ML18341A130

Enclosure 3 to E-53202 - Proposed Changes to CoC 9233, Revision 16

ML18341A130
Person / Time
Site:	07109233
Issue date:	12/06/2018
From:	TN Americas LLC
To:	Office of Nuclear Material Safety and Safeguards
Shared Package
ML18341A130	List: ML18341A130
References
E-53202
Download: ML18341A130 (6)

Text

Enclosure 3 to E-53202 Proposed Changes to Coe 9233 Revision 16

NRCFORM 618 (8-2000) 10CFR 71

. a. CERTIFICATE NUMBER 9233 to E-53202 Proposed Changes to CoC 9233 Revision 16 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 16 71-9233 USA/9233/B(U)-96 1

OF 5

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 cif the U.S. Department of Transportation or other applicable regulatory agencies, including the government of any country through or intc:'l 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)

TN Americas LLC 7135 Minstrel Way, Suite 300 Columbia, MD 21045

b. TITLE AND IDENTiFICATION OF REPORT OR APPLICATION TN Americas LLC application dated January 29, 2018.

Supplement dated December 6, 2018.

4: CONDITIONS

5.

This certificate is conditional upon fulfilling the requiremenis of 1 D CFR Part 71, as applicable, and the conditions specified below.

(a)

Packaging

( 1)

Model No.: TN-RAM (2)

Description The package is a steel encased iead shielded cask with wood i111pact limiters attached at both ends.. The cas~_is.a*righ_t c::irculat cylinder. T!ie oyerall dimensions of the packaging are approxirnately f78 inches long and 92 in<;:hes diameter with.the impact limiters installed. The cask bodyls appro.ximately 129 inches long with*an outet diameter of 51 inches. The cask p~vity has a lerigt~ of appr9xiinately 111 inches and an inside diameter of 35'inches. The cask body is made of :a o. 75-inch stainless steel inner shell, a 5.88-inch thick lead annulus, a 1.5'-ifrch thick stainless steel *outer shell, a 0:5-inch thick inner bottom plate and a 2.5-inch thick outside bottom plate. The lead shielding is

?!PProximately 6 inches thick in the bottom end of the cask. The outer shell of the cask body is covered with a stainless steel :thermal shield. The closure lid consists of a 2.5-inch thick outer stainless steei plate and a 0.5-inch thick inner stainless steel plate separated by approximately 6 inches of lead shielding. An optional lid, with the lead shielding in the form of a separate shielding disk, can also be used. The lid is secured by sixteen 1.5-inch diameter closure bolts. Two concentric silicone 0-rings are installed in grooves on the underside of the lid. The cask is equipped with a sealed leak test port between the 0-rings, a vent port in the clos1,1re lid and a sealed drain port in the bottom of the cask. Each impact limiter is attached to the cask by eight 1.'75-inch diameter bolts.

The cask is equipped with 6 trunnions, four at the top and two at the bottom. The gross weight of the package is approximately 80,000 pounds, including maximum contents of 9,500 pounds. There are two models of the TN-RAM: TN..;RAM No. 01 and TN-RAM No.

02, with different allowed radioactive quantities, as described in Condition 5.(b)(2)(ii) of this Certificate.

Page 1 of 5 to E-53202 Proposed Changes to CoC 9233 Revision 16 NRC FORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8*2000)

CERTIFICATE OF COMPLIANCE 10CFR71 FOR RADIOACTIVE MATERIAL PACKAGES

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGE.S 9233 16 71-9233 USA/9233/B{U)-96 2

OF 5.(a)

Packaging (continued)

(b)

(3)

Drawings The packaging is constructed in accordance with Transnuclear, Inc. Drawing Nos.

990-701, Rev. 10; 990-702, Rev.10; 990-703, Rev~ 11; 990-704, Rev. 7; 990-705, Rev. 8; 990-706, Rev. 5; 990-707, Rev. 6; 990-708, Rev.

• 990-709, Rev. 2; and 990-710, Rev. 2.

Contents 11 (1)

Type and Form of Material Dry irradiated and contaminated *non-fuel""bearing sol.id materials contained within a secondary container. No powdered material is authorized.

Materials other than steel must show shielding equivalence or better to steel for 6°Co. Localized regions of low..clensity material (e.g., 84C in a control rod blade) are acceptable if the low-density regions contain negligible source. The mass of any low-density re{;Jions shall not be credited in the specific.activity calculation.

(2)

Maximum quantity of material per package (i)

Greater than Type A q1,.1antities of radioactive material which may include fissile material provided thatthe fissile material does not exceed the mass limits of 10 CFR 71.15.' The combined quantity bfal_l radioactive material per pacKage is limited to 3,000 times an A2 quantity (as determined by using Table A-1 of Appendix A to 10 CFR Part 71 ).

Pure*Alpha and Beta. emittirig,iiyclides c3,re limited to 3;000 times an A2 quantity.

Significant neutron sources are l'lOtallowed.

The maximum total package neutron soµrce is 1 x 106 neutrons/se<::ond for materials that produce r:ieutrons (other than fissile neutrons) through any means, including spontaneous fission, alpha-neutron reactions, and gamma-neutron reactions.

Page 2 of 5 5

NRCFORM 618

{8-2000) 10CFR71

. a. CERTIFICATE NUMBER 9233 to E-53202 Proposed Changes to CoC 9233 Revision 16 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

b. REVISION NUMBER

.c. DOCKET NUMBER.

d. PACKAGE IDENTIFICATION NUMBER PAGE PAGES 16 71-9233 USA/9233/B(U)-96 3

OF 5

5.(b)(2)

Maximum quantity of material per package (continued)

(ii)

Gamma emitting radionuclides are limited to a combined total of 30,000 Ci of 6°Co

. ~

or equivalent for TN-RAM No. 01, or 18,000 Ci of 6°Co or equivalent for TN-RAM No. 02, as determined by the followin*g equation:

L s;(E)

~1

ActivityLimit;(E)

Where Eis the energy of the gamma emitter, Si(E) is the source strength of the gamma emitter, and Activity Umit i (E) is the limit in gammas per second (y/s} as a function of energy. For gammas with energies that do not correspond exactly to one of the energies in the table, the Activity Limit ;{E) used shall correspond to the next highest enE;irgy. Limits can be found in the following table:

Activity Limit (y/s)

Energy (MeV)

TN-RAM No. 01 TN-RAMNo. 02

'0.6 7.62E+l7

• 4.4sE+17 0.8 l.25E+l7

6.64E+l6 1

2.03E+l6

.. l.13E+16 1.1732 4.49E+15

• 2.63E+l5 1.3325 1.47E+15 8.92E+14 1.5 6.15E+I4 3.84E+14

.1.75 2.40E+l4 l.50E+I4 2

1.25E+I4 7.76E+I3 2.5

-'i

.5.52E+13

. 3.47E+13.*,

3 3A2E+l3 2.22E+l-3' 3.5

. 2.55E+l3.

l.67E+I3 4

2.14E+13 1.4iE+l3 4.5 1.90E+l3 l.23E+13 s*

1;?8E+13 l.18E+l3 6

1.66E+I3 l.10E+l3 8

1.58E+l3 l.04E+13 10 l.49E+13 9.69E+12 The average specific activity of discrete components is limited to 1 O Ci/kg of 6°Co or equivalent.

The volume of discrete components shall be divided into ten or more nearly equal volumes no greater than 0.1 m3* The specific activity of each volume is assessed (through measurements, calculations, or process knowledge) and the specific activity of individual volumes shall not exceed 1 O Ci/kg.

Page 3 of 5 to E-53202 Proposed Changes to CoC 9233 Revision 16 NRCFORM 618 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE

• FOR RADIOACTIVE MATERIAL PACKAGES

a. CERTIFICATE NUMBER

b. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE 5.(b)(2) 9233 16 71-9233 USA/9233/B(U)-96 4

OF Maximum quantity of material per package (continued)

Materials other than steel must show shielding equivalence or better to steel for 60cc. Localized regions of low-density material (e.g., 84C in a control rod blade) are acceptable if the low-density regions contain negligible source. The mass of any low-density regions shall not be credited in the specific activity calculation.

The decay heat of the contents may not exceed 500 W.

The maximum gross weight of the contents, which includes the secondary container and shoring, is limi.ted to 9,500 lb (4,309 kg).

6.

As appropriate, shoring must be used in the secondary container sufficient to prevent significant movement of the contents under accident conditions.

7.

Both the inner cask cavity and the secondary container must be free of water when the package is delivered to a carrier for transport.

8.

In addition to the requirements of Subpart G of 1 O CFR Part 71:

(a)

(b)

(c)

Prior to each shipment, the lid seals must be inspect.ad. The seals must be replaced with new seals if inspection show~ any defects or every 12 months, whichever occurs first; The package shall be preparec:l for shipment and operated in accqr9ance with the Operating Procedures of Section 7.0 of the ~ppliqation; and The package must meet the Acceptance Tests and Maintenance Program of Section 8.0 of the application.

9, The package authori *. d by this certificate is hereby approved for use under the general license provisions of10 71.17.

10.

Revision No, 1'\\of this certificate may be used until April 30, 2019.

11.

Expiration date: January 31, 2021.

REFERENCES TN Americas LLC, safety analysis report letter dated January 29, 2018.

!Supplement dated December 6, 2018. !

Page 4 of 5 PAGES 5

NRCFORM618 (8*2000).

10CFR71

. a. CERTIFICATE NUMBER 9233 to E-53202 Proposed Changes to CoC 9233 Revision 16 U.S. NUCLEAR REGULATORY COMMiSSION CERTIFICATE.. OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES b.. REVISION NUMBER

c. DOCKET NUMBER

d. PACKAGE IDENTIFICATION NUMBER PAGE 16 71-9233 USA/9233/B(U)-96 5

OF FOR H U.S. NUCL'A' REG.. ULATORY COMMISSION l¥-r~

Joh cKirgan, Chief Sp. t Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Page 5 of 5 PAGES 5