ML24326A353
| ML24326A353 | |
| Person / Time | |
|---|---|
| Site: | Crane, 07200020  (SNM-2508) |
| Issue date: | 11/21/2024 |
| From: | Meraj Rahimi US Dept of Energy, Idaho Operations Office |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML24326A350 | List: |
| References | |
| CLN240550 | |
| Download: ML24326A353 (1) | |
Text
9.
Authorized Use: For use in accordance with the statements, representations, and conditions of the Technical Specifications and Final Safety Analysis Report (FSAR), as updated. The materials identified in 6.A, 6.B, and 7.A above are authorized for receipt, possession, storage, and transfer.
NRC FORM 588 (10-2000) 10 CFR 72 U. S. NUCLEAR REGULATORY COMMISSION 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.
License No.
SNM-2508 Amendment No.
5 2.
U. S. Department of Energy Idaho Operations Office 1955 Fremont Avenue Renewed on September 16, 2019 4.
Expiration Date March 19, 2039 5.
Docket or Reference No.
72-20 6.
Byproduct, Source, and/or Special Nuclear Material 7.
Chemical or Physical Form 8.
Maximum Amount That Licensee May Possess at Any One Time Under This License A. Radioactive material from the Three Mile Island Unit 2 (TMI-2) reactor core damaged by the March 28, 1979, reactor accident, including the remains of 177 Babcox and Wilcox 15x15 fuel assemblies with a maximum of 2.98% U-235 isotope, 61 control rod assemblies, and miscellaneous irradiated core and core basket material.
B. Radioactive material related to receipt, storage, and transfer of the above radioactive material, including 267 fuel canisters, 12 knockout canisters, and 62 filter canisters used to confine the above TMI-2 core debris in the absence of intact fuel assembly cladding.
A. As debris consisting of significantly damaged fuel and control assemblies and non-fuel reactor components in the form of partially intact assemblies, conglomerate core material, previously molten materials, rubble, and fines.
A.
82,985.9 kg U initially contained in the fuel assemblies of the damaged TMI-2 reactor core, contained in roughly 139,293 kg of material removed from the TMI-2 reactor vessel.
NRC FORM 588A (10-2000) 10 CFR 72 U. S. NUCLEAR REGULATORY COMMISSION PAGE 2
OF 3
PAGES License No.
Amendment No.
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE SUPPLEMENTARY SHEET SNM-2508 5
Docket or Reference No.
72-20 Renewed 10.
Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at the TMI-2 ISFSI located at the Idaho National Laboratory within the perimeter of the Idaho Nuclear Technology and Engineering Center site in Scoville, Idaho.
11.
The Secretary of Energy has delegated the Deputy Manager, Department of Energy, Idaho Cleanup Project, as the Secretarys authorized representative in all matters regarding this license and future amendments thereto and informed the Commission of this delegation in writing on September 8, 2016.
12.
Pursuant to 10 CFR 72.7, the licensee is hereby exempted from the following:
a)
Requirements of 10 CFR 72.102(f)(1) related to the specified seismic design criteria of 10 CFR Part 100, Appendix A.
b)
Requirements of 10 CFR 20.1501(d) to use NVLAP accredited dosimetry and instead is authorized to use DOELAP dosimetry.
c)
Requirement of 10 CFR 72.124(b) that the design of the ISFSI shall provide for positive means to verify the continued efficacy of solid neutron absorbing materials.
13.
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.
14.
For the duration of the license, the licensee shall inform the Director, NMSS, at least 90 days in advance, of the replacement of the entity contracted by DOE-ID to perform the management and operation (the DOE contractor) of the TMI-2 ISFSI.
Within 180 days after the replacement of the DOE contractor, the licensee shall assess the performance of the DOE contractor and provide a statement to the NRC verifying that the replacement of the DOE contractor has had no effect on the execution of licensed responsibilities for the TMI-2 ISFSI.
15.
DOE-ID shall be responsible for requesting necessary funds from Congress to ensure compliance of TMI-2 ISFSI operations and decommissioning under this license. DOE-ID will notify the Nuclear Regulatory Commission, 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-ID to obtain the required funding and/or prevent adverse impacts on ISFSI operations.
16.
Within 90 days after issuance of the renewed license, the licensee shall submit an updated FSAR to the Commission and continue to update the FSAR pursuant to the requirements in 10 CFR 72.70(b) and (c).
The updated FSAR shall include the revised TMI-2 ISFSI FSAR Supplement, as documented in Appendix C of the TMI-2 Independent Spent Fuel Storage Installation Application for 10 CFR 72 Specific License Renewal, Revision 3, dated May 21, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19150A336) (hereinafter referred to as the FSAR supplement). The licensee may make changes to the FSAR, including changes to the FSAR supplement, consistent with 10 CFR 72.48(c).
17.
Within one year after the renewed license effective date, the licensee shall document a program for implementing the activities in the Aging Management Programs (AMPs) described in the FSAR supplement. The program document shall contain a reference to the specific AMP provision(s) that the program document is intended to implement, and the reference shall be maintained even if the program document is modified. The licensee shall maintain the program document throughout the term of this license.
for the (ICP)
XX X, 2024 Department of Energy (DOE) ICP ICP ICP ICP ICP DOE DOE DOE designated designation
NRC FORM 588A (10-2000) 10 CFR 72 U. S. NUCLEAR REGULATORY COMMISSION PAGE 3
OF 3
PAGES License No.
Amendment No.
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE WASTE SUPPLEMENTARY SHEET SNM-2508 5
Docket or Reference No.
72-20 Renewed 18.
Horizontal storage module (HSM)-15 and its pre-installed dry shielded canister (DSC) overpack shall not be used for spent fuel storage operations.
19.
The NUHOMS-MP187 Multi-Purpose Cask described in the FSAR is prohibited for use as a transfer cask at the TMI-2 ISFSI if the NUHOMS-MP187 Multi-Purpose Cask was fabricated 20 or more years prior to the proposed date of use.
To use a NUHOMS-MP187 Multi-Purpose Cask aged greater than 20 years, the licensee shall submit a license amendment request which shall include information that will address aging management considerations for the NUHOMS-MP187 Multi-Purpose Cask.
20.
Transfer cask spacers, if required for DSC retrieval, shall only be used if they are fabricated fewer than 20 years before use.
21.
This license is effective as of the date of issuance shown below.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
/RA/
Meraj Rahimi, Chief Renewals and Materials Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Washington, DC 20555 Date of Issuance: March 19, 1999 Renewed License: Dated September 16, 2019
Attachment:
Appendix - Technical Specifications
Renewed License TECHNICAL SPECIFICATIONS FOR THREE MILE ISLAND - UNIT 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION
TMI-2 ISFSI 5.1-1 Renewed License Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Deputy Manager for Idaho Cleanup Project (ICP) (DOE-ID) is responsible for the operation of the TMI-2 ISFSI and for compliance with all applicable regulatory requirements and license conditions.
5.1.2 The TMI-2 Facility Director is responsible for overall ISFSI operation. The TMI-2 Facility Director and any alternates shall be designated in writing.
5.1.3 The TMI-2 Facility Director shall maintain routine electronic and verbal communication with the facility staff.
5.1.4 The TMI-2 Facility Director is stationed near the TMI-2 ISFSI at the Idaho National Laboratory site or in Idaho Falls, Idaho.
5.1.5 The TMI-2 Facility Director shall review and concur with all TMI-2 ISFSI evaluations prepared pursuant to 10 CFR 72.44(e), 10 CFR 72.44(f), 10 CFR 72.48, TS 5.5.1.b, and TS 5.5.2.3.
the
TMI-2 ISFSI 5.2-1 Renewed License Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations 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 for 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.
- 2.
The Deputy Manager for Idaho Cleanup Project (DOE-ID), 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.
- 3.
The individuals who train the operating staff, carry out health physics, or 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.
((continued) the ICP designated
Procedures 5.4 5.0 5.4 ADMINISTRATIVE CONTROLS Procedures TMI-2 ISFSI 5.4-1 Renewed License 5.4.1 Written procedures shall be established, implemented, and maintained for the following activities:
- 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.
Transfer operations;
- l.
Quality assurance inspections and audits;
- m.
- n.
Records management;
- o.
Reporting; and
- p.
All programs specified in Section 5.5.
Implementing procedures may be common with the Idaho National Laboratory procedures provided that all ISFSI requirements are met.
5.4.2 The 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 performance of audits of the Quality Assurance program. Each area will be reviewed at least biennially.
Idaho Operations Office
Programs 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs TMI-2 ISFSI 5.5-1 Renewed License 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:
- 1.
A change in the TS incorporated in the license; or
- 2.
A change to the SAR or Bases which involves an unreviewed safety question, a significant increase in occupational exposure, or a significant unreviewed environmental impact as defined in 10 CFR 72.48.
- c.
The Bases Control Program shall contain provisions to ensure the Bases are maintained consistent with the SAR.
- d.
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 without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 72.48(d)(2).
(continued) requires a license amendment according to the criteria of
Programs 5.5 5.5 Programs (continued)
TMI-2 ISFSI 5.5-2 Renewed License 5.5.2 Essential Program Control
- 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.
Changes may be made to essential programs without prior NRC approval provided the changes do not involve either of the following:
- a.
A change in the TS incorporated in the license; or
- b.
A decrease in effectiveness.
- 4.
The Essential Programs 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 programs implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 72.70(c)(6).
- 7.
DOE-ID shall review and approve all submittals to the NRC pursuant to TS 5.5.2.5 and TS 5.5.2.6.
(continued)
TMI-2 ISFSI 5.6-1 Renewed License Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements 5.6.1 All reports required by 10 CFR Part 72 for the TMI-2 ISFSI and all reports required by the TMI-2 ISFSI license and Technical Specifications, shall be submitted by the Manager, DOE-ID or the DOE-ID TMI-2 Facility Director.
5.6.2 All instances of noncompliance with the Limiting Conditions for Operations, Surveillance 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 noncompliance. Copies shall be provided to the Director, Office of Nuclear Material Safety and Safeguards and the Regional Administrator, Region IV.
for the ICP