ML19025A105
| ML19025A105 | |
| Person / Time | |
|---|---|
| Site: | 07109309 |
| Issue date: | 01/24/2019 |
| From: | John Mckirgan Spent Fuel Licensing Branch |
| To: | Murray S Global Nuclear Fuel |
| Garcia-Santos N | |
| Shared Package | |
| ML19025A103 | List: |
| References | |
| EPID L-2018-RNW-0021 | |
| Download: ML19025A105 (8) | |
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 9309 12 71-9309 USA/9309/B(U)F
-96 1 OF 8 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 NEDO-33869 , Revision 10 , Global Nuclear Fuel
- Americas, LLC, application dated September 4 , 2018 , as supplemented
. 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.: 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 olyethylene 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 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 the event of a drop of the package. The fuel rod 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 (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 9309 12 71-9309 USA/9309/B(U)F
-96 2 OF 8 5.(a)(2) Descriptio n (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 nom inal 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.
8 105E3738, Sheet 1 , Rev. 1 1 105E3738, Sheet s 2- 3, Rev. 10 105E3739, Rev.
6 105E3740, Rev.
6 105E3741, Rev.
3 105E3742, Rev. 5 105E3743, Rev.
7 105E3744, Rev.
8 (ii) Inner Container Drawings 105E3745, Sheets 1
-4, Rev. 10 105E3746, Rev. 3 105E3747, Rev. 6 105E3748, Rev. 4 105E3749, Rev. 8
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 9309 12 71-9309 USA/9309/B(U)F
-96 3 OF 8 5.(a) (3) Drawings (Continue)
(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 uranium, as defined in ASTM C996, uranium oxide or uranium carbide fuel rods enriched to no more than 5.0 weight percent in the Uranium-235 (235 U) isotope, with limits specified in Table s 1 and 2 below.
Table 1. Maximum Weight of Uranium Dioxide Pellets per Fuel Assembly Type 8x8 fuel assembly Type 9x9 fuel assembly Type 10x10 fuel assembly 235 kg 240 kg 275 kg Table 2. Maximum Authorized Concentrations Isotope Maximum content 232 U 5.00 x 10-8 g/gU 234 U 2.00 x 10-3 g/gU 235 U 5.00 x 10-2 g/gU 236 U 2.50 x 10-2 g/gU 237 Np 1.66 x 10-6 g/gU 238 Pu 6.20 x 10-11 g/gU 239 Pu 3.04 x 10-9 g/gU 240 Pu 3.04 x 10-9 g/g U Gamma Emitters 4.4 x 10 5 MeV - Bq/kgU 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 9309 12 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 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 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. 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 4 below. (v) Uranium carbide or generic PWR uranium oxide fuel rods configured loose, in a 5
-i n. 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 (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 9309 12 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
- 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, P f is the absolute fill pressure, and P a is atmospheric pressure (refer to Section 3.4.4 of the application)
Parameter Units Type Type Type Type Fuel Assembly Type Rods 8 x 8 9 x 9 FANP 10 x 10 GNF 10 x 10 UO 2 Density % Theoretical Number of water rods (See Condition 8)
Water rods 0, 2 x 2 0, 2-2 x 2 off-center diagonal, 3x3 0, 2-2 x 2 off-center diagonal, 3x3 0, 2-2 x 2 off-center diagonal, 3x3 , 1-axially varying centered Number of fuel rods Number 60 - 64 72 - 81 91 - 100 Fuel Rod OD cm Fuel Pellet OD cm Cladding Type N/A Zirconium Alloy Cladding ID cm Cladding Thickness cm Active fuel length cm 85 Fuel Rod Pitch cm 1.692 51 35 1.3 63 235 U Pellet Enrichment wt% 5.0 Lattice Average Enrichment wt% 5.0 Channel Thickness cm 0.17 - 0.3048 Any Partial Length Fuel Rods Fuel Rods None Gadolinia Requirements Lattice Average Enrichment < 5.0 wt % 235 U < 4.9 wt % 235 U < 4.7 wt % 235 U < 4.6 wt % 235 U < 4.5 wt % 235 U < 4.3 wt % 235 U < 4.2 wt % 235 U < 4.1 wt % 235 U < 3.9 wt % 235 U < 3.8 wt % 235 U < 3.7 wt % 235 U < 3.6 wt % 235 U < 3.4 wt % 235 U < 3.3 wt % 235 U < 3.2 wt % 235 U < 3.1 wt % 235 U < 2.9 wt % 235 U # @ wt% Gd 2 O 3 7 @ 2 wt %
7 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
4 @ 2 wt %
4 @ 2 wt %
4 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
None None 10 @ 2 wt %
10 @ 2 wt % 8 @ 2 wt %
8 @ 2 wt %
8 @ 2 wt %
8 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
4 @ 2 wt %
4 @ 2 wt %
4 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
None 12 @ 2 wt %
12 @ 2 wt %
12 @ 2 wt %
10 @ 2 wt %
10 @ 2 wt %
9 @ 2 wt %
8 @ 2 wt %
8 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
6 @ 2 wt %
4 @ 2 wt %
4 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
2 @ 2 wt %
None 12 @ 2 wt %
11 @ 2 wt %
1 1 @ 2 wt % 10 @ 2 wt %
9 @ 2 wt %
9 @ 2 wt %
8 @ 2 wt %
8 @ 2 wt %
7 @ 2 wt % 7 @ 2 wt % 6 @ 2 wt % 5 @ 2 wt % 4 @ 2 wt %
3 @ 2 wt % 2 @ 2 wt %
1 @ 2 wt % None Polyethylene Equivalent Mass per assembly kg Thermal Performance Criteria d MPa r/t (P f 921/293 - P a 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 9309 12 71-9309 USA/9309/B(U)F
-96 6 OF 8 5.(b) (1) Type and form of material (continued)
Table 4. Fuel Rod Parameters Parameter Units Type Fuel Assembly Type N/A 8 x 8 (UO 2) 9 x 9 (UO 2) 10 x 10 (UO 2) CANDU-14 (UC) CANDU-25 (UC) Generic 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 < 1.0 2 < 1.00 < 1.267 < 0.951 < 1.004 Cladding Thickness cm > 0.038 > 0.036 > 0.038 > 0.033 Active Fuel Length cm < 381 < 385 < 47.752 < 40.013 < 450 235 U Pellet Enrichment wt.% < 5.0 Average Fuel Rod Enrichment wt.% < 5.0 Polyethylene Equivalent Mass a per Compartment b kg Unlimited Protective Sleeves: <
2.3 All other packing materials: <
27.5 within SS pipe, unlimited outside of SS pipe Reference Density for Polyethylene Equivalent Mass a Calculation b g/cm 3 Protective Sleeves: 0.925 Protective Sleeves: 1.005 All Other Packaging Materials: 0.08 All Other Packing Materials: 0.70 Thermal Performance Criteria f MPa r/t (P f 921/293 - P a r/t (P f 921/293 - P a Loose Rod Configuration N/A Maximum Number of Rods per Compartment based on the Maximum Active Fuel Length Freely Loose No. of fuel rods < 25 N/A Packed in 5
-in. SS Pipe or Protective Case c < 22 < 26 < 30 < 695d,e < 1 , 458d,e < 105 d Strapped Together
< 25 N/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 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, P f is the absolute fill pressure, and P a is atmospheric pressure (refer to Section 3.4.4 of the application)
.
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 9309 12 71-9309 USA/9309/B(U)F
-96 7 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 is 484 kg (1
,069 pounds).
(i) For the contents 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)(iv) and 5(b)(1)(v)
- allowable number of fuel rods, as specified in Table 4, per compartment (2 compartments per package).
(c) Criticality Safety Index, except for contents described in 5.(b)(1)(v) and limited in 5
.(b)(2)(ii) 1.0 Criticality Safety Index for contents described in 5.(b)(1)(v) and limited in 5
.(b)(2)(ii) 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 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 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES 1.a. CERTIFICATE NUMBERb.REVISION NUMBERc. DOCKET NUMBERd.PACKAGE IDENTIFICATION NUMBERPAGE PAGES 9309 12 71-9309USA/9309/B(U)F
-96 8 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 water rod, and the water rod locatio n 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 th e assembly, and the water rod location occupies a space equivalent to (a) two 2 x 2 fuel rod equivalentspaces on a diagonal at the center of the assembly, or (b) one 3 x 3 fuel rod equivalent space (9 fuelrods space) in the center of the assembly. These configurations 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 ro d can occupy a space equivalent to a single 2 x 2 fuel rod equivalent at the bottom of the assembly an d expanded at the top; this configuration is design ated as 1-axially varying centered in the table.
9.The package authorized by this certificate is hereby approved for use under the general license provisionsof 10 CFR 71.17.
1 0.Transport by air of fissile material is not authorized.
1 1.Revision No. 11 of this certificate may be used until November 30, 2019
.1 2.Expiration date: January 31 , 2024.REFERENCES NEDO-33869, Revision 10 , Global Nuclear Fuel - Americas, LLC, application dated September 4, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession Number (No.) ML18247A218). Supplement: January 10, 2019 (ADAMS Package Accession No. ML19010A108). FOR THE U.S. NUCLEAR REGULATORYCOMMISSION John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety
and Safeguards Date: