ML25050A046

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NAC International, Inc., SAR Replacement Pages NAC-OPTIMUS-L SAR, Supplement 01, Revision 25B
ML25050A046
Person / Time
Site: OPTIMUS-L
Issue date: 02/19/2025
From:
NAC International
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML25050A044 List:
References
ED20250027, EPID L-2024-LLA-0019
Download: ML25050A046 (1)


Text

Enclosure 1 SAR Replacement Pages NAC-OPTIMUS-L SAR, Supplement 01, Revision 25B Docket No 71-9390 NAC International February 2025 to ED20250027 Page 1 of 1

OPTIMUS-L Package SAR February 2025 Docket No. 71-9390 Revision 25B NAC International 1.2-12 Type and Form of IFW Waste Material:

1. LEU fuel.
2. Activated metal structural components (e.g., cladding, liners, baskets, etc.).

Maximum Quantity of IFW Contents per Package:

1. Greater than Type A quantities of radioactive material in the form of LEU fuel.
2. Greater than Type A quantities of radioactive material in the form of activated metal structural components (e.g., cladding, liners, baskets, etc.).
3. That quantity of any radioactive material not generating spontaneously more than 100 thermal watts of radioactive decay heat.
4. IFW not exceeding the Fissile Equivalent Mass (FEM) limits from Table 1.2-2 for the specified criticality configuration limits.
5. IFW contents shall comply with regulatory dose rates, as demonstrated in accordance with Chapter 7, Attachment 7.5-1. Note: Maximum activity limits for key individual gamma-emitting isotopes (e.g., Co-60, Cs-137 and Ba-137m) and neutron-emitting isotopes (e.g., Cf-252 and Cm-244) are provided in Table 1.2-3.

Loading Restrictions:

1. IFW contents shall be in secondary containers (e.g., drums or boxes).
2. IFW contents with a total decay heat exceeding 50 watts shall be inerted with helium gas.
3. Free liquids shall not exceed 1% of the CCV cavity volume.
4. Maximum weight of the CCV contents, including IFW waste, secondary containers, and internal structures (e.g., CCV bottom support plate, SIA, etc.) and dunnage or shoring shall not exceed 3,500 pounds (1,587 kg).

1.2.2.3 TRISO Compacts configured with the GEO basket assembly subject to the following requirements and restrictions:

Type and Form of TRISO Compacts:

1. TRISO compacts are solid right circular
2. TRISO compacts shall be unirradiated.

NAC PROPRIETARY INFORMATION REMOVED

OPTIMUS-L Package SAR February 2025 Docket No. 71-9390 Revision 25B NAC International 1.2-13 Maximum Quantity of TRISO Compacts per Package:

1. Maximum total weight 581 pounds (263 kg).
2. Maximum enrichment 20% U-235.
3. Total mean uranium loading 68 kgU
4. Maximum mean matrix density 1.8 g/cc.

For TRISO Compacts, the fuel may originate from enriched slightly contaminated uranium with trace quantity limits. The following table shows the maximum concentrations of the content, including contaminants. U-238 is not listed as it is assumed to be the remainder of the uranium concentration.

Isotope Maximum content U-232 2.6 x 10-9 g/gU U-234 1.00 x 10-2 g/gU U-235 2.00 x 10-1 g/gU U-236 7.72 x 10-2 g/gU U-238 Balance of Uranium Np-237 3.85 x 10-6 g/gU Pu-238 1.56 x 10-10 g/gU Pu-239/Pu-240 4.29 x 10-8 g/gU Fission Products 0.25 mCi/gU Loading Restrictions:

1. TRISO compacts shall be shipped in the GEO basket assembly.
2. TRISO compacts shall not protrude above the top end of the GEO basket fuel tubes.
3. TRISO compact shall be shipped dry (i.e., no free liquids).
4. Shoring or dunnage (e.g., spacers) may be placed between contents and the CCV cavity, baskets and/or tubes to prevent excessive movement during transport. The material shall not react negatively with the packaging materials or contents and should have a auto-ignition temperature above 300°F to ensure the materials maintain their geometry under routine and normal conditions of transport.
5. Non-metallic adhesive-backed seals or labels may be included as contents.
6. The non-metallic components must have an auto-ignition temperature of 300°F or higher and must be evaluated for gas generation in accordance with Attachment 7.5-3 prior to shipment.