ML22307A045
| ML22307A045 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/17/2023 |
| From: | Shaun Anderson Reactor Decommissioning Branch |
| To: | |
| Karl Sturzebecher, 301-415-8534 | |
| Shared Package | |
| ML23050A001 | List: |
| References | |
| EPID L-2022-LLA-0112 | |
| Download: ML22307A045 (16) | |
Text
Enclosure 1 Amendment No. 297 Renewed Operating License DPR-46 HOLTEC DECOMMISSIONING INTERNATIONAL, LLC AND HOLTEC INDIAN POINT 2, LLC DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 AMENDMENT TO RENEWED FACILITY LICENSE Renewed License No. DPR-26 Amendment No. 297 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Holtec Decommissioning International, LLC (HDI),
on behalf of Holtec Indian Point 2, LLC (IP1 & IP2), for Indian Point Nuclear Generating Unit No. 2 at the Indian Point Energy Center complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in Title 10 of the Code of Federal Regulations (10 CFR), Chapter I; B. The facility will be maintained in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this renewed license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; D. The issuance of this renewed license will not be inimical to the common defense and security or to the health and safety of the public; E. The issuance of this amendment is in accordance with 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions, of the Commissions regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes as indicated in the attachment to this license amendment. Specifically, paragraph 2.c.(2) of Renewed Facility License No. DPR-26 is hereby amended to read as follows:
The Technical Specifications contained in Appendices A, and B, as revised through Amendment No. 297, are hereby incorporated in the renewed license. HDI shall maintain the facility in accordance with the Technical Specifications.
Amendment No. 297 Renewed Operating License DPR-46 Further, Renewed Facility License No. DPR-26 is hereby amended to:
Modify the IP2 staffing requirements in Appendix A, Permanently Defueled Technical Specifications (PDTS);
Revise the 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, Renewed Facility License (RFL) and delete the Appendix C, Inter-Unit Fuel Transfer Technical Specifications, (Appendix C TS) to prohibit the transfer of Indian Point Nuclear Generating Station, Unit No. 3 (IP3) spent fuel to the IP2 spent fuel pit (SFP); and Incorporate a prohibition against the storage of spent fuel in the IP2 SFP in the PDTS.
3.
This license amendment is effective upon issuance and shall be implemented within 60 days following that date.
FOR THE NUCLEAR REGULATORY COMMISSION Shaun M. Anderson, Chief Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery and Waste Programs Office of Nuclear Material Safety and Safeguards
Attachment:
Changes to the Renewed Facility License and Technical Specifications Date of Issuance: November 17, 2023 Signed by Anderson, Shaun on 11/17/23
Amendment No. 297 Renewed Operating License DPR-46 ATTACHMENT TO LICENSE AMENDMENT NO. 297 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 RENEWED FACILITY LICENSE NO. DPR-26 DOCKET NO. 50-247 Replace the following pages of Renewed Facility License No. DPR-26 and Appendix A, Technical Specifications, with the attached revised pages, and delete Appendix C. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Renewed Facility License No. DPR-26 REMOVE INSERT Page 3 Page 3 Page 6 Page 6 Page 7 Page 7 Appendix A, Technical Specifications REMOVE INSERT Page i Page i Page 1.1-1 Page 1.1-1 Page 4.0-1 and 4.0-2 Page 4.0-1 and 4.0-2 Page 5.1-1 Page 5.1-1 Page 5.2-1 and 5.2-2 Page 5.2-1 and 5.2-2 Page 5.3-1 Page 5.3-1 Page 5.7-2 Page 5.7-2 Appendix C, Technical Specifications REMOVE INSERT Cover Sheet, and i through 5.0-4
-No Pages-Amendment No. 297 Renewed Operating License DPR-46 3.
HDI pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use, at any time any byproduct, source and special nuclear material as sealed neutron sources that were used for reactor startup, sealed sources that were used for reactor instrumentation and are used in the calibration of radiation monitoring equipment, and that were used as fission detectors in amounts as required; 4.
HDI pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; 5.
HDI pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials that were produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Deleted per Amendment No. 294.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 297, are hereby incorporated in the renewed license. HDI shall maintain the facility in accordance with the Technical Specifications.
(3)
Deleted per Amendment No. 294.
Amendment No. 297 Renewed Operating License DPR-46 (c)
Actions to minimize release to include consideration of:
1.
Water spray scrubbing 2.
Dose to onsite responders O. Deleted per Amendment No. 294.
P. Deleted per Amendment No. 297.
Q. License Renewal License Conditions (1)
The information in the UFSAR supplement, submitted pursuant to 10 CFR 54.21(d) and as revised during the license renewal application review process, and licensee commitments as listed in Appendix A of the Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Units 2 and 3, (SER) and supplements to the SER, are collectively the License Renewal UFSAR Supplement. The UFSAR Supplement is henceforth part of the UFSAR, which will be updated in accordance with 10 CFR 50.71(e). As such, the licensee may make changes to the programs, activities, and commitments described in the UFSAR Supplement, provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59, Changes, Tests, and Experiments, and otherwise complies with the requirements in that section.
(2)
The License Renewal UFSAR Supplement, as defined in license condition Q(1) above, describes certain programs to be implemented and activities to be completed prior to the period of extended operation (PEO).
a.
The licensee shall implement those new programs and enhancements to existing programs no later than the date specified in the License Renewal UFSAR Supplement.
b.
The licensee shall complete those activities no later than the date specified in the License Renewal UFSAR Supplement.
c.
The licensee shall notify the NRC in writing within 30 days after having accomplished item (2)a above and include the status of those activities that have been or remain to be completed in item (2)b above.
3.
Deleted (a)
Deleted (b)
Provisional Trust:
(i)
The provisional trust agreement must be in a form acceptable to the NRC.
(ii)
Investment in the securities or other obligations of Holtec International or its affiliates, subsidiaries, successors, or assigns are and shall be prohibited.
Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are and shall be prohibited.
(iii)
The provisional trust agreement must provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee unless the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The provisional trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.
(iv)
The provisional trust agreement must provide that the agreement cannot be amended in any material respect, or terminated, without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.
(v)
The appropriate section of the provisional trust agreement shall state that the trustee, investment advisor, or anyone else directing the investments made in the trust shall adhere to a prudent investor standard, as specified in 18 CFR 35.32(a)(3) of the Federal Energy Regulatory Commission's regulations.
(vi)
Use of assets in the provisional trust, in the first instance, shall be limited to the expenses related to decommissioning IP2 or IP1 as defined by the NRC in its regulations and issuances, and as provided in this license and any amendments thereto.
(c)
Deleted 4.
Deleted 5.
Deleted 6.
This renewed license is effective as of the date of issuance, and until the Commission notifies the licensee in writing that the license is terminated.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Ho K. Nieh, Director Office of Nuclear Reactor Regulation Attachments:
Appendix A - Permanently Defueled Technical Specifications Appendix B - Environmental Technical Specification Requirements Date of Issuance: September 17, 2018
Amendment No. 297 Renewed Operating License DPR-46 APPENDIX A TO FACILITY LICENSE DPR-26 FOR HOLTEC INDIAN POINT 2, LLC AND HOLTEC DECOMMISSIONING INTERNATIONAL, LLC INDIAN POINT NUCLEAR GENERATING PLANT UNIT NO. 2 DOCKET NO. 50-247 PERMANENTLY DEFUELS TECHNICAL SPECIFICATIONS AND BASES
FACILITY LICENSE No. DPR-26 Appendix A - Permanently Defueled Technical Specifications Indian Point 2 i
Amendment No. 297 Table of Contents 1.0 USE AND APPLICATION 1.1 Definitions 1.2 Logical Connectors 1.3 Completion Times 1.4 Frequency 2.0 DELETED 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 3.7 SPENT FUEL PIT REQUIREMENTS 3.7.11 Spent Fuel Pit Water Level 3.7.12 Spent Fuel Pit Boron Concentration 3.7.13 Spent Fuel Pit Storage 4.0 DESIGN FEATURES 4.1 Site Location 4.2 Deleted 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.2 Organization 5.2.1 Onsite and Offsite Organizations 5.3 Facility Staff Qualifications 5.4 Procedures 5.5 Programs And Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) 5.5.2 Deleted 5.5.3 Radioactive Effluent Controls Program 5.5.4 Deleted 5.5.5 Deleted 5.5.6 Deleted 5.5.7 Deleted 5.5.8 Deleted 5.5.9 Deleted 5.5.10 Explosive Gas and Storage Tank Radioactivity Monitoring Program 5.5.11 Deleted 5.5.12 Technical Specification (TS) Bases Control Program 5.5.13 Deleted 5.5.14 Deleted 5.5.15 Deleted 5.5.16 Deleted
Definitions 1.1 1.0 USE AND APPLICATION Indian Point 2 1.1 - 1 Amendment No. 297 1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
Design Features 4.0 Indian Point 2 4.0 - 1 Amendment No. 297 4.0 DESIGN FEATURES 4.1 Site Location Indian Point 2 is located on the East bank of the Hudson River at Indian Point, Village of Buchanan, in upper Westchester County, New York. The site is approximately 24 miles north of the New York City boundary line. The nearest city is Peekskill which is 2.5 miles northeast of Indian Point.
The minimum distance from the reactor center line to the boundary of the site exclusion area and the outer boundary of the low population zone, as defined in Title 10 of the Code of Federal Regulations (10 CFR) 100.3, Definitions, is 520 meters and 1100 meters, respectively. For the purpose of satisfying 10 CFR Part 20, Standards for Protection Against Radiation, the Restricted Area is the same as the Exclusion Area shown in the Defueled Safety Analysis Report (DSAR), Figure 2.2-2.
4.2 Deleted 4.3 Fuel Storage Spent fuel shall not be stored in the Spent Fuel Pit.
Design Features 4.0 Indian Point 2 4.0 - 2 Amendment No. 297 4.0 DESIGN FEATURES 4.3 Deleted
Responsibility 5.1 Indian Point 2 5.1 - 1 Amendment No. 297 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety.
Organization 5.2 Indian Point 2 5.2 - 1 Amendment No. 297 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility staff and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear fuel.
a.
Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all decommissioning organization 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 personnel 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 DSAR, b.
The plant manager shall be responsible for overall safe maintenance of the facility and shall have control over those onsite activities necessary for storage and maintenance of nuclear fuel.
c.
The corporate officer with direct responsibility for IP2 shall have corporate responsibility for the safe storage and handling of nuclear fuel and shall take any measures needed to ensure acceptable performance of the staff in maintaining and providing technical support to the facility to ensure safe management of nuclear fuel, and d.
The individuals who train the individuals that 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 ability to perform their assigned functions.
Organization 5.2 Indian Point 2 5.2 - 2 Amendment No. 297 5.2 Organization
Procedures 5.3 Indian Point 2 5.3 - 1 Amendment No. 297 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the HDI Quality Assurance Program Manual (QAPM).
Indian Point 2 5.7 - 2 Amendment No. 297 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued) 4.
A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter)
- and, a.
Be under the surveillance, as specified in the Radiation Work Permit (RWP) or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or b.
Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.
e.
Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.
5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation
- a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:
1.
All such door and gate keys shall be maintained under the administrative control of the IP3 Shift Manager, radiation protection manager, or his or her designee.
2.
Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.