ML20071H190

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Enclosure 1: Certificate of Compliance 71-9355. Rev. 3
ML20071H190
Person / Time
Site: 07109355
Issue date: 03/12/2020
From: John Mckirgan
Storage and Transportation Licensing Branch
To: Al-Daouk A
US Dept of Energy (DOE)
Garcia-Santos N
Shared Package
ML20071H189 List:
References
EPID L-2018-LLA-0314
Download: ML20071H190 (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 9355 3

71-9355 USA/9355/B(U)-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 National Nuclear Security Administration P.O. Box 5400 Albuquerque, NM 87185 National Nuclear Security Administration application dated September 19, 2019.

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.:

435-B (2)

Description The Model No. 435-B package consists of multiple configurations. The package is a Category I container. When loaded and prepared for transport, the external dimensions of the 435-B package are approximately 83 inches (in.) [210.8 centimeters (cm)] tall and 70 in. [177.8 cm] in diameter (over the lower impact limiter). The maximum weight of the package is 10,100 pounds (lb.)

[4,545.5 kilograms (kg)].

Unless noted in the application, all elements of the 435-B package are made of Type 304 stainless steel in conformance with the American Standards for Testing Materials (ASTM) A240. The major components of the package include:

(i)

A baseThe base consists of the lower torispherical head, lower flange, lower internal impact limiter, and external impact limiter. The volume inside the external impact limiter is filled with 15 pounds per cubic feet (lb/ft3) polyurethane foam poured in place. The inside surface of the bottom shell is covered with a 1/4-inch thick layer of refractory insulation paper. A full penetration weld connects the lower torispherical head (1/2-inch thick plate) to the lower flange.

(ii)

A bellThe bell consists of the upper torispherical head, cylindrical shell, upper flange, vent and test port blocks, upper internal impact limiter, dual side thermal shield, head thermal shield, and the closure bolt access tube structure. Two, 1/4-inch thick, layers of refractory insulation paper cover the area of the containment wall adjacent to the tubes. Machined blocks of 30 lb/ft3 polyurethane foam are located between the tubes.

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 9355 3

71-9355 USA/9355/B(U)-96 2

OF 8

5.(a)

Packaging (Continued)

(2)

Description (iii)

Internal lodgments, made of aluminum, which support the Long Term Storage Shield (LTSS),

Disposal Canisters, or the IBL 437 (aka IBL 437C) Shielded Device (Type 1 or Type 2)The lodgments and the inner container designs allow maintaining the position of the payload in the package cavity during normal conditions of transport and hypothetical accident conditions.

The LTSS rests on a 1/2-inch thick plate covered with a 1/2-inch thick layer of neoprene rubber.

(iv)

LTSSThe LTSS consists of a central steel magazine, or barrel, surrounded by thick lead encased in a steel shell. The barrel contains four longitudinal holes, each of which can accommodate one drawer assembly.

(v)

An inner container, which supports shielded devices (including Hopewell Designs, Inc.

Shielded Devices and Transport Shield) The inner container holds a shielded device and provides support for the device and the blocking (dunnage) materials during transport.

(vi)

Two internal impact limitersThe internal impact limiters located at each end of the payload cavity include an array of 130 ASTM A249 or A269, Type TP304, stainless steel tubes. The impact limiters are curved on one side to match the inside of the torispherical head, and flat on the other. Each of the 130 tubes is tack-welded in three places to a stainless steel tube stabilizer sheet. Four stainless steel clips welded to the inner surface of the containment boundary in the lower and upper position hold the internal impact limiters in place.

The LTSS, Disposal Canisters, or shielded devices provide shielding. Shielding materials are lead, tungsten, steel, or depleted uranium. The LTSS provides the shielding for the sealed capsule content specified in Tables 1 and 2. Therefore, these sources must be packed in the LTSS drawer(s). The shielded devices, identified in Table 3, are self-shielding, and must be packed in an inner container for shipment as specified in Table 4.

(3)

Drawings The packaging is constructed in accordance with AREVA Federal Services LLC drawings:

1) 1916-01-01-SAR, 435-B Package Assembly SAR Drawing, sheets 1-7, Revision 7
2) 1916-01-02-SAR, 435-B LTSS Lodgment SAR Drawing, sheets 1-2, Revision 4
3) 1916-01-03-SAR, 435-B Inner Container SAR Drawing, sheets 1-2, Revision 4
4) 1916-01-04-SAR, 435-B Disposal Canister Lodgment SAR Drawing, sheets 1-2, Revision 0; and
5) 1916-01-05-SAR, 435-B IBL 437 Lodgment SAR Drawing, sheets 1-2, Revision 1.

5.(b)

Contents (1)

Type and form of material Radioactive sealed sources of isotopes described in Tables 1 through 5.

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 9355 3

71-9355 USA/9355/B(U)-96 3

OF 8

5.(b)

Contents (Continued)

(2)

Maximum quantity of material per package (i)

LTSS Table 1. Maximum Activity of LTSS Payload Source Nuclides 1, 2, 3, 4 Nuclide Maximum Activity Ci 60Co 12,970 137Cs 14,000 90Sr 1,000 226Ra (no Be) 5 20 226Ra Be 5 1.2 241Am (no Be) 6 1,000 241Am Be 6 6.6 192Ir 200 75Se 80 Notes:

1. Physical form of all nuclides is solid material in a sealed capsule.
2. The maximum decay heat limit for the 435-B package is 200W.
3. The values in the table represent the absolute maximum activities allowed in the 435-B. Individual payload activity limits depend on the configuration of the LTSS used.

Payload activity limits are specified in Section 7.1.4, Loading and Preparing the LTSS for Transport, of the application.

4. The sum of the LTSS payload activities listed above is 86,732 A2, which bounds the value for the Disposal Canister. This value exceeds the maximum number of A2 that could be transported.
5. Impurities may include oxygen, carbon, sulfur, bromine, and chlorine (hydrous and anhydrous).
6. Impurities may include oxygen and chlorine.

Table 2. Maximum Mass of LTSS Payload Source Nuclides. 1, 2 Nuclide Maximum Mass grams of Pu 238Pu (no Be) 75 g Pu 239Pu (no Be) 15 g Pu 239Pu Be 15 g Pu Notes:

1. Physical form of all nuclides is solid material in a sealed capsule.
2. Impurities may include oxygen.

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 9355 3

71-9355 USA/9355/B(U)-96 4

OF 8

5.(b)

Contents (Continued)

(2)

Maximum quantity of material per package (Continued)

(ii)

Inner Container-Shielded Devices Table 3. Maximum Activity and Weight of Shielded Devices 1 Model Name/Type Maximum Activity Ci Nominal Weight 2 lb.

Sealed Source Device Registry No.3 Group 1 Devices Gammator 50B, B, B34, G-50-B 420 1,800 NR-0880-D-802-S Gammator M34 1,920 1,850 NR-0880-D-806-S Gammator M38 3,840 2,250 NR-0880-D-806-S Gammacell 1000 (GC-1000)

-Models A through D

-Elite A through D, Type I and Type II 3,840 (bounding value) 2,800 NR-0880-D-808-S, NR-1307-D-102-S Gammacell 3000 (GC-3000)

-Elan A through C, Type I and Type II 2 3,048 3,300 NR-1307-D-102-S Group 3 Devices Gammacell-40 (GC-40 Exactor) 2,250 4 2,650 NR-1307-D-101-S Other Devices IBL 437 (aka IBL 437C) 5,160 4,550 MA-0219-D-813-S Notes:

1. Radionuclide in all cases is 137Cs.
2. Gammacell 3000 external secondary shielding is not credited in the shielding analysis.
3. Consult NRCs Sealed Source Device Registry for design and safety features of each model.
4. GC-40 activity is given for one of the two device components that make up a complete GC-40. Only one device component may be shipped at one time.

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 9355 3

71-9355 USA/9355/B(U)-96 5

OF 8

5.(b)

Contents (Continued)

(2)

Maximum quantity of material per package (Continued)

(ii)

Inner Container-Shielded Devices (Continued)

Table 4. Hopewell Designs, Inc. Shielded Devices and Transport Shield Model Name Maximum Activity Maximum Weight lb.

Option a Option b Option c Shielded Devices G10-1-360 530 Ci 137Cs or 2 Ci 60Co 1,200 G10-2-360 530 Ci 137Cs and 2 Ci 60Co Total 530 Ci 137Cs in 2 sources Total 2 Ci 60Co in 2 sources 1,900 G10-1-2600 2,800 Ci 137Cs or 5 Ci 60Co 1,600 G10-2-2600 2,800 Ci 137Cs and 5 Ci 60Co Total 2,800 Ci 137Cs in 2 sources Total 5 Ci 60Co in 2 sources 2,200 G10-2-2600-BX 2,800 Ci 137Cs and 5 Ci 60Co Total 2,800 Ci 137Cs in 2 sources Total 5 Ci 60Co in 2 sources 2,200 Transport Shield SC2323-GC60 5,952 Ci 137Cs and 1,945 Ci 60Co and shall not exceed 30W decay heat 3,500

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 9355 3

71-9355 USA/9355/B(U)-96 6

OF 8

5.(b)

Contents (Continued)

(2)

Maximum quantity of material per package (Continued)

(iii)

Disposal Canisters Table 5. Disposal Canisters Source Nuclides.1, 2, 3, 4 Nuclide Maximum Activity Ci 60Co 12,970 137Cs 27,000 90Sr 1,000 226Ra (no Be) 5 20 226Ra Be 5 4.88 192Ir 200 75Se 80 Notes:

1. Physical form of all nuclides is solid material in a sealed capsule.
2. The maximum decay heat limit for the 435-B package is 200 W.
3. The values in the table represent the absolute maximum activities allowed in the 435-B. Individual payload activity limits depend on the specific Disposal Canister used.

Payload activity limits are specified in Section 7.1.5, Loading and Preparing the Disposal Canisters for Transport of the application.

4. The sum of the LTSS payload activities listed above is 86,732 A2, which bounds the value for the Disposal Canister. This value exceeds the maximum number of A2 that could be transported.
5. Impurities may include oxygen, carbon, sulfur, bromine, and chlorine (hydrous and anhydrous).

(3)

The maximum weight of contents in the package is 5,160 lb. Conditions 5.(b)(3)(i) through (v) include the maximum weight of the authorized contents.

(i)

LTSS For the LTSS, the payload of isotopes other than plutonium is limited by the activity rather than their weight as depicted in Tables 1 and 2 of this certificate. The maximum weight of the LTSS and its contents is 4,660 lb.

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 9355 3

71-9355 USA/9355/B(U)-96 7

OF 8

5.(b)(3) Contents (Continued)

(ii)

Inner Container The maximum weight of the shielded device includes the mass of radioactive material and the source drawer.

Table 6. Maximum Weight of Inner Container Contents Content Type Maximum Weight lb.

Dunnage 500 Group 1-Shielded Device 3,500 Group 3-Shielded Device 3,500 IBL 437 (aka IBL 437C) 4,550 (iii)

Disposal Canisters Table 7. Maximum Weight of Disposal Canisters Payload Content Type Maximum Weight of Payload lb.

Lodgment 500 Heavy Disposal Canister 4,610 Medium Disposal Canister 4,630 Light Disposal Canister 4,165 (iv)

Honeywell Inc. Shielded Devices: Type 1 and Type 2 The maximum weight of Type 1 or Type 2 Honeywell devices is 3,500 lb.

(v)

The total fissile mass limit for the 435-B package is 15 grams.

(4)

Maximum decay heat Table 8. Maximum Decay Heat of the Packages Authorized Contents Content Type Decay Heat W

LTSS shielded devices 200 Inner container shielded devices 30 IBL 437 (aka IBL 437C)

Shielded Device 15 Hopewell Designs, Inc.

Transport Shield 30 Heavy disposal canister 200 Medium disposal canister 159 Light disposal canister 144

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 9355 3

71-9355 USA/9355/B(U)-96 8

OF 8

6.

Plutonium sources are not permitted for transport by air.

7.

Americium sources are not permitted for transport by air.

8.

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 Operating Procedures in Chapter 7.0 of the application; and (b)

The package must meet the Acceptance Tests and Maintenance Program of Chapter 8.0 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.

Expiration date: March 31, 2025.

REFERENCES National Nuclear Security Administration application dated September 19, 2019.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION John McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: _______

/RA/

3/12/20