ML24218A175
| ML24218A175 | |
| Person / Time | |
|---|---|
| Site: | 07109392 |
| Issue date: | 08/05/2024 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | NAC International |
| Shared Package | |
| ML24218A174 | List: |
| References | |
| EPID L-2022-NEW-0000 | |
| Download: ML24218A175 (1) | |
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-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)
2 Sun Court, Suite 220 Peachtree Corners, GA 30092 OPTIMUS-H OPTImal Modular Universal Shipping Cask Safety Analysis Report - Revision No. 0, dated April 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.: OPTIMUS-H (2)
Description The OPTIMUS-H packaging consists of (i) the Cask Containment Vessel (CCV), (ii) the Outer Shield Vessel (OSV), and (iii) upper and lower impact limiters.
The CCV fits within the cavity of the OSV and is the packaging containment system. It is a stainless-steel cylindrical vessel that includes a body weldment, bolted lid, bolted port cover, and elastomeric O ring seals. The CCV has an outer diameter of 34.5 inches, which expands to 39.0 inches at the bolt flange and lid, and an overall height of approximately 51.4 inches.
The internal cavity of the CCV has a diameter of 32.5 inches by 47.0 inches high. The CCV cylindrical shell and bottom plate are both 1.0-inch thick. The CCV lid, which is 3.38 inches thick, is fastened to the CCV body by twelve (12) equally spaced 1-inch diameter socket head cap screws. The CCV includes an optional drain port that is used to drain water from the CCV cavity for wet-loading operations.
The OSV is a ductile cast iron vessel consisting of a body and lid. The OSV has an overall height of 61.5 inches and an outer diameter of 49.0 inches. The internal cavity of the OSV, with a diameter of 35.0 inches by 51.9 inches high, is large enough to accommodate the CCV with sufficient clearance to assure free differential thermal expansion. The OSV lid is fastened to the OSV body by twelve (12) 1.25-inch diameter heavy hex screws.
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 2
OF 8
5.(a)(2)
Description (Continued)
The cylindrical-shaped impact limiters fit over the upper and lower ends of the OSV assembly. The upper and lower impact limiters are identical, with a pocket that fits over the end of the OSV assembly and consisting of energy absorbing closed-cell polyurethane foam cores sealed inside the exterior stainless-steel inner and outer shells.
The packaging may also be configured with a Shield Insert Assembly (SIA), within the cavity of the CCV, to provide additional gamma shielding. The SIA is a coated carbon steel container, placed inside the CCV cavity, that is either 1-inch thick, 21/4-inch thick or 33/4-inch thick. The internal cavity of the 1-inch thick and 21/4-inch thick SIA has a diameter of 24.0 inches and a length of 35.3 inches, whereas the 33/4-inch thick SIA has a diameter of 24.0 inches and a length of 41.0 inches. The 21/4 inch and 33/4 inch SIAs both include lids providing supplemental top end gamma shielding.
The maximum weight of the contents (including the CCV, SIA, dunnage or shoring) is 7,300 lbs. and the maximum gross weight of the package is approximately 32,200 lbs.
(3)
Drawings The packaging is constructed and assembled in accordance with the following NAC International Drawing Nos.:
70000.14-L501 1P Packaging Assembly - OPTIMUS-H 70000.14-L510 0P CCV Assembly - OPTIMUS 70000.14-L511 0P CCV Body Weldment - OPTIMUS 70000.14-L512 0P CCV Lid - OPTIMUS 70000.14-L513 0P Port Cover - OPTIMUS 70000.14-L520 0P OSV Assembly - OPTIMUS-H 70000.14-L521 2P OSV Body - OPTIMUS-H 70000.14-L522 1P OSV Lid - OPTIMUS-H 70000.14-L530 1P Impact Limiter Assembly - OPTIMUS-H 70000.14-L550 1P 1-Inch Shield Insert Assembly (SIA) - OPTIMUS 70000.14-L551 1P 21/4-Inch Shield Insert Assembly (SIA) - OPTIMUS 70000.14-L552 1P 33/4-Inch Shield Insert Assembly (SIA) - OPTIMUS (b)
Contents (1)
Type and Form of Material Radioactive contents of the package include two (2) classes of waste, transuranic containing waste (TRU) and irradiated fuel waste (IFW), as summarized in Table 1.
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 3
OF 8
5.(b)(1) Type and Form of Material (continued)
Table 1 - Content Designations Contents Class Type Sub-Type Content ID Compliant(1) 1-1 Aerosol Cans, Type 1(2) 1-2A Aerosol Cans, Type 2(3) 1-2B TRU waste Non-Compliant(1)
Standard DOT 3E Lecture Bottle 1-2C LEU(4) 2-1 Irradiated Fuel Waste CANDU 2-2 Notes:
(1) Refers to Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) for TRU waste.
(2) Aerosol cans with compressed gas propellant.
(3) Aerosol cans with liquified gas propellant or unknown propellant.
(4) Low enriched uranium.
(i) Byproduct, source, special nuclear material, non-fissile or fissile-excepted, as special form or non-special form in the form of process solids or resins, either dewatered, solid, or solidified waste (Content 1-1).
(ii) Dewatered, solid, or solidified transuranic-containing wastes (TRU), fissile, non-fissile, or fissile-excepted (Content 1-1).
(iii) Neutron activated metals or metal oxides in solid form, including reactor components or segments of components of waste from a nuclear process or power plant (Content 1-1).
(iv) TRU waste containing standard DOT 2P or 2Q, 1 liter aerosol cans containing compressed gas propellant (Content 1-2A).
(v) TRU waste containing standard DOT 2P or 2Q, 1 liter aerosol cans with liquified gas propellant or unknown propellants (Content 1-2B).
(vi) TRU waste containing standard DOT 3E lecture bottles with known contents of nonflammable gases or with unknow contents (Content 1-2C).
(vii) Radioactive material in the form of LEU waste with or without activated metal structural components (e.g., cladding, liners, baskets, etc.) (Content 2-1).
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 4
OF 8
5.(b)(1) Type and Form of Material (continued)
(viii)
Irradiated CANDU fuel waste contents and irradiated hardware contents. Irradiated CANDU fuel contents are restricted to natural UO2 fuel of a typical CANDU fuel bundle design with cladding and bundle structure comprised exclusively of Zircaloy material (Content 2-2).
(ix) CANDU fuel baskets of irradiated hardware materials (Content 2-2).
5.(b)(2) Maximum quantity of material per package (i)
Compliant TRU Waste - Content 1-1:
a) Maximum weight of contents: 7,300 pounds including radioactive waste, secondary containers, SIA, and shoring.
b) Fissile contents must not exceed the fissile gram equivalents (FGE) in Table 2 for the specified criticality configuration limits. Plutonium contents in quantities greater than 0.74 TBq (20 Ci) must be in solid form.
c)
TRU waste contents shall comply with regulatory dose rate limits, as determined in accordance with Chapter 7, Attachment 7.5-1.
d) Compliant TRU waste may contain only one (1) form of non-compliant TRU waste contents.
TRU waste containing any approved non-compliant TRU waste items must also satisfy the maximum quantity requirements for the respective non-compliant TRU waste contents.
e) Except for approved non-compliant TRU waste contents, any other explosives, corrosives, non-radioactive pyrophorics, and sealed items containing compressed and/or flammable gas (e.g., aerosol cans, lecture bottles, etc.) are prohibited. Pyrophoric radionuclides may be present only in residual amounts less than 1 wt.%. All nonradioactive pyrophoric material shall be reacted (or oxidized) and/or otherwise rendered nonreactive prior to placement in a secondary container (e.g., drum).
f) Free liquids shall not exceed 1% of the CCV cavity volume.
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 5
OF 8
5.(b)(2) Maximum quantity of material per package (continued)
Table 2 - TRU Waste FGE Limits FGE Criticality Configuration Description Machine Compacted(2)
Weight %
Special Reflector(3)
Minimum 240Pu Credit Chemically or Mechanically Bound FGE Limit, (g 239Pu)(1)
FGE-1 1
335 FGE-2a 1
5 g 350 FGE-2b 1
15 g 370 FGE-2c 1
25 g 390 FGE-3
> 1 121 FGE-4
> 1
320 FGE-5
1 245 (1) FGE equivalents determined as described in Section 6.3.4 of the Application. FGE conversion based on a ratio of subcritical mass limits in ANSI/ANS-8.1 [1-7], SAR Section 5.2 of 0.7 kg (1.5 lb) for 235U and 0.45 kg (1.0 lb) for 239Pu (See Table 7-1 of the Application).
(2) For uncompacted or manually compacted TRU waste, materials with hydrogen density up to that of water (0.1117 g/ cm3) are unlimited, but materials with hydrogen density greater than water are limited to the hydrogen density of polyethylene (0.1336 g/cm3) and may not exceed 15% of the total contents by volume. For machine compacted contents, hydrogenous materials in the contents are limited to the hydrogen density of polyethylene (0.1336 g/cm3) in an unlimited quantity.
(3) Special reflector materials are defined as beryllium, beryllium oxide, carbon (graphite), heavy water, magnesium oxide, and depleted uranium. The weight% of the special reflector materials is calculated as the mass of all special reflector materials present divided by the total mass of all waste material contents inside the secondary container. For FGE-3, these materials are unlimited.
(ii)
Non-Compliant TRU - Content 1-2A, Content 1-2B, and Content 1-2C a) Content 1-2A - A maximum of ninety-five (95) standard DOT 2P or 2Q 1 liter aerosol cans.
b) Content 1-2B - A maximum of 4.4 liters of liquified gas propellant in any number of standard DOT 2P or 2Q 1 liter aerosol cans when the volume is known based on process knowledge x ray (or other) interrogation methods, or a maximum of four (4) full standard DOT 2P or 2Q 1 liter aerosol cans if the amount of liquified propellant, or type of propellant, in the aerosol cans is not known.
c) Content 1-2C - A maximum of eight (8) full Standard DOT 3E Lecture bottles with known contents of non-flammable gases, or a maximum of one (1) Standard DOT 3E Lecture bottle with unknown contents.
(iii)
Irradiated Fuel Waste a) Shall not exceed the Fissile Equivalent Mass (FEM) limits from Table 3 for the specified criticality configuration limits.
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 6
OF 8
5.(b)(2) Maximum quantity of material per package (continued) b) IFW contents shall comply with regulatory dose rates, as demonstrated in accordance with Chapter 7, Attachment 7.5-1 of the Application.
c) Irradiated CANDU fuel waste contents shall have a maximum burnup of 5 GWd/MTU, a minimum cooling time of 40 years, and a maximum fuel mass of 1808.8 kg (3,988 lb) UO.
d) Free liquids shall not exceed 1% of the CCV cavity volume.
e) CANDU fuel baskets of irradiated hardware materials may not be shipped in the same package as other irradiated CANDU fuel waste contents.
f) Maximum weight of contents, including IFW in a secondary container, internal structures (e.g.,
SIA, etc.) and dunnage or shoring shall not exceed 7,300 lbs (3,311 kg).
g) CANDU fuel baskets of irradiated hardware materials are limited to 2.5 kg (5.5 lbs) of Inconel, 200 Kg (441 lbs) of stainless steel, and unlimited Zircaloy per package.
Table 3 - IFW FEM Limits LEU Waste Criticality Configuration Description Config.
ID(1)
Weight %
Special Reflector(2)
Enrichment Limit (wt% U-235)
Particle Size Restriction (cm)
Uranium Mass Limit (lb)
FEM-1 1
0.96 wt%
0.1 and/or 8.0 FEM-2 1
0.80 wt%
N/A 5,000 (1)
IFW contents must be non-machine compacted. Materials with hydrogen density up to that of water (0.1117 g/cm3) are unlimited, but materials with hydrogen density greater than water are limited to the hydrogen density of polyethylene (0.1336 g/cm3) and may not exceed 15% of the total contents by volume.
(2) Special reflector materials are defined as beryllium, beryllium oxide, carbon (graphite), heavy water, magnesium oxide, and depleted uranium. The weight% of the special reflector materials is calculated as the mass of all special reflector materials present divided by the total mass of all waste material contents inside the secondary container.
(iv) Plutonium contents in quantities greater than 0.74 TBq (20 Ci) must be in solid form.
5.(c)
Criticality Safety Index (CSI) 0.0 6.
In addition to the requirements of 10 CFR 71 Subpart G:
(a)
The package must be loaded and prepared for shipment in accordance with the Package Operations in Section 7 of the application.
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 7
OF 8
(b)
The package must be tested and maintained in accordance with the Acceptance Tests and Maintenance Program in Section 8 of the application.
7.
Shoring must be placed between loose fitting contents and the CCV cavity to prevent excessive movement during transport. The shoring material shall not react negatively with the packaging materials or contents and should have a melting temperature above 300°F to ensure shoring maintains its geometry under routine and normal conditions of transport.
- 8.
All radioactive contents shall be packaged in secondary container(s) (e.g., drums, liners, specialty bags, etc.). TRU waste contents may be shipped on a nonexclusive use conveyance or under exclusive use controls. IFW shall be shipped under exclusive use.
9.
Packaging preparations for shipment:
(a)
Each package prepared for shipment may only contain one form of non-compliant TRU waste contents, alone or in combination with compliant TRU waste (Content 1-1, Content 1-2A, Content 1-2B, Content 1-2C, Contents 1-1 and 1-2A, Contents 1-1 and 1-2B, and Contents 1-1 and 1-2C) and shall otherwise satisfy the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC).
(b)
The package shipment for TRU waste shall ensure that hydrogen and other flammable gases make up less than 5 percent by volume of the total gas inventory, or lower if warranted by the flammable gas, within any confined volume, for shipment within the allowable shipping time frame, as determined by Attachment 7.5-3 of the application.
(c)
Maximum decay heat for shipment of TRU waste is 200 watts. For TRU waste, with a total decay heat exceeding 50 watts, the CCV cavity shall be filled with helium gas per Table 3.1-1 of the application.
(d)
Maximum decay heat for shipment of IFW is 1,500 watts. For any heat load (0-1,500 watts),
the CCV cavity shall be filled with helium gas per Table 3.1-1 of the application.
10.
If not transported by private carriers, with individual monitoring of personnel in conformance with 10 CFR 20.1502, the minimum distance to occupied spaces shall be 20 ft from the centerline of the nearest package.
- 11.
Transport by air is not authorized.
12.
The package authorized by this certificate is hereby approved for use under the general license provisions of 10 CFR 71.17.
13.
Expiration date: August 31, 2029.
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 PAGE 9392 0
71-9392 USA/9392/B(U)F-96 8
OF 8
REFERENCES NAC International, Inc., Application - OPTIMUS-H OPTImal Modular Universal Shipping Cask Safety Analysis Report - Revision No. 0, dated April 2024.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Yoira Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Date: August 5, 2024 Signed by Diaz-Sanabria, Yoira on 08/05/24