ML18173A032

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Enclosure 1: Certificate of Compliance (Letter to T. Tate Certificate of Compliance No. 9372, Revision No. 1, for the Model No. TN-B1 Package)
ML18173A032
Person / Time
Site: 07109372
Issue date: 06/21/2018
From: John Mckirgan
Spent Fuel Licensing Branch
To: Travis Tate
Framatome
Saverot P
Shared Package
ML18173A031 List:
References
CAC l25164, EPID L-2017-LLA-0073
Download: ML18173A032 (9)
v • d • e


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 1 71-9372 USA/9372/B(U)F-96 1 OF 9
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. 8, dated March 27, 2018.

Richland, WA 99354

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.: 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 5.0 weight percent U-235. The package carries a maximum of (i) two Boiling Water Reactor (BWR) fuel assemblies or individual rods, meeting the ASTM C996-96 standard of enriched commercial grade uranium, enriched reprocessed uranium, 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 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 1 71-9372 USA/9372/B(U)F-96 2 OF 9 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 105E3738, sheets 1 and 2, Rev. 8 105E3738, sheet 3, Rev. 7 105E3739, Rev. 4 105E3740, Rev. 4 105E3741, Rev. 1 105E3742, Rev. 3 105E3743, Rev. 5 02-9162717, Rev. 1 Inner Container Drawings Contents Containers 105E3745, sheets 1-4, Rev. 8 105E3773, Rev. 1 105E3746, Rev. 1 0028B98, Rev. 1 105E3747, Rev. 4 105E3748, Rev. 2 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 1 71-9372 USA/9372/B(U)F-96 3 OF 9
5. continued (b) Contents (1) Type and form of material Enriched commercial grade uranium or enriched reprocessed uranium, as defined in ASTM C996-96, uranium oxide or uranium carbide fuel rods enriched to no more than 5.0 weight percent U-235, 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 Type 11x11 fuel assembly assembly assembly assembly 235 kg 240 kg 275 kg 281 kg Table 2: Maximum Authorized Concentrations 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 1 71-9372 USA/9372/B(U)F-96 4 OF 9 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 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 and poison rod specifications 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 and poison rod specifications are in accordance with Table 3 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 4 below.

(v) 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 5 below.

(vi) Uranium carbide or generic 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 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. REVISION NUMBER c. DOCKET NUMBER d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 9372 1 71-9372 USA/9372/B(U)F-96 5 OF 9 5.(b)(1) continued Table 3: Fuel Assembly Parameters (8x8, 9x9, 10x10)

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

Theoretical Theoretical Theoretical Theoretical Number of water rodsa # 0, 2x2 0, 2-2x2 0, 2-2x2 0, 2-2x2 off-center off-center off-center diagonal, 3x3 diagonal, 3x3 diagonal, 3x3 Number of fuel rods # 60 - 64 72 - 81 91 - 100 91 - 100 Fuel Rod OD cm 1.176 1.093 1.000 1.010 Fuel Pellet OD cm 1.05 0.96 0.895 0.895 Cladding Type Zirconium Alloy Zirconium Alloy Zirconium Alloy 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 381 381 385 385 Nominal Fuel Rod Pitch cm 1.63 1.45 1.30 1.30 U-235 Pellet Enrichment wt% 5.0 5.0 5.0 5.0 Maximum Lattice Average Enrichment wt% 5.0 5.0 5.0 5.0 Channel Thicknessb cm 0.17 - 0.3048 0.17 - 0.3048 0.17 - 0.3048 0.17 - 0.3048 Partial Length Fuel Rods (1/3 through 2/3 normal length) Max # None 12 14 14 Gadolinia Requirements Lattice Average Enrichmentc #

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

< 4.7 wt% U-235 Gd2O3 6 @ 2 wt% 8 @ 2 wt% 12 @ 2 wt% 12 @ 2 wt%

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

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

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

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

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

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

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

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

< 3.5 wt% U-235 2 @ 2 wt% 2 @ 2 wt% 4 @ 2 wt% 4 @ 2 wt%

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

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

< 3.0 wt% U-235 None None 2 @ 2 wt% 2 @ 2 wt%

< 2.9 wt% U-235 None None None None Polyethylene Equivalent Massd (Maximum per Assembly) kg 11 11 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 1 71-9372 USA/9372/B(U)F-96 6 OF 9 5.(b)(1) continued Table 4: Fuel Assembly Parameters (11x11)

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 Fuel Pellet OD cm 0.820 Cladding Type Zirconium Alloy Cladding ID cm 0.840 Cladding Thickness cm 0.045 Equivalent Nominal Fuel Rod Pitch cm 1.195 U-235 Pellet Enrichment wt% 5.0 Maximum Lattice Average Enrichment wt% 5.0 Fuel Channel Side Thicknessb cm 0.254 Full Length Fuel Rods Quantity # 92 Active Length cm 385 Short Part Length Fuel Rods Quantity # 12 Active Length cm 155.1 Long Part Length Fuel Rods Quantity # 8 Active Length cm 236.8 Gadolinia Requirements Lattice Average Enrichmentc 5.0 wt% U-235 13 @ 2 wt%

4.8 wt% U-235 12 @ 2 wt%

4.6 wt% U-235 11 @ 2 wt%

4.4 wt% U-235 10 @ 2 wt%

4.2 wt% U-235 9 @ 2 wt%

4.1 wt% U-235 8 @ 2 wt%

3.9 wt% U-235 # @ wt% 7 @ 2 wt%

3.8 wt% U-235 Gd2O3 6 @ 2 wt%

3.6 wt% U-235 5 @ 2 wt%

3.5 wt% U-235 4 @ 2 wt%

3.3 wt% U-235 3 @ 2 wt%

3.2 wt% U-235 2 @ 2 wt%

2.9 wt% U-235 None Polyethylene Equivalent Mass kg 10.2 (Maximum per Assembly)d

a. Density based on a pellet modeled as a right 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 1 71-9372 USA/9372/B(U)F-96 7 OF 9 5.(b)(1) continued Table 5: Fuel Rod Parameters Parameter Units Type CANDU- CANDU-Fuel Assembly 8x8 9x9 10x10 11x11 Generic 14 25 Type (UO2) (UO2) (UO2) (UO2) PWR (UO2)

(UC) (UC)

UO2 or UC g/cm3 10.74 10.74 10.74 10.763 13.36 13.36 10.74 Fuel Densitya 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. Alloy Zirc. Alloy Zirc. Alloy Cladding Type Zirc. Alloy Zirc. Alloy Zirc. Alloy Zirc. 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 Length cm <381 <381 <385 385 <47.752 <40.013 <450 Maximum U-235 wt.% <5.0 <5.0 <5.0 5.0 <5.0 <5.0 <5.0 Pellet Enrichment Maximum Average fuel rod wt.% <5.0 <5.0 <5.0 5.0 <5.0 <5.0 <5.0 Enrichment Loose Rod Configuration Freely Loose or

  1. <25 <25 <25 <25 N/A N/A N/A Strapped Together Packed in 5 SS Pipe or protective
  1. <22 <26 <30 <30 <74b <130b <105b Case, i.e., SS Box with Lid
a. Density based on a pellet modeled as a right 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 1 71-9372 USA/9372/B(U)F-96 8 OF 9 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), and 5(b)(1)(iv): two fuel assemblies.

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

(c) Criticality Safety Index, except for contents described in 5(b)(1)(vi) and limited in 5(b)(2)(ii) 1.0 Criticality Safety Index for contents described in 5(b)(1)(vi) and limited in 5(b)(2)(ii) 2.1

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 prepressure 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. ATRIUM 11x11 fuel shall contain only commercial grade uranium, i.e., cannot be made from down-blended low enrichment fuel or reprocessed uranium.
8. 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.
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.

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 1 71-9372 USA/9372/B(U)F-96 9 OF 9
11. Revision No. 0 of this certificate may be used until April 30, 2019.
12. Expiration date: April 30, 2019.

REFERENCES Framatome TN-B1 Safety Analysis Report, FS1-0014159, Revision 8, dated March 27, 2018.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA/

John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Date: June 21, 2018

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