ML24324A065
| ML24324A065 | |
| Person / Time | |
|---|---|
| Site: | 07200009 |
| Issue date: | 11/14/2024 |
| From: | US Dept of Energy, Idaho Operations Office |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML24324A062 | List: |
| References | |
| CLN250095 | |
| Download: ML24324A065 (1) | |
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.
Department of Energy
- 3.
Renewed SNM-2504 License No.
Amendment No.
11
- 2.
850 Energy Drive Idaho Falls, Idaho 83401-1563
- 4.
Expiration Date November 30, 2031
- 5.
Docket or 72-09 Reference No.
- 6.
Byproduct, Source, and/or
- 7. Chemical or Physical Form
- 8.
Maximum Amount That Licensee May Special Nuclear Material Possess at Any One Time Under This License A. Fuel elements from Fort St.
A. Irradiated TRISO coated (Th, A.
1036 Kg uranium and 14,540 Kg Vrain (FSV) Nuclear Generating U)C2 fuel particles inside thorium initially contained in Station using thorium and graphite fuel elements 1,482 irradiated HTGR fuel uranium enriched to not greater elements than 93.15% in the U-235 isotope B. Transuranium elements, source B. Irradiated fuel elements, B.
Quantity contained in 1,482 material, byproduct material, contaminated ISFSI irradiated HTGR fuel elements, and associated radioactive equipment (e.g., fuel storage 270 contaminated fuel storage material related to receipt, containers, container handling containers, 1 contaminated storage, and transfer of fuel machine, standby storage container handling machine, 3 elements wells), depleted uranium contaminated storage wells, 3 shielding materials, and low-depleted uranium shielding level radioactive waste related components of transfer casks, to receipt, storage, and and low-level radioactive waste transfer of fuel elements related to receipt, storage, and transfer of fuel elements C. Byproduct and special nuclear C. As calibration discs or sealed C. Radioactive sources used for material related to receipt, sources, without restriction to sample analysis and instrument storage, and transfer of fuel chemical or physical form, for calibration elements sample analysis and instrument calibration
NRC FORM 588A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2
OF 3
PAGES (10-2000)
Renewed License No.
I Amendment No.
10 CFR 72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2504 11 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.
SUPPLEMENTARY SHEET 72-9
- 9.
Authorized Use: For use in accordance with statements, representations, and the conditions of the Technical Specifications and Safety Analysis Report (SAR) dated December 17, 1996, and supplements dated February 4, February 5, February 18, March 12, March 24, April 2, April 16, April 29, December 10, and December 18, 1997; and February 6, April 7, July 2, July 20, August 24, October 2, October 16 (two letters), November 16, November 19 (two letters), December 1, December 9, and December 24, 1998; and April 27, May 5, May 12, May 13, October 19, and November 24, 1999; January 18, 2000; May 24, 2001; November 10, 2009; June 9, July 30, August 13, September 7, November 9, November 30, and December 23, 201 O; July 18, 2011; June 13, 2013; and September 8, 2016; and as further supplemented and amended in accordance with 10 CFR 72. 70 and 10 CFR 72.48.
The material identified in 6.A, 6.B, 7.A, and 7.B above must be related to spent fuel storage and is authorized for receipt, possession, storage, and transfer. Material identified in 6.C and 7.C above shall be related to spent fuel storage, and is authorized for receipt, possession, storage, transfer, and use.
- 10.
Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the FSV Independent Spent Fuel Storage Installation (ISFSI) located in Platteville, Colorado, as described in the Safety Analysis Report.
- 11.
The Technical Specifications contained in Appendix A attached hereto are incorporated into the license.
The licensee shall operate the installation in accordance with the Technical Specifications in Appendix A.
- 12.
The licensee shall follow the physical protection plan entitled "DOE-ID Independent Spent Fuel Storage Installation Security Plan," dated October 9, 1998, with subsequent modifications dated December 1, 1998, April 27, 1999, May 24, 2001, and June 30, 2014 and as it may be further amended under the provisions of 10 CFR 72.44( e) and 72.186(b ).
- 13.
The repackaging of fuel assemblies is not authorized.
- 14.
For the duration of the license, the licensee shall inform the Director, Office of Nuclear Material Safety and Safeguards, at least 90 days in advance, of the planned replacement of the entity contracted by DOE-ID to perform the management and operation (the M&O contractor) of the FSV ISFSI.
Within 180 days after the replacement of the M&O contractor, the licensee shall assess the performance of the M&O contractor and provide a statement to the NRC verifying that the replacement of the M&O contractor has had no effect on the execution of licensed responsibilities for the FSV ISFSI.
- 15.
DOE shall be responsible for requesting necessary funds from Congress to ensure compliance of FSV operations and decommissioning under this license. DOE will notify the NRC, in writing, of any anticipated or forecasted budget shortfalls, as soon as they are known, along with a plan detailing the specific measures that will be taken by DOE to obtain the required funding and prevent adverse impacts on ISFSI operations.
and XXX XX, 2024 Department of Energy (DOE) Idaho Cleanup Project (ICP)
NRC FORM 588A U.S. NUCLEAR REGULATORY COMMISSION PAGE 3
OF 3
PAGES (10-2000)
Renewed License No.
I Amendment No.
10CFR72 LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2504 11 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No.
SUPPLEMENTARY SHEET 72-9
- 16.
This license is effective as of the date of issuance shown below.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION Date of Issuance: 6/6/17
Attachment:
Appendix A
~!1?1~
~O'hn McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555
APPENDIX A TECHNICAL SPECIFICATIONS FOR THE FORT ST. VRAIN INDEPENDENT SPENT FUEL STORAGE INSTALLATION SNM-2504
3.3 Fuel Storage Container 3.3.1 Seal Leak Rate Fuel Storage Container 3.3 LCO 3.3.1 The FSC or storage well seal leakage rate shall not exceed 1 x 10-3 standard cc/sec.
APPLICABILITY:
During STORAGE OPERATIONS ACTION CONDITION REQUIRED ACTION COMPLETION TIME A. If seal leak rate limit is exceeded for A.1.1 Restore top seal integrity.
7 days one or two FSCs (or storage wells)
OR A.1.2.1 Transfer the FSC to a storage well 7 days AND A.1.2.2 Verify integrity of storage well.
7 days AND A.2 Perform leak test on two additional FSCs from each vault 30 days AND A.3 Submit report to NRC describing condition, results of engineering evaluations and actions being 90 days taken.
B. If seal leak rate limit is exceeded for B.1 Notify NRC Operations Center Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of three or more FSCs or storage wells entry into CONDITION B
Fort St. Vrain ISFSI 3.3-1 21 21 21 45
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.3.1.1 Leak test one FSC from each vault.
Fort St. Vrain ISFSI 3.3-2 Fuel Storage Container 3.3 FREQUENCY NOTE: SR 3.0.2 is not applicable 5 years.
5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility Responsibility 5.1 5.1.1 The Deputy Manager for Idaho Cleanup Project (ICP), Office of Environmental Management (DOE-ID), is responsible for the operation of the FSV ISFSI and for compliance with all applicable regulatory requirements and license conditions.
5.1.2 The Facility Director is responsible for overall ISFSI operation. The Facility Director and any alternates shall be designated in writing.
5.1.3 Although not in residence at the FSV ISFSI, the Facility Director shall maintain routine electronic and verbal communication with the facility staff.
5.1.4 The Facility Director shall be present during significant operational or maintenance evolutions, emergency exercises, and announced NRC inspections. During prolonged evolutions, the Facility Director shall be present during initial activities and at least monthly thereafter.
5.1.5 The Facility Director shall visit the FSV ISFSI at least twice a year for the purpose of verification or audit of FSV ISFSI compliance with regulatory requirements and licensing basis commitments, to communicate and interface in person with facility staff and to appraise DOE-ID management of FSV ISFSI status based on observations.
5.1.6 The Facility Director shall review and concur with all FSV ISFSI evaluations prepared pursuant to 10 CFR 72.44(e), 10 CFR 72.44(f), 10 CFR 72.48, TS 5.5.1.b, TS 5.5.2.3, and TS 5.5.3.2.
Fort St. Vrain ISFSI 5.1-1 the DOE ICP
5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Organization 5.2 Onsite and offsite organizations shall be established for facility operation and support services, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the ISFSI.
- 1.
Lines of authority, responsibility, and communication shall be defined and established throughout the organization, from senior management levels to all operational and support positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions tor key positions, or in equivalent forms of documentation. These requirements, including the facility-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Safety Analysis Report;
- 2.
The responsible Department executive, as delegated by the Energy Secretary, shall have Department responsibility for overall facility nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the facility to ensure nuclear safety; and
- 3.
The individuals who perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
- 4.
The Safety Review Committee shall provide oversight of FSV ISFSI operation by performing reviews of:
- a.
Performance indicators (audit findings, reportable events and conditions, Technical Specification violations);
- b.
Evaluations performed pursuant to 10 CFR 72.44(e), 10 CFR44(t), 10 CFR 72.48, TS 3.3.1 (A)(3), TS 5.5.1.b, TS 5.5.2.3, and TS 5.5.3.2;
- c.
Proposed license amendments;
- d.
Selected activities of the ALARA committee and the staff level document review committee;
- e.
Preparation for major operations (such as detueling) for potential safety hazards; and
- t.
Special reviews at the direction of the Facility Director.
Fort St. Vrain ISFSI 5.2-1 Manager for the ICP designated
Organization 5.2 The Safety Review Committee members and chair shall be appointed in writing. The Facility Director shall be informed of all appointments to the Safety Review Committee The Safety Review Committee membership shall represent the following disciplines:
Radiological Safety, Criticality Safety, Nuclear Facility Operation, Nuclear Quality Assurance, and Engineering.
A quorum for a Safety Review Committee meeting shall include a minimum of three committee members including members representing the technical disciplines appropriate for matters under consideration. The Facility Director, acting in an ex-officio capacity, shall be present to constitute a quorum.
The Safety Review Committee shall meet at least once every twelve months and at least once not more than three months prior to the start of defueling operations.
Fort St. Vrain ISFSI 5.2-2
Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained for the following activities:
5.4.2
- a. Administrative controls;
- b.
Routine ISFSI operations;
- c.
Emergency response;
- d.
Design Control;
- e.
Facility changes, tests and experiments;
- f.
Control of Surveillances and tests;
- g. Control of special processes;
- h.
Maintenance;
- i.
Health physics, including ALARA practices;
- j. Spent fuel management;
- k. Quality assurance inspection and audits; I.
- m.
Records management
- n.
Reporting; and
- o. All programs specified in Specification 5.5 Implementing procedures may be common with the Idaho National Engineering and Environmental Laboratory procedures provided that all ISFSI requirements are met.
The FSV Facility Director will ensure performance, and review the results of DOE-performed surveillances, assessments, or audits of changes to procedures described above. The DOE-ID QA manager is responsible to ensure audits of the Quality Assurance Program. Each area will be reviewed at least biennially.
Fort St. Vrain ISFSI 5.4-1 Idaho Operations Office
Programs 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs The following programs shall be established, implemented, and maintained.
5.5.1 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a.
Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b.
Changes may be made to Bases without prior NRC approval provided the changes do not involve either of the following:
- c.
- d.
- 1.
A change in the TS incorporated in the license; or
- 2.
A change to the SAR or Bases which requires a license amendment according to the criteria of 10 CFR 72.48.
The Bases Control Program shall contain provisions to ensure the Bases are maintained consistent with the SAR.
Proposed changes which don't meet the criteria of 5.5.1.b above shall be reviewed and approved by the NRC before implementation. Changes to the Bases implemented which do not require prior NRC approval shall be provided to the NRC on a frequency consistent with 1 O CFR 72.48(b)(2).
Fort St. Vrain ISFSI 5.5-1 (d)
5.5.2 Essential Program Control Program Programs 5.5
- 1.
This program provides a means for processing changes to the following essential programs.
- a. Quality Assurance Program
- b.
Radiological Environmental Monitoring Program
- c. Training Program
- 2.
Changes to essential programs shall be made under appropriate administrative controls and reviews.
- 3.
The licensee may make changes to essential programs without prior NRC approval provided the changes do not involve either of the following:
- a.
A change in the Technical Specification incorporated in the license; or
- b.
A decrease in effectiveness.
- 4.
The Essential Programs Change Control program shall contain provisions to ensure essential programs are maintained consistent with the regulations.
- 5.
Proposed changes to essential programs which don=t meet the criteria of 5.5.2.3 above shall be reviewed and approved by the NRC before implementation.
- 6.
Changes to essential program implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 72.70(b).
- 7.
DOE will review and approve all submittals to the NRC made pursuant to TS 5.5.2.5 and TS 5.5.2.6.
Fort St. Vrain ISFSI 5.5-2 don't 10 CFR 72.70(c)(6)
5.0 ADMINISTRATIVE CONTROLS 5.6 REPORTING REQUIREMENTS Reporting Requirements 5.6 5.6.1 All reports required by 10 CFR Part 72 tor the FSV ISFSI and all reports required by the FSV ISFSI license and Technical Specifications, shall be submitted by the Deputy Manager for ICP or the Facility Director.
5.6.2 All instances of noncompliance with the Limiting Conditions tor Operation, SuNeillance Requirements, Design Features or Administrative Controls contained within these Technical Specifications shall be reported in writing to the NRC Document Control Desk within 30 days of discovery of the non-compliance. Copies shall be provided to the Director, Office of Nuclear Material Safety and Safeguards and the Regional Administrator, NRC Region IV.
Fort St Vrain ISFSI 5.6-1 the