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{{#Wiki_filter:}} | {{#Wiki_filter:OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION Page 1 of 5 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 Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. Licensee Framatome Inc. License Number: SNM-1227, Amendment 10 2101 Horn Rapids Road Expiration Date: April 24, 2049 Docket Number: 70-1257 Richland, WA 99354-0130 Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION 1. Byproduct, Source, and/or Special Nuclear Material A. Uranium enriched in U-235 to any enrichment B. Uranium enriched up to 5.00 wt. % U-235 2. Chemical and/or Physical Form A. Any B. Uranium Compounds 3. Maximum Amount that Licensee May Possess At Any One Time A. 350 g U-235 B. See Sensitive Conditions 4. Authorized Place of Use: The licensee's existing facilities in Richland, Washington. This license contains SECURITY RELATED INFORMATION. When separated from the Sensitive Conditions on Page 5, this license is DECONTROLLED. | ||
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 5. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. These 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 Date: April 26, 2018 _______________\RA\____________________ Robert Johnson, Chief Fuel Manufacturing Branch Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Material Safety and Safeguards NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 SAFETY CONDITIONS S-1 Authorized use: For use in accordance with the statements, representations, and conditions in the LA dated October 24, 2006, and supplements dated December 13, 2006 (License Application and Request for Additional Information Responses); December 10, 2008; E-mail from R.E. Link titled "Compliance Plan" dated March 5, 2009; June 12, 2008, August 22, 2008, June 5, 2009, July 13, 2009, November 11, 2009, December 4, 2009, February 4, 2010, E-mail and Attachment Submitted by C.D. Manning on April 16, 2010, April 28, 2010; and E-mail and Attachment Submitted by C.D. Manning on July 1, 2010. Letters and LA dated February 14, 2011; October 8, 2010; August 24, 2011; February 13, 2012; April 19, 2013; May 7, 2014; September 23, 2014 (supplemented on December 10, 2014); April 20, 2015; and January 19, 2018. S-2 The licensee shall maintain and execute the response measures in its Emergency Plan titled "Emergency Preparedness-Part I, Emergency Plan (E08-01-1.0),"Version 10.0, dated February 27, 2014, or as further revised by the licensee consistent with 10 CFR 70.32(i). S-3 [deleted] S-4 [deleted] S-5. [deleted] S-6 Pressure vessels used in the supercritical CO2 extraction process that have an outside diameter of more than 6 inches shall be constructed, certified, and maintained in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section VIII, Division 1, without exception. SAFEGUARDS CONDITIONS Section 1.0 - Material Control & Accounting SG-1.1 The licensee shall follow Sections 0.0 through 8.0 of the Fundamental Nuclear Material Control Plan, Version 7.1, and as the plan may be further revised in accordance with, and pursuant to, the provisions of 10 CFR 70.32(c). SG-1.2 [deleted] SG-1.3 [deleted] SG-1.4 Operations involving special nuclear material (SNM) which are not described in the Plan identified in Condition SG-1.1 shall not be initiated until an appropriate safeguards plan has been NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 approved by the appropriate safeguards licensing authority of the U.S. Nuclear Regulatory Commission. Section 2.0 - Physical Protection for SNM of Low Strategic Significance SG-2.1 The licensee shall follow the Physical Protection Plan entitled "Physical Protection Plan for SNM for Low Strategic Significance, Revision 8.0 for AREVA Inc.'s (AREVA) Richland, Washington Fuel Fabrication Facility," dated June 28, 2012; and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e). SG-2.2 [deleted] Section 3.0 - International Safeguards SG-3.1 The licensee shall follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment No. 1a dated May 1, 1986, to the US/ International Atomic Energy Agency 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's Design Inventory Questionnaires), the licensee may submit required data in the AREVA's license paper format. | |||
OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION Page 1 of 5 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 Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. Licensee Framatome Inc. License Number: SNM-1227, Amendment 10 2101 Horn Rapids Road Expiration Date: April 24, 2049 Docket Number: 70-1257 Richland, WA 99354-0130 Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION 1. Byproduct, Source, and/or Special Nuclear Material A. Uranium enriched in U-235 to any enrichment B. Uranium enriched up to 5.00 wt. % U-235 2. Chemical and/or Physical Form A. Any B. Uranium Compounds 3. Maximum Amount that Licensee May Possess At Any One Time A. 350 g U-235 B. See Sensitive Conditions 4. Authorized Place of Use: The licensee's existing facilities in Richland, Washington. This license contains SECURITY RELATED INFORMATION. When separated from the Sensitive Conditions on Page 5, this license is DECONTROLLED. | |||
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 5. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. These 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 Date: April 26, 2018 _______________\RA\____________________ Robert Johnson, Chief Fuel Manufacturing Branch Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Material Safety and Safeguards NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 SAFETY CONDITIONS S-1 Authorized use: For use in accordance with the statements, representations, and conditions in the LA dated October 24, 2006, and supplements dated December 13, 2006 (License Application and Request for Additional Information Responses); December 10, 2008; E-mail from R.E. Link titled "Compliance Plan" dated March 5, 2009; June 12, 2008, August 22, 2008, June 5, 2009, July 13, 2009, November 11, 2009, December 4, 2009, February 4, 2010, E-mail and Attachment Submitted by C.D. Manning on April 16, 2010, April 28, 2010; and E-mail and Attachment Submitted by C.D. Manning on July 1, 2010. Letters and LA dated February 14, 2011; October 8, 2010; August 24, 2011; February 13, 2012; April 19, 2013; May 7, 2014; September 23, 2014 (supplemented on December 10, 2014); April 20, 2015; and January 19, 2018. S-2 The licensee shall maintain and execute the response measures in its Emergency Plan titled "Emergency Preparedness-Part I, Emergency Plan (E08-01-1.0),"Version 10.0, dated February 27, 2014, or as further revised by the licensee consistent with 10 CFR 70.32(i). S-3 [deleted] S-4 [deleted] S-5. [deleted] S-6 Pressure vessels used in the supercritical CO2 extraction process that have an outside diameter of more than 6 inches shall be constructed, certified, and maintained in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section VIII, Division 1, without exception. SAFEGUARDS CONDITIONS Section 1.0 - Material Control & Accounting SG-1.1 The licensee shall follow Sections 0.0 through 8.0 of the Fundamental Nuclear Material Control Plan, Version 7.1, and as the plan may be further revised in accordance with, and pursuant to, the provisions of 10 CFR 70.32(c). SG-1.2 [deleted] SG-1.3 [deleted] SG-1.4 Operations involving special nuclear material (SNM) which are not described in the Plan identified in Condition SG-1.1 shall not be initiated until an appropriate safeguards plan has been NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 approved by the appropriate safeguards licensing authority of the U.S. Nuclear Regulatory Commission. Section 2.0 - Physical Protection for SNM of Low Strategic Significance SG-2.1 The licensee shall follow the Physical Protection Plan entitled "Physical Protection Plan for SNM for Low Strategic Significance, Revision 8.0 for AREVA Inc.'s (AREVA) Richland, Washington Fuel Fabrication Facility," dated June 28, 2012; and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e). SG-2.2 [deleted] Section 3.0 - International Safeguards SG-3.1 The licensee shall follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment No. 1a dated May 1, 1986, to the US/ International Atomic Energy Agency 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's Design Inventory Questionnaires), the licensee may submit required data in the AREVA's license paper format.}} | |||
Revision as of 22:32, 17 May 2018
| ML18106A128 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 04/26/2018 |
| From: | Johnson R K Fuel Manufacturing Branch |
| To: | Tate T J Framatome |
| Ramsey K M | |
| Shared Package | |
| ML18106A085 | List: |
| References | |
| EPID L-2018-LLA-0009 | |
| Download: ML18106A128 (4) | |
Text
OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION Page 1 of 5 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 Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. Licensee Framatome Inc. License Number: SNM-1227, Amendment 10 2101 Horn Rapids Road Expiration Date: April 24, 2049 Docket Number: 70-1257 Richland, WA 99354-0130 Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION 1. Byproduct, Source, and/or Special Nuclear Material A. Uranium enriched in U-235 to any enrichment B. Uranium enriched up to 5.00 wt. % U-235 2. Chemical and/or Physical Form A. Any B. Uranium Compounds 3. Maximum Amount that Licensee May Possess At Any One Time A. 350 g U-235 B. See Sensitive Conditions 4. Authorized Place of Use: The licensee's existing facilities in Richland, Washington. This license contains SECURITY RELATED INFORMATION. When separated from the Sensitive Conditions on Page 5, this license is DECONTROLLED.
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 5. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. These 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 Date: April 26, 2018 _______________\RA\____________________ Robert Johnson, Chief Fuel Manufacturing Branch Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Material Safety and Safeguards NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 SAFETY CONDITIONS S-1 Authorized use: For use in accordance with the statements, representations, and conditions in the LA dated October 24, 2006, and supplements dated December 13, 2006 (License Application and Request for Additional Information Responses); December 10, 2008; E-mail from R.E. Link titled "Compliance Plan" dated March 5, 2009; June 12, 2008, August 22, 2008, June 5, 2009, July 13, 2009, November 11, 2009, December 4, 2009, February 4, 2010, E-mail and Attachment Submitted by C.D. Manning on April 16, 2010, April 28, 2010; and E-mail and Attachment Submitted by C.D. Manning on July 1, 2010. Letters and LA dated February 14, 2011; October 8, 2010; August 24, 2011; February 13, 2012; April 19, 2013; May 7, 2014; September 23, 2014 (supplemented on December 10, 2014); April 20, 2015; and January 19, 2018. S-2 The licensee shall maintain and execute the response measures in its Emergency Plan titled "Emergency Preparedness-Part I, Emergency Plan (E08-01-1.0),"Version 10.0, dated February 27, 2014, or as further revised by the licensee consistent with 10 CFR 70.32(i). S-3 [deleted] S-4 [deleted] S-5. [deleted] S-6 Pressure vessels used in the supercritical CO2 extraction process that have an outside diameter of more than 6 inches shall be constructed, certified, and maintained in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section VIII, Division 1, without exception. SAFEGUARDS CONDITIONS Section 1.0 - Material Control & Accounting SG-1.1 The licensee shall follow Sections 0.0 through 8.0 of the Fundamental Nuclear Material Control Plan, Version 7.1, and as the plan may be further revised in accordance with, and pursuant to, the provisions of 10 CFR 70.32(c). SG-1.2 [deleted] SG-1.3 [deleted] SG-1.4 Operations involving special nuclear material (SNM) which are not described in the Plan identified in Condition SG-1.1 shall not be initiated until an appropriate safeguards plan has been NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 approved by the appropriate safeguards licensing authority of the U.S. Nuclear Regulatory Commission. Section 2.0 - Physical Protection for SNM of Low Strategic Significance SG-2.1 The licensee shall follow the Physical Protection Plan entitled "Physical Protection Plan for SNM for Low Strategic Significance, Revision 8.0 for AREVA Inc.'s (AREVA) Richland, Washington Fuel Fabrication Facility," dated June 28, 2012; and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e). SG-2.2 [deleted] Section 3.0 - International Safeguards SG-3.1 The licensee shall follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment No. 1a dated May 1, 1986, to the US/ International Atomic Energy Agency 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's Design Inventory Questionnaires), the licensee may submit required data in the AREVA's license paper format.
OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION Page 1 of 5 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 Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below. Licensee Framatome Inc. License Number: SNM-1227, Amendment 10 2101 Horn Rapids Road Expiration Date: April 24, 2049 Docket Number: 70-1257 Richland, WA 99354-0130 Enclosure 1 OFFICIAL USE ONLY - SECURITY-RELATED INFORMATION 1. Byproduct, Source, and/or Special Nuclear Material A. Uranium enriched in U-235 to any enrichment B. Uranium enriched up to 5.00 wt. % U-235 2. Chemical and/or Physical Form A. Any B. Uranium Compounds 3. Maximum Amount that Licensee May Possess At Any One Time A. 350 g U-235 B. See Sensitive Conditions 4. Authorized Place of Use: The licensee's existing facilities in Richland, Washington. This license contains SECURITY RELATED INFORMATION. When separated from the Sensitive Conditions on Page 5, this license is DECONTROLLED.
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 5. This license shall be deemed to contain two sections: Safety Conditions and Safeguards Conditions. These 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 Date: April 26, 2018 _______________\RA\____________________ Robert Johnson, Chief Fuel Manufacturing Branch Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Material Safety and Safeguards NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 SAFETY CONDITIONS S-1 Authorized use: For use in accordance with the statements, representations, and conditions in the LA dated October 24, 2006, and supplements dated December 13, 2006 (License Application and Request for Additional Information Responses); December 10, 2008; E-mail from R.E. Link titled "Compliance Plan" dated March 5, 2009; June 12, 2008, August 22, 2008, June 5, 2009, July 13, 2009, November 11, 2009, December 4, 2009, February 4, 2010, E-mail and Attachment Submitted by C.D. Manning on April 16, 2010, April 28, 2010; and E-mail and Attachment Submitted by C.D. Manning on July 1, 2010. Letters and LA dated February 14, 2011; October 8, 2010; August 24, 2011; February 13, 2012; April 19, 2013; May 7, 2014; September 23, 2014 (supplemented on December 10, 2014); April 20, 2015; and January 19, 2018. S-2 The licensee shall maintain and execute the response measures in its Emergency Plan titled "Emergency Preparedness-Part I, Emergency Plan (E08-01-1.0),"Version 10.0, dated February 27, 2014, or as further revised by the licensee consistent with 10 CFR 70.32(i). S-3 [deleted] S-4 [deleted] S-5. [deleted] S-6 Pressure vessels used in the supercritical CO2 extraction process that have an outside diameter of more than 6 inches shall be constructed, certified, and maintained in accordance with the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section VIII, Division 1, without exception. SAFEGUARDS CONDITIONS Section 1.0 - Material Control & Accounting SG-1.1 The licensee shall follow Sections 0.0 through 8.0 of the Fundamental Nuclear Material Control Plan, Version 7.1, and as the plan may be further revised in accordance with, and pursuant to, the provisions of 10 CFR 70.32(c). SG-1.2 [deleted] SG-1.3 [deleted] SG-1.4 Operations involving special nuclear material (SNM) which are not described in the Plan identified in Condition SG-1.1 shall not be initiated until an appropriate safeguards plan has been NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 5 License Number: SNM-1227, Amendment 10 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number: 70-1257 approved by the appropriate safeguards licensing authority of the U.S. Nuclear Regulatory Commission. Section 2.0 - Physical Protection for SNM of Low Strategic Significance SG-2.1 The licensee shall follow the Physical Protection Plan entitled "Physical Protection Plan for SNM for Low Strategic Significance, Revision 8.0 for AREVA Inc.'s (AREVA) Richland, Washington Fuel Fabrication Facility," dated June 28, 2012; and as it may be further revised in accordance with the provisions of 10 CFR 70.32(e). SG-2.2 [deleted] Section 3.0 - International Safeguards SG-3.1 The licensee shall follow, as applicable, Codes 2 through 7 of Transitional Facility Attachment No. 1a dated May 1, 1986, to the US/ International Atomic Energy Agency 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's Design Inventory Questionnaires), the licensee may submit required data in the AREVA's license paper format.