ML20037A134: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter: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 9282                                 4                 71-9282               USA/9282/B(U)-96                     1   OF       3
{{#Wiki_filter: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 9282 4
71-9282 USA/9282/B(U)-96 1
OF 3
: 2. PREAMBLE
: 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.
: 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.
Line 25: Line 30:
: b. other applicable regulatory agencies, including the government of any country through or into which the package will be transported.
: b. 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
: 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 Source Production                                                        Source Production and Equipment Company, Inc.
: a.
and Equipment Company, Inc.                                             application dated February 9, 2015.
ISSUED TO (Name and Address)
113 Teal Street St. Rose, LA 70087-9691
: b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION Source Production and Equipment Company, Inc.
113 Teal Street St. Rose, LA 70087-9691 Source Production and Equipment Company, Inc.
application dated February 9, 2015.
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
: 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR Part 71, as applicable, and the conditions specified below.
5.
: 5.
(a)       Packaging (1)       Model No.: SPEC-300 (2)         Description The SPEC-300 is a radiographic device that consists of a source assembly, a depleted uranium shield, and a stainless steel enclosure. The radioactive source assembly is housed in a zircaloy or titanium S tube that is surrounded by the depleted uranium shield. The depleted uranium shield is secured in the stainless steel enclosure. The void space between the depleted uranium shield and the enclosure is filled with high density polyurethane foam.
(a)
Packaging (1)
Model No.: SPEC-300 (2)
Description The SPEC-300 is a radiographic device that consists of a source assembly, a depleted uranium shield, and a stainless steel enclosure. The radioactive source assembly is housed in a zircaloy or titanium S tube that is surrounded by the depleted uranium shield. The depleted uranium shield is secured in the stainless steel enclosure. The void space between the depleted uranium shield and the enclosure is filled with high density polyurethane foam.
The package is approximately 26 inches long, 14 inches wide, and 15 inches high (16.5 inches high when including the lifting eye blocks). The maximum gross weight of the package is 780 pounds.
The package is approximately 26 inches long, 14 inches wide, and 15 inches high (16.5 inches high when including the lifting eye blocks). The maximum gross weight of the package is 780 pounds.
(3)       Drawings The packaging is constructed and assembled in accordance with Source Production and Equipment Co., Inc. General Arrangement drawings: 19B000, sheets 1-8, Rev. 5, B190700, sheet 1, Rev. 5, and B190701, sheet 1, Rev. 1.
(3)
(b)         Contents (1)         Type and form of material Cobalt-60 sources which meet the requirements of special form radioactive material.
Drawings The packaging is constructed and assembled in accordance with Source Production and Equipment Co., Inc. General Arrangement drawings: 19B000, sheets 1-8, Rev. 5, B190700, sheet 1, Rev. 5, and B190701, sheet 1, Rev. 1.
(b)
Contents (1)
Type and form of material Cobalt-60 sources which meet the requirements of special form radioactive material.  


NRC FORM 618                                                                                 U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9282                        4              71-9282        USA/9282/B(U)-96                 2 OF     3 5.(b)     Contents (continued)
: 1.
(2)       Maximum quantity of material per package 11.1 TBq (300 Ci) (output)
: a. CERTIFICATE NUMBER 9282
: b. REVISION NUMBER 4
: c. DOCKET NUMBER 71-9282
: d. PACKAGE IDENTIFICATION NUMBER USA/9282/B(U)-96 PAGE 2
PAGES 3
OF 5.(b)
Contents (continued)
(2)
Maximum quantity of material per package 11.1 TBq (300 Ci) (output)
Output curies are determined in accordance with American National Standard N432-1980, Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography.
Output curies are determined in accordance with American National Standard N432-1980, Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography.
: 6.       The source shall be secured in the shielded position of the packaging by the source assembly lock, lock cap and safety plug assembly. The safety plug assembly, lock cap and source assembly must be fabricated of materials capable of resisting a 1475°F fire environment for one-half hour and maintaining their positioning function. The locking ball of the source assembly must engage the locking device. The flexible cable of the source assembly and safety plug assembly must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.
: 6.
: 7.       The name plate must be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining its legibility.
The source shall be secured in the shielded position of the packaging by the source assembly lock, lock cap and safety plug assembly. The safety plug assembly, lock cap and source assembly must be fabricated of materials capable of resisting a 1475°F fire environment for one-half hour and maintaining their positioning function. The locking ball of the source assembly must engage the locking device. The flexible cable of the source assembly and safety plug assembly must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.
: 8.       In addition to the requirements of Subpart G of 10 CFR Part 71:
: 7.
(a)       The package shall be prepared for shipment in accordance with the Operating Procedures in Chapter 7.0 of the application, as supplemented; and (b)       The package must meet the Acceptance Test and Maintenance Program of Chapter 8.0 of the application, as supplemented.
The name plate must be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining its legibility.
: 9.       The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
: 8.
: 10.       Revision No. 3 of this certificate may be used until February 28, 2021.
In addition to the requirements of Subpart G of 10 CFR Part 71:
: 11.       Expiration date: April 30, 2025.
(a)
The package shall be prepared for shipment in accordance with the Operating Procedures in Chapter 7.0 of the application, as supplemented; and (b)
The package must meet the Acceptance Test and Maintenance Program of Chapter 8.0 of the application, as supplemented.
: 9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
: 10.
Revision No. 3 of this certificate may be used until February 28, 2021.
: 11.
Expiration date: April 30, 2025.  


NRC FORM 618                                                                           U.S. NUCLEAR REGULATORY COMMISSION (8-2000) 10 CFR 71 CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES
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 9282                4                71-9282        USA/9282/B(U)-96                 3 OF     3 REFERENCES Source Production and Equipment Company, Inc., application dated February 9, 2015.
: 1.
Request for Timely Renewal of Certificate of Compliance (CoC) No. 9282 letter dated January 17, 2020.
: a. CERTIFICATE NUMBER 9282
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
: b. REVISION NUMBER 4
                                                          /RA/
: c. DOCKET NUMBER 71-9282
: d. PACKAGE IDENTIFICATION NUMBER USA/9282/B(U)-96 PAGE 3
PAGES 3
OF REFERENCES Source Production and Equipment Company, Inc., application dated February 9, 2015.
Request for Timely Renewal of Certificate of Compliance (CoC) No. 9282 {{letter dated|date=January 17, 2020|text=letter dated January 17, 2020}}.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION  
/RA/
Daniel I. Doyle, Acting Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: February 7, 2020}}
Daniel I. Doyle, Acting Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: February 7, 2020}}

Latest revision as of 03:48, 20 December 2024

Certificate of Compliance No. 9282, Revision 4 for Radioactive Materials Packages
ML20037A134
Person / Time
Site: 07109282
Issue date: 02/10/2020
From: Dan Doyle
Office of Nuclear Material Safety and Safeguards
To:
Source Production & Equipment Co
Saverot P
Shared Package
ML20037A119 List:
References
EPID L-2020-RNW-0006
Download: ML20037A134 (3)


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 9282 4

71-9282 USA/9282/B(U)-96 1

OF 3

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.

This certificate does not relieve the consignor from compliance with any requirement of the regulations of the U.S. Department of Transportation or

b. 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 Source Production and Equipment Company, Inc.

113 Teal Street St. Rose, LA 70087-9691 Source Production and Equipment Company, Inc.

application dated February 9, 2015.

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.: SPEC-300 (2)

Description The SPEC-300 is a radiographic device that consists of a source assembly, a depleted uranium shield, and a stainless steel enclosure. The radioactive source assembly is housed in a zircaloy or titanium S tube that is surrounded by the depleted uranium shield. The depleted uranium shield is secured in the stainless steel enclosure. The void space between the depleted uranium shield and the enclosure is filled with high density polyurethane foam.

The package is approximately 26 inches long, 14 inches wide, and 15 inches high (16.5 inches high when including the lifting eye blocks). The maximum gross weight of the package is 780 pounds.

(3)

Drawings The packaging is constructed and assembled in accordance with Source Production and Equipment Co., Inc. General Arrangement drawings: 19B000, sheets 1-8, Rev. 5, B190700, sheet 1, Rev. 5, and B190701, sheet 1, Rev. 1.

(b)

Contents (1)

Type and form of material Cobalt-60 sources which meet the requirements of special form radioactive material.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER 9282
b. REVISION NUMBER 4
c. DOCKET NUMBER 71-9282
d. PACKAGE IDENTIFICATION NUMBER USA/9282/B(U)-96 PAGE 2

PAGES 3

OF 5.(b)

Contents (continued)

(2)

Maximum quantity of material per package 11.1 TBq (300 Ci) (output)

Output curies are determined in accordance with American National Standard N432-1980, Radiological Safety for the Design and Construction of Apparatus for Gamma Radiography.

6.

The source shall be secured in the shielded position of the packaging by the source assembly lock, lock cap and safety plug assembly. The safety plug assembly, lock cap and source assembly must be fabricated of materials capable of resisting a 1475°F fire environment for one-half hour and maintaining their positioning function. The locking ball of the source assembly must engage the locking device. The flexible cable of the source assembly and safety plug assembly must be of sufficient length and diameter to provide positive positioning of the source in the shielded position.

7.

The name plate must be fabricated of materials capable of resisting the fire test of 10 CFR Part 71 and maintaining its legibility.

8.

In addition to the requirements of Subpart G of 10 CFR Part 71:

(a)

The package shall be prepared for shipment in accordance with the Operating Procedures in Chapter 7.0 of the application, as supplemented; and (b)

The package must meet the Acceptance Test and Maintenance Program of Chapter 8.0 of the application, as supplemented.

9.

The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.

10.

Revision No. 3 of this certificate may be used until February 28, 2021.

11.

Expiration date: April 30, 2025.

NRC FORM 618 (8-2000) 10 CFR 71 U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE FOR RADIOACTIVE MATERIAL PACKAGES

1.
a. CERTIFICATE NUMBER 9282
b. REVISION NUMBER 4
c. DOCKET NUMBER 71-9282
d. PACKAGE IDENTIFICATION NUMBER USA/9282/B(U)-96 PAGE 3

PAGES 3

OF REFERENCES Source Production and Equipment Company, Inc., application dated February 9, 2015.

Request for Timely Renewal of Certificate of Compliance (CoC) No. 9282 letter dated January 17, 2020.

FOR THE U.S. NUCLEAR REGULATORY COMMISSION

/RA/

Daniel I. Doyle, Acting Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: February 7, 2020