ML21049A060

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Renewed Certificate of Compliance 9337
ML21049A060
Person / Time
Site: 07109337
Issue date: 02/23/2021
From: John Mckirgan
Storage and Transportation Licensing Branch
To: Ashley Ferguson
Croft Associates Limited
WCAllen - NMSS/DFM/STL - 301.415.6877
Shared Package
ML21049A058 List:
References
CoC No. 9337, EPID: L-2021-RNW-0000 CoC No. 9337
Download: ML21049A060 (7)
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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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 1 OF 7
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 Croft Associates Limited Croft Associates Limited application dated Building F4, Culham Science Centre July 30, 2009, as supplemented.

Culham, Abingdon Oxfordshire, OX14 3BD, United Kingdom

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.: 3979A (2) Description The Model No. 3979A is a package for the transport of radioisotopes used in a wide range of therapeutic and diagnostic applications and research. The packaging consists of an outer stainless steel keg and an inner containment vessel surrounded by insulating cork packing. There are three specific inserts authorized for use in the Model No. 3979A, designated as Shielding Insert Design Nos. 3983, 3984, and 3986. The outer keg provides impact and thermal protection. Containment is provided by the containment vessel. Shielding is provided by the containment vessel and shielding insert.

The keg has a stainless steel outer shell and a stainless steel liner, between which insulating cork is fitted. The keg lid is attached to the body by 8 stainless steel studs and nuts, with a single O-ring weather seal. An inner cork liner is fitted between the keg liner and the top and sides of the containment vessel, consisting of a cork body and cork top, with no cork between the bottom of the containment vessel and the keg liner.

The containment vessel consists of a body and lid. The body has a stainless steel outer wall, base, and flange/cavity wall. The flange/cavity wall is welded to the outer wall to form a cavity into which

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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 2 OF 7 5.(a) (2) Description (Continued) the lead shielding is cast. The base is then welded to the outer wall. The containment vessel lid top and lid shielding casing are stainless steel, with 22 mm of lead cast inside. The containment vessel lid is secured by eight, M-10x1.5x20, alloy steel recessed hexagon socket head cap screws. The containment system is sealed by two concentric ethylene propylene rubber O-rings, and the lid is equipped with a leak test port.

There are three Shielding Inserts designed for use in the Model No. 3979A packaging. Design No.

3983, LS-31x73-Tu, is a tungsten insert with inner cavity size of 31 mm diameter by 73 mm height.

The approximate mass of the insert is 4.9 kg. Design No. 3984, LS-12x65-Tu, is a tungsten insert with inner cavity size of 12 mm diameter by 65 mm in height. The approximate mass of the insert is 5.8 kg. The third design, Design No. 3986, LS-50x103-SS, is a stainless steel insert with inner cavity size of 50 mm diameter by 103 mm height. The approximate mass of the insert is 1.0 kg.

The radioactive material may be enclosed in any convenient product container such as a quartz vial or aluminum capsule. Irradiated items may be carried in plastic or metal can or wrapping to minimize the contamination of the insert.

The approximate dimensions and mass of the package are:

Overall package outer diameter 424 mm Overall package height 483 mm Containment vessel outer diameter 175 mm Containment vessel height 204 mm Containment vessel cavity inner diameter 65 mm Containment vessel cavity inner height 109 mm Maximum package mass 65 kg (3) Drawings The packaging is constructed and assembled in accordance with Croft Associates Limited Drawing Nos:

1C-6040, Rev. H Cover Sheet for Safkeg LS Design No. 3979A (Licensing Drawing) 0C-6041, Rev. C SAFKEG LS Design No 3979A (Licensing Drawing) 0C-6042, Rev. F Keg Design No. 3979 (licensing Drawing) 0C-6043, Rev. C Cork Set for Safkeg LS (Licensing Drawing) 1C-6044, Rev. F Containment Vessel Design No. 3980 (Licensing Drawing) 1C-6045, Rev. E Containment Vessel Lid (Licensing Drawing) 1C-6046, Rev. E Containment Vessel Body (Licensing Drawing)

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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 3 OF 7 5.(a) (3) Drawings (Continued)

The shielding inserts are constructed and assembled in accordance with Croft Associates Limited Drawing Nos:

2C-6171, Rev. C LS-12x65-Tu Insert Design No. 3984 (Licensing Drawing) 2C-6172, Rev. C LS-31x73-Tu Insert Design No. 3983 (Licensing Drawing) 2C-6175, Rev. D LS-50X103-SS Insert Design No. 3986 (Licensing Drawing) 5.(b) Contents (1) Type and form of material Solid material must have melting point greater than 250o C.

(i) Solid, normal form material, as limited in Table 1, within insert Design No. 3984.

(ii) Solid, normal form material, as limited in Table 2, within insert Design No. 3983.

(iii) Solid, normal form material, as limited in Table 3, within insert Design No. 3986.

(iv) Krypton-79, and Xenon-133 gas, as limited in Table 4, within insert Design No. 3983.

(v) Solid, normal form material or solid sealed sources that meet the requirements of special form radioactive material, as limited in Table 5, within insert Design No. 3986.

(2) Maximum quantity of material per package Decay heat not to exceed 10 watts per package. The contents may include fissile materials provided the mass limits of 10 CFR 71.15, 71.22, or 71.23 are not exceeded. Mixtures of nuclides are allowed providing the sum of the proportionate amounts of each nuclide with respect to the quantities shown in the respective table does not exceed unity.

(i) For the contents described in 5(b)(1)(i):

Total mass of contents and insert not to exceed 5.8 kg. Maximum mass of radioactive material, is 30 g.

TABLE 1 Radionuclide Maximum TBq Radionuclide Maximum Radionuclide Maximum TBq TBq Ac-225 1.22E-01 I-131 1.34E+00 Re-188 5.74E-01 Ac-227 8.38E-01 In-111 1.42E+02 Rh-105 2.71E+02 Ac-228 1.07E-02 Ir-192 9.60E-01 Se-75 1.54E+02 Am-241 3.90E+00 Ir-194 2.58E-01 Sm-153 1.90E+02

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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 4 OF 7 Radionuclide Maximum TBq Radionuclide Maximum Radionuclide Maximum TBq TBq As-77 1.95E+02 Lu-177 3.43E+02 Sr-89 1.07E+02 Au-198 2.33E+00 Mo-99 2.80E-01 Sr-90 1.62E+01 Ba-131 4.52E-01 Na-24 7.80E-04 Tb-161 3.19E+02 C-14 4.80E+00 Np-237 7.80E-04 Th-227 1.79E+00 Co-60 2.28E-03 P-32 1.90E-02 Th-228 2.53E-03 Cs-131 2.24E+03 P-33 8.15E+02 Tl-201 4.84E+02 Cs-134 2.24E-02 Pb-203 1.45E+01 W-187 1.96E-01 Cs-137 1.42E-01 Pb-210 8.40E+01 W-188 6.02E-01 Cu-67 2.30E+02 Pd-109 1.73E+02 Y-90 8.76E-03 Hg-203 1.86E+02 Ra-223 8.46E-01 Yb-169 1.47E+02 Ho-166 2.42E-01 Ra-224 3.33E-03 Yb-175 3.69E+02 I-125 1.06E+03 Ra-226 3.62E-03 I-129 1.95E-04 Re-186 1.38E+02 (ii) For the contents described in 5(b)(1)(ii):

Total mass of contents and insert not to exceed 5.3 kg. Maximum mass of radioactive material, is 200 g.

TABLE 2 Radionuclide Maximum TBq Radionuclide Maximum Radionuclide Maximum TBq TBq Ac-225 8.35E-02 I-131 6.71E-01 Re-188 3.55E-01 Ac-227 4.70E-01 In-111 1.42E+02 Rh-105 2.71E+02 Ac-228 6.90E-03 Ir-192 4.30E-01 Se-75 1.54E+02 Am-241 1.13E+01 Ir-194 1.66E-01 Sm-153 1.90E+02 As-77 7.84E+01 Lu-177 3.43E+02 Sr-89 6.64E+01 Au-198 1.32E+00 Mo-99 1.52E-01 Sr-90 6.89E+00 Ba-131 2.56E-01 Na-24 5.66E-04 Tb-161 2.99E+02 C-14 3.20E+01 Np-237 5.20E-03 Th-227 1.01E+00 Co-60 1.53E-03 P-32 1.35E-02 Th-228 1.86E-03 Cs-131 2.24E+03 P-33 8.15E+02 Tl-201 4.84E+02 Cs-134 1.29E-02 Pb-203 7.34E+00 W-187 1.01E-01 Cs-137 7.09E-02 Pb-210 5.60E+02 W-188 3.72E-01 Cu-67 2.30E+02 Pd-109 1.73E+02 Y-90 6.41E-03 Hg-203 1.86E+02 Ra-223 4.74E-01 Yb-169 1.47E+02 Ho-166 1.66E-01 Ra-224 2.44E-03 Yb-175 3.65E+02 I-125 1.06E+03 Ra-226 2.54E-03 I-129 1.30E-03 Re-186 7.21E+01

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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 5 OF 7 5.(b)(2) (continued)

(iii) For the contents described in 5(b)(1)(iii):

Total mass of contents and insert not to exceed 2.5 kg. Maximum mass of radioactive material, is 800 g.

TABLE 3 Radionuclide Maximum TBq Radionuclide Maximum Radionuclide Maximum TBq TBq Ac-225 2.08E-02 I-129 5.20E-03 Ra-226 6.81E-04 Ac-227 5.40E-02 I-131 5.03E-02 Re-186 6.93E+00 Ac-228 1.41E-03 In-111 1.42E+02 Re-188 6.02E-02 Am-241 1.13E+01 Ir-192 2.10E-02 Rh-105 1.48E+01 As-77 2.85E+00 Ir-194 3.35E-02 Se-75 1.28E+00 Au-198 7.61E-02 Lu-177 3.43E+02 Sm-153 3.15E+01 Ba-131 2.31E-02 Mo-99 1.70E-02 Sr-89 1.06E+01 Bi-210 2.74E-02 Na-24 1.79E-04 Sr-90 8.94E-01 C-14 1.28E+02 Np-237 2.08E-02 Tb-161 1.69E+01 Co-60 3.68E-04 P-32 2.20E-02 Th-227 1.16E-01 Cs-131 2.24E+03 P-33 8.15E+02 Th-228 5.96E-04 Cs-134 1.62E-03 Pb-203 5.70E-01 Tl-201 4.84E+02 Cs-137 5.85E-03 Pb-210 2.39E+02 W-187 8.88E-03 Cu-67 7.67E+01 Pd-109 1.50E+01 W-188 6.31E-02 Hg-203 6.03E+01 Po-210 1.18E+01 Y-90 6.02E-03 Ho-166 4.46E-02 Ra-223 5.46E-02 Yb-169 5.06E+01 I-125 1.06E+03 Ra-224 7.83E-04 Yb-175 2.56E+00 (iv) For the contents described in 5(b)(1)(iv):

Total mass of contents and insert not to exceed 5.3 kg. Maximum mass of contents; i.e., radioactive material, is 429 g. Maximum volume of contents, including the material of the gas container, is 10cc.

TABLE 4 Radionuclide Maximum TBq Radionuclide Maximum TBq Kr-79 2.00E-01 Xe-133 3.45E+02

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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 6 OF 7 5.(b)(2) (continued)

(v) For the contents described in 5(b)(1)(v):

Total mass of contents and insert not to exceed 2.5 kg. Maximum mass of radioactive material, is 800 g.

TABLE 5 Radionuclide Maximum TBq Radionuclide Maximum Radionuclide Maximum TBq TBq Pu-238 1.14E+01 Pu-240 6.72E+00 U-235 Note 1 Pu-239 Note 1 Pu-241 Note 1 Note1: Fissile material must meet the mass limits and conditions of 10 CFR 71.15, Exemption from classification as fissile material, or of the general license in 10 CFR 71.22 or 71.23. For shipment under the general license for fissile material, 10 CFR 71.22, and plutonium-beryllium special form material, 10 CFR 71.23, package contents are limited to no more than a Type A quantity of radioactive material.

5.(c) Criticality Safety Index For the contents described in 5(b)(1)(v), as limited in 5(b)(2)(v), the criticality safety index must be calculated in accordance with the provisions of 10 CFR 71.22 or 71.23, as appropriate, and rounded up to the first decimal place. Criticality safety index is not required for material meeting the mass limits and conditions of 10 CFR 71.15.

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 in Section 7.0 of the application.

(b) The package must meet the Acceptance Tests and Maintenance Program in Section 8.0 of the application.

7. Air transport of plutonium is not authorized.
8. The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
9. Revision No. 3 of this certificate may be used until February 28, 2022.
10. Expiration date: April 30, 2026.

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 PAGE PAGES NUMBER 9337 4 71-9337 USA/9337/B(U)-96 7 OF 7 REFERENCES Croft Associates Limited application dated July 30, 2009.

Supplements dated: October 15, 2009; March 31, and, September 30, 2010; April 19, and September 5, 2012; April 20, July 17, and December 17, 2015; January 21, and March 10, 2016; February 21, 2021.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION John B. Digitally signed by John B.

McKirgan McKirgan Date: 2021.02.23 16:16:32

-05'00' John B. McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: February 23, 2021

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