ML22242A018
| ML22242A018 | |
| Person / Time | |
|---|---|
| Site: | 07200001 |
| Issue date: | 11/22/2022 |
| From: | Yoira Diaz-Sanabria Storage and Transportation Licensing Branch |
| To: | GE Hitachi Nuclear Energy |
| K BANOVAC NMSS/DFM/STLB 3014157116 | |
| Shared Package | |
| ML22234A256 | List: |
| References | |
| Download: ML22242A018 (3) | |
Text
NRC FORM 588 U. S. NUCLEAR REGULATORY COMMISSION (10-2000) 10 CFR 72 PAGE 1 OF 3 PAGES
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE 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 1, Part 72, and in reliance on statements and representations heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, and possess the power reactor spent fuel and other radioactive materials associated with spent fuel storage designated below; to use such material for the purpose(s) and at the place(s) designated below; and 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 herein.
Licensee
- 1. GE-Hitachi Nuclear Energy Americas, LLC 3. License No. SNM-2500
Amendment No. 15
- 2. GE-Hitachi Nuclear Energy Americas, LLC 7555 East Collins Road 4. Expiration Date May 31, 2042 Morris, Illinois 60450 Renewed December 21, 2004
Subsequently Renewed on November 22, 2022
- 5. Docket or Reference No. 72-1
- 6. Byproduct, Source, and/or 7. Chemical or Physical Form 8. Maximum Amount That Licensee Special Nuclear Material May Possess at Any One Time Under This License
A. Fuel assemblies from reactors A. 1. As UO2 clad with A. 1. 37.5 MT using natural water for cooling zirconium or zirconium 2. 9.0 MT and enriched not greater than alloys. 3. 2.5x109 Ci 5 percent U-235. These fuels and associated materials 2. Liquid and Solid Waste related to storage and transfer Treatment Products of fuel assemblies will possibly contain:
- 1. Uranium 235
- 2. Plutonium
- 3. Fission and activation Products
B. Byproduct and special nuclear B. As solutions, calibration B. Quantities possessed be no material discs sealed source or in greater than that specified in other form specific in Table A Table A
- 9. Authorized Use: The material identified in 6.A and 7.A above is authorized for possession and storage at the Morris Operation, and transfer as described in NEDO-21326, the approved General Electric Morris Operation Consolidated Safety Analysis Report (CSAR), as supplemented and amended in accordance with 10 CFR 72.70 and 10 CFR 72.48. Material identified in 6.B, 7.B and 8.B is to be used for calibration and standardization purposes.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 3 PAGES (10-2000) 10 CFR 72 License No. Amendment No.
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2500 15 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-1 SUPPLEMENTARY SHEET
- 10. Authorized Place of Use: The licensed material is to be possessed, transferred, and stored at the Morris Operation located in Grundy County, Illinois, near Morris, Illinois. This site is described in Chapter 1 and 3 of the licensee's CSAR for the Morris Operation.
Table A. Authorized materials - instrument, calibration, and laboratory sources
Materials Chemical and/or Physical Form Quantity Radionuclides with atomic Solution or calibration disc Total Aggregate of 5 curies numbers ranging from 1 to 83 Cobalt-60 Sealed source 10 curies Cesium-137 Sealed source 10 curies Thorium-230 Any 1 millicurie Neptunium Any 20 grams Plutonium Any 50 grams Uranium-235 Any 250 grams (In uranium or any enrichment)
Americium-241 Any 200 µCi Americium-241 Sealed source 40 curies Plutonium-Beryllium Sealed source 2 curies Uranium-natural Any 15 kilograms
- 11. Pursuant to 10 CFR Part 40 the licensee is authorized to possess, store, and transfer a combined quantity of unirradiated natural and unirradiated depleted uranium not to exceed 42 tonnes. This limitation does not include uranium in stored fuel or uranium used in construction of shipping casks. Natural UO 3, UO2, UNH, and UF6, used during Midwest Fuel Recovery Plant (MFRP) testing may be stored in process vessels in the Canyon area or in the site warehouse.
- 12. No changes shall be made to the Radiological Emergency Plan for Morris Operation, NEDO-31995, which would decrease the effectiveness of the emergency plan without the prior approval of the Commission as evidenced by a license am endment. The licensee shall maintain implementing procedures for the Radiological Emergency Plan as necessary. The licensee shall maintain records of changes that are made to the plan without prior approval for a period of two years from the date of the change. Within six months of such change the licensee shall furnish the Director, Office of Nuclear Materials Safety and Safeguards, and the NRC Region III Office a report containing a description of each change.
- 13. The Technical Specifications contained in Appendix A attached hereto, as revised through the issuance of the subsequent renewed license, are incorporated into the license. The licensee shall operate the installation in accordance with the Technical Specifications in Appendix A. Appendix A contains Technical Specifications related to Environmental Protection to satisfy the requirements of 10 CFR 72.44(d)(2).
- 14. The licensee shall follow the physical protection plan entitled Physical Security Plan for Morris Operation, NEDS-14507, Revision D5, dated April 1995; and as it may be further amended under the provisions of 10 CFR 72.44(e) and 72.180. The requirements of 10 CFR Part 73, Appendix B for guard training and qualification are incorporated in Section 3.4, Security Force Training and Qualification, of the approved security plan. The requirements of 10 CFR Part 73, Appendix C, for contingency planning are addressed in Section 9.0 of the physical security plan.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION PAGE 3 OF 3 PAGES (10-2000) 10 CFR 72 License No. Amendment No.
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2500 15 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-1 SUPPLEMENTARY SHEET
- 15. Within 90 days after issuance of the subsequent renewed license, the licensee shall submit an updated CSAR to the NRC, in accordance with 10 CFR 72.4, and continue to update the CSAR pursuant to the requirements in 10 CFR 72.70(b) and (c). The updated CSAR shall reflect the Draft Revision 15A to the CSAR, as documented in Attachment 3 of the Ma y 12, 2022, submittal (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22132A072). The licensee may make changes to the updated CSAR, consistent with 10 CFR 72.48(c).
- 16. Within one year after issuance of the subsequent renewed license, the licensee shall create, update, or revise procedure(s) for implementing the activiti es in the aging management programs described in the updated CSAR. The licensee shall maintain the procedure(s) throughout the term of this license.
- 17. This license is effective as of the date of issuance shown below.
FOR THE NUCLEAR REGULATORY COMMISSION
Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555
Date of Issuance: May 4, 1982
Renewed License: Dated December 21, 2004
Subsequent Renewed License: Dated November 22, 2022
Attachment:
Technical Specifications