ML23311A383
| ML23311A383 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 12/11/2023 |
| From: | Lav S NRC/NMSS/DFM/FFLB |
| To: | Global Nuclear Fuel |
| Shared Package | |
| ML23311A379:ML23311A379 | List: |
| References | |
| EPID L-2022-LLA-0065 | |
| Download: ML23311A383 (5) | |
Text
Page 1 of 5 NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, Code of Federal Regulations, Chapter I, Parts 30, 31, 32, 33, 34, 35, 36, 39, 40, and 70, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to all applicable rules, regulations, and orders of the U.S. Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
Licensee
- 1. Global Nuclear Fuel - Americas, LLC 3. License Number: SNM-1097
. Amendment 18
- 2. P.O. Box 780
- 4. Expiration Date: May 19, 2049 Wilmington, North Carolina 28402
- 5. Docket No. 70-1113
- 6. Byproduct Source, and/or 7. Chemical and/or Physical 8. Maximum Amount That Licensee Special Nuclear Material Form May Possess at Any One Time Under This License A. Uranium enriched to A. Uranium - any chemical A.
8 percent U-235 or physical form B. Uranium enriched in B. Any form or enrichment B.
U-235 for use in instruments, sources, and standards C. Uranium enriched from C. Uranium compounds for use C.
>8% to <20% U-235 in laboratory and process development D. Uranium-233 D. Uranium compounds D.
E. Plutonium E. Sealed neutron sources E.
F. Plutonium F. Analytical samples F.
G. Plutonium G. In nuclear fuel rods G.
Enclosure 3
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 5 License No. SNM-1097 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket No. 70-1113 Amendment 18
- 9. Authorized place of use: The licensee's existing facilities at Wilmington, North Carolina.
- 10. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions.
Both sections are part of the license, and the licensee is subject to compliance with all listed conditions in each section.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Signed by Lav, Samantha December 11, 2023 on 12/11/23 Date: _________________ By: ____ ___________________
Samantha C. Lav, Chief Fuel Facility Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 5 License No. SNM-1097 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket No. 70-1113 Amendment 18 SAFETY CONDITIONS S-1 Authorized use: For use in accordance with statements, representations, and conditions of application dated and supplements dated April 2, 2007; June 29, 2007; February 14, 2008; November 25, 2008; January 8, 2009; February 24, 2009; July 12, 2010; July 28, 2010; August 13, 2010; December 2, 2010; June 15, 2011, November 29, 2011, May 9, 2012, August 16, 2012, September 27, 2013; November 14, 2013; January 27, 2014; March 27, 2014; October 8, 2015; December 15, 2016; January 12, 2016; October 27, 2016; May 10, 2018; August 2, 2018; June 23, 2020; July 28, 2020, August 20, 2021, September 17, 2021, and June 24, 2022 (ML22175A070).
S-2 The licensee is hereby granted exemptions and special authorizations in Section 1.3 of the application.
S-3 The licensee shall maintain and execute the response measures in Revision 23 of the Radiological Contingency and Emergency Plan, dated March 26, 2015. This Plan may be further revised by the licensee consistent with Title 10 of the Code of Federal Regulations (10 CFR) 70.32(i).
S-4 In a letter dated September 22, 2015, GNF-A provided a response to GL 2015-01, describing 1) A description of the work that has been completed to date, including a general description of the type of work, what facilities are affected, and the status of these actions; 2) A description of the work that remains to be completed and what facilities are involved; 3) An acceptable explanation for not being able to submit a 90 day response to the GL; and 4) A formal response will be provided by the requested date of January 29, 2016, addressing items (1)a. through (1)d. of the GL and including a formal statement of compliance, signed under oath or affirmation as required.
S-5 Notwithstanding the requirements of 10 CFR 70.50(b)(1), the licensee is exempted from the requirement to report unplanned contamination events when the following conditions are met:
- 1. The event occurs in a restricted area in a building surrounded by a fenced area which is maintained inaccessible to the public by multiple access controls,
- 2. The area was controlled for contamination before the event occurred, the release of radioactive material is under control, and no contamination has spread outside the area,
- 3. Radiation safety personnel trained in contamination control are readily available,
- 4. Equipment and facilities that may be needed for contamination control are readily available, and
- 5. The otherwise reportable unplanned contamination event is documented in the licensees Corrective Action Program.
S-6. The licensee is granted an exemption from performing the biennial emergency plan exercise listed in 10 CFR 70.22(i)(3)(xii) in calendar year 2021 but must complete said exercise within 35 months of the previously evaluated emergency plan exercise which occurred on October 30, 2019. Following that evaluated exercise, the licensee will conduct biennial emergency plan exercises in odd number years.
S-7. The licensee shall control the entire fuel fabrication facility to safely process enrichments up to 8.0 wt.% U-235 and shall not segment the facility based on enrichment.
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 5 License No. SNM-1097 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket No. 70-1113 Amendment 18 S-8. Except for the special nuclear material authorized under Items 6.B, 6.C, 7.B, 7.C, 8.B, and 8.C of Materials License SNM-1097, GNF-A shall not receive, possess, handle, store, or process any special nuclear material in excess of 5.0 wt. % U-235 until the NRC completed an operational readiness review that verifies the facility will be operated safely and in accordance with the requirements of Material License SNM-1097. GNF-A will notify the NRC at least 120 days prior to the receipt of special nuclear material in excess of 5 wt. % U-235, other than special nuclear material authorized in Items 6.B and 6.C.
SAFEGUARDS CONDITIONS SECTION 1.0 - MATERIAL CONTROL AND ACCOUNTING SG-1.1 The licensee shall follow Chapters 1.0 through 10.0 of its Fundamental Nuclear Material Control Plan, which has been revised as indicated by Revision 19, dated August 7, 2015. Any further revision to this Plan shall be made only in accordance with, and pursuant to, either the provisions of 10 CFR 70.32(c) or 70.34.
SG-1.2 Notwithstanding the requirements of Sections 6.1 and 7.1 of the Plan identified in Condition SG-1.1, the licensee may (1) utilize a computer system independent of its Manufacturing Information and Control System to track the SNM contained in fuel bundles and loose fuel rods received from the Wurgassen plant in Germany; and (2) have up to 90 days for completing shipper-receiver differences determinations and evaluations associated with the initial shipment of fuel assemblies from the Wurgassen plant, and up to six calendar months for subsequent shipments of loose rods. Receipt measurements and item controls associated with these fuel assemblies and rods shall be in accordance with the commitments contained in the licensee's letter (from Dr. R. J. Reda to Mr. R. C.
Pierson), dated January 24, 1996.
SG-1.3 Notwithstanding the commitment in Section 7.1 of the Fundamental Nuclear Material Control Plan identified in Condition SG-1.1 to perform receipt verification measurements within 60 days, the licensee shall have until March 26, 2014, to fulfill the above-stated commitment relative to the shipments of uranium oxide powder identified in the attachment of the January 27, 2014, request letter.
SG-1.4 The licensee is authorized to exchange foreign obligations between similar materials as needed for routine licensed activities as described in letters dated June 30, 2022 (ML22259A198) and September 28, 2022 (ML22259A200).
SECTION 2.0 - PHYSICAL PROTECTION FOR SNM OF LOW STRATEGIC SIGNIFICANCE SG-2.1 The licensee shall follow the physical protection plan entitled, "Physical Security Plan," Revision 11, dated May 27, 2011 (letter dated June 2, 2011); and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e).
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 5 of 5 License No. SNM-1097 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket No. 70-1113 Amendment 18 SECTION 3.0 - INTERNATIONAL SAFEGUARDS SG-3.1 The licensee shall follow all sub codes within Codes 1 through 8 of the 19-page Transitional Facility Attachment No. 11A, dated January 24, 1996, to the US/IAEA Safeguards Agreement.
SG-3.2 Notwithstanding the requirements of 10 CFR 75.11(d) to submit facility data on forms supplied by the Commission (including IAEA Design Inventory Questionnaires [DIQs]), the licensee may submit the required data on internally generated forms that follow the IAEA's DIQ format.
SG-3.3 Notwithstanding the requirements of 10 CFR 75.35(a) to submit Material Balance Reports on DOE/NRC Form 742, Physical Inventory Listings on DOE/NRC Form 742C and Concise Notes on DOE/NRC Form 740, the licensee may use computer-generated facsimiles for the report forms specified in 10 CFR 75.35(a). The facsimiles must, as nearly as possible, approximate the referenced DOE/NRC forms in format and contain the information specified in NUREG/BR-0007, unless otherwise accepted by license condition.
SG-3.4 The licensee may disregard, for IAEA reporting purposes, the printed instructions contained in NUREG/BR-0007 relating to Blocks 6H and 6M of DOE/NRC Form 742-C, "Physical Inventory Listing (PIL)." The licensee may use Code "J" in Block 6H of the PIL regardless of nuclear material ownership and may use Code "M" in Block 6M of the PIL regardless of the basis of the measurement source data.