(1)(iv) and 5.(b)(1)(v) and limited in 5.(b)(2)(ii) 1.6

Criticality Safety Index for contents described in 5(b)(1)(iii) 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 shall 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 Maintenanc e Program of Chapter 8 of the application.

(c) Prior to each shipment, the stainless steel components of t he packaging must be visually inspected.

Packages in which stainless steel components show pitting corro sion, cracking, or pinholes are not authorized for transport.

(d) If wrapping is used on the unirradiated fuel assemblies, th e ends must be assured to be open during the shipment in the package.

7. Cluster separators are optional and may be comprised of poly ethylene or other plastics. Polyethylene or plastic mass limits shall be determined in accordance with Sect ion 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES

9309 1213 71-9309 USA/9309/B(U)F-96 9 OF 8

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

For 8 x 8 fuel assembly designs, there can be either 0 or 1 wa ter rod, and the water rod location occupies a space equivalent to 2 x 2 fuel rods. This is design ated as 0, 2 x 2 in the table.

For 9 x 9 and 10 x 10 fuel assembly designs, there can be eithe r 0, 1, or 2 water rods in the assembly, and the water rod location occupies a space equivalen t to (a) two 2 x 2 fuel rod equivalent 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 configuration s are designated as 0, 2 - 2 x 2 off-center diagonal, 3 x 3 in the table. Additionally, for GNF 10 x 10 fuel assembly designs, the water rod can occupy a space equivalent to a single 2 x 2 fuel rod equiva lent at the bottom of the assembly and expanded at the top; this configuration is designated as 1-axia lly varying centered in the table.

9. The package authorized by this certificate is hereby approve d 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. 11 12 of this certificate may be used until November 30, 2019.

12. Expiration date: January 31, 20242028.

REFERENCES

NEDO-33869, Revision 1011, Global Nuclear Fuel - Americas, LLC, application dated Sept ember 4, 2018 (Agencywide Documents Access a nd Management System (ADAMS) Acce ssion Number (No.)

ML18247A218).

Supplement: January 10, 2019 (ADAMS Package Accession No. ML19 010A108).

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards

Date: __________