ML23215A133
| ML23215A133 | |
| Person / Time | |
|---|---|
| Site: | 07109186 |
| Issue date: | 09/08/2023 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | US Dept of Energy, Naval Reactors |
| Shared Package | |
| ML23215A132 | List: |
| References | |
| Download: ML23215A133 (4) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9186 20 71-9186 USA/9186/B(U)F-96 1
OF 4
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 U.S. Department of Energy Division of Naval Reactors Washington, DC 20858 Safety Analysis for Shipping S8G Power Units in the S-6213 Container, Revision 7, dated June 16, 1975, as supplemented; and Safety Analysis for Shipment of S6W Shipboard Power Units in the Model 2 S-6213 PUSC, as supplemented.
- 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 Nos.:
Model 1, S-6213 Power Unit Shipping Container Model 2, S-6213 Power Unit Shipping Container (2)
Description A power unit shipping container (PUSC) for shipment of a power unit complete with control rods and control rod drive mechanisms installed.
The Model 1 S-6213 PUSC consists of a carbon steel cylindrical shell approximately 9-1/4 feet in outside diameter by 39-1/2 feet long, including hemispherical steel end impact limiters, with 10-3/4-foot outside diameter central flanges joining the barrel and cover halves.
The Model 2 S-6213 PUSC is of the same design as the Model 1, except that the primary container material is HY-80 steel. An internal pressure cap and seal ring are attached to the PUSC barrel flange. A power unit is supported in the PUSC by a centrally located thick circular steel plate (PU head) which is clamped between the central mating flanges of the PUSC and fastened by 94, 2-inch diameter high strength studs. The upper and lower extremities of the power unit cantilever into the barrel and cover halves without additional support. A shipping/lifting ring, a flange adapter, and a lower support adapter are installed in the container during shipment of the S9G shipboard power unit.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9186 20 71-9186 USA/9186/B(U)F-96 2
OF 4
5.(a) Packaging (Continued)
(2)
Description The PUSC is shipped in the horizontal position on a support frame which is secured to a specially built flatbed rail car.
The weight of the PUSC, including frame and contents, is approximately 320,000 pounds for shipment of the S9G shipboard power unit.
(3)
Drawings The Model 1 and Model 2 S-6213 PUSC are constructed in accordance with the drawings included in the applications (see references, below).
5.(b) Contents (1)
Type and form of material Unirradiated S9G power unit containing the Virginia Forward Fit Core, as described in supplement dated June 22, 2015.
(2)
Maximum quantity of material per package For the Model 1 S-6213 PUSC:
One S9G Power Unit containing Virginia Forward Fit Core.
For the Model 2 S-6213 PUSC:
One S9G Power Unit containing Virginia Forward Fit Core.
5.(c) Criticality Safety Index (CSI):
Minimum CSI to be shown on label for nuclear criticality control: 100 6.
All control rods shall be restrained in the power unit fuel cells by the control rod hold down latches.
7.
Transport by air of fissile material is not authorized.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9186 20 71-9186 USA/9186/B(U)F-96 3
OF 4
8.
For the Model 1 S-6213 PUSC, a nondestructive examination of the entire length of both inner and outer surfaces of the four tie-down support bracket-to-container wall butt welds shall be conducted prior to each loaded shipment.
(a)
The nondestructive examination in accordance with a written procedure may be by either:
(1)
The liquid penetrant method in accordance with:
(i)
Article 6, section V, ASME code, or (ii)
MIL-STD-271E, "Nondestructive Testing Requirements for Metals,"
section 5, October 31, 1973, or (iii)
NAVSHIPS 250-1500-1, "Welding Standard," section 12.5 (2) or the magnetic particle method in accordance with:
(i)
Article 7, section V, ASME code (Yoke Technique; Dry Particle Method; direct or rectified current), or (ii)
MIL-STD-271E, section 4; specifically 4.3.1 (General) and 5.6.1(coatings),
4.3.3 (Dry Powder), 4.3.3.3.6 (Continuous), and 4.3.3.3 (Procedure) as excepted by using direct or rectified current, 4.3.3.3.3 (Yoke Technique),
4.3.2.5 (sensitivity and cleaning), and 4.3.1.3 (smoothness), or (iii)
NAVSHIPS 250-1500-1, Section 12.4, 12.4.1 (General), 12.4.3 (Dry powder), 12.4.3.3.2.1 (Yoke Technique) using direct or rectified current.
(b)
If any indications, as defined in accordance with either:
(1)
Paragraph UA-93(a), appendix VIII, division 1, section VIII, ASME code (with 7(b)(2)(i), above), or (2)
Paragraphs UA-72 and UA-73, appendix VI, division 1, section VIII, ASME code (with 7(b)(2)(i), above), or (3)
Class 1 acceptance criteria of NAVSEA 0900-LP-003-8000, "Surface Inspection Acceptance Standards for Metal," with change 2, July 1, 1974 (with 7(b)(1)(ii) or 7(b)(2)(ii), above), or (4)
NAVSHIPS 250-1500-1, section 10.3.2 (with 7(b)(1)(iii) or 7(b)(2)(iii), above), as
- noted, are detected, the packaging shall be repaired and reinspected prior to use and shall be inspected prior to each shipment thereafter. Any defects shall be reported in accordance with 10 CFR §71.95.
U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 618 (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 9186 20 71-9186 USA/9186/B(U)F-96 4
OF 4
9.
Expiration date: July 31, 2028.
REFERENCES For the Model 1 S-6213 PUSC:
U.S. Naval Reactors application dated July 24, 1975.
Supplements dated: June 3, 1977; July 24, 1978; Naval Reactors letter G#C89-2838, dated May 22, 1989; Naval Reactors letter G#C90-03664, dated September 5, 1990; Naval Reactors letter G#92-03563, dated June 17, 1992; and Naval Reactors letter G#C92-03714, dated October 2, 1992; Naval Reactors letter G#97-03425, dated February 7, 1997; Naval Reactors letter G#C97-03614, dated September 29, 1997; Naval Reactors letter G#01-03619, dated December 11, 2001; Naval Reactors letter G#06-04833, dated December 18, 2006; Naval Reactors letter G#C08-00667, dated March 13, 2008; Naval Reactors letter G#11-04084, dated September 20, 2011; Naval Reactors letters G#C15-02760 dated June 22, 2015, and G#C01632 dated April 13, 2016; Naval Reactors letter G#16-04427, dated September 20, 2016; Naval Reactors letter G#C18-02888, dated June 13, 2018; Naval Reactors letter G#22-00013, dated January 18, 2022; and Naval Reactors Letter G#22-05956 dated December 28, 2022.
For the Model 2 S-6213 PUSC:
U.S. Naval Reactors application G#C91-11165, dated December 19, 1991.
Supplements dated: Naval Reactors letter G#92-03563, dated June 17, 1992; and Naval Reactors letter G#C92-03714, dated October 2, 1992; Naval Reactors letter G#97-03425, dated February 7, 1997; Naval Reactors letter G#C97-03614, dated September 29, 1997; Naval Reactors letter G#01-03619, dated December 11, 2001; Naval Reactors letter G#06-04833, dated December 18, 2006; Naval Reactors letter G#C08-00667, dated March 13, 2008; Naval Reactors letter G#11-04084, dated September 20, 2011; Naval Reactors letters G#C15-02760 dated June 22, 2015, and G#C01632 dated April 13, 2016; Naval Reactors letter G#16-04427, dated September 20, 2016; Naval Reactors letter G#C18-02888, dated June 13, 2018; Naval Reactors letter G#22-00013, dated January 18, 2022; Naval Reactors Letter G#22-05956 dated December 28, 2022.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Dated: September 8, 2023 Signed by Diaz-Sanabria, Yoira on 09/08/23