ML24030A977
| ML24030A977 | |
| Person / Time | |
|---|---|
| Site: | 07109401 |
| Issue date: | 01/30/2024 |
| From: | Holtec |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML24030A975 | List: |
| References | |
| 11071001-NRC, EPID L-2023-NEW-0005 HI-2220077, Rev 0 | |
| Download: ML24030A977 (1) | |
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 9401 0
71-9401 USA/9401/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.
- 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 Holtec International 1 Holtec Blvd.
Camden, NJ 08104 Holtec International Report No. HI-2220077 Safety Analysis Report on THE HI-STAR 370 Package, Revision 0, dated January 30, 2024
- 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.:
HI-STAR 370 (2)
Description The HI-STAR 370, designed for transportation of defueled and irradiated reactor vessels and reactor vessel internals previously used for nuclear power generation at the end of their service life, where the description of the cask is summarized below.
Cask The cask is a right circular cylinder where the welded closure lid, the top flange, shell, baseplate and grout injection port define the containment boundary. The cask containment cavity is the heart of the package. The cask containment boundary also encloses the Gamma Capture Space (GCS), which is the grout filled space surrounding the loaded contents and bounded by the containment shell, lid, and baseplate. The overpack also features collapsible trunnions. The top forging has a bolted closure lid with two machined concentric grooves for elastomeric seals. The outer surface of the overpack inner shell is buttressed with a layered combination of lead, steel and neutron shielding material. The cask provides the containment boundary, shielding, and heat rejection capability of the package.
The cask is approximately 262 and 1/8th inches long, with a top flange inside diameter of 138 and 7/8th inches, and an outer diameter (including the trunnions) of 159 and 7/8th inches.
Table 7.4.1 of the SAR includes the maximum empty weight of the cask and the maximum gross weight for transportation (including the HI-STAR 370 and package contents).
(3) Drawings
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 9401 0
71-9401 USA/9401/B(U)-96 2
OF 3
The packaging shall be constructed and assembled in accordance with the following drawings:
(a)
HI-STAR 370 Cask Drawing 13241, Sheet 1, Rev. 2 5(b) Contents (1)
Type and form of material (a)
Defueled and irradiated reactor vessels and reactor vessel internals previously used for nuclear power generation.
5(b) Contents (continued)
(2)
Maximum quantity of material per package:
(a)
Reactor vessel and reactor vessel internals meeting the activity limits specified in Table 7.1.1 of the SAR.
(b)
Reactor vessel and reactor vessel internals meeting the minimum cooling time specified in Table 7.1.1 of the SAR.
(c)
Reactor vessel and reactor vessel internals under the maximum heat load specified in Table 7.1.1 of the SAR.
(d)
Reactors with diameters less than the maximum enveloping diameter specified in Table 7.1.1 of the SAR.
(e)
The maximum permissible quantity of fissile materials meets requirements of 10CFR71.15 for classification as fissile exempt material. Negligible fissile material.
(f)
Maximum weight of contents: 352,000 lbs.
- 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 Operating Procedures in Chapter 7 of the application; and (a)
The package must meet the Acceptance Tests and Maintenance Program of Chapter 8 of the application.
- 7.
The Criticality Safety Index (CSI) is 0.0.
- 8.
No air shipment is authorized.
- 9.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
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 9401 0
71-9401 USA/9401/B(U)-96 3
OF 3
- 10.
REFERENCES Holtec International Report No. HI-2220077 Safety Analysis Report on the HI-STAR 370 Package, Revision 0, dated January 30, 2024.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION TBD, TBD Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: TBD, TBD.