ML23242A274
| ML23242A274 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/30/2023 |
| From: | Shaun Anderson Reactor Decommissioning Branch |
| To: | Holtec Decommissioning International |
| Sturzberger, Karl NMSS/RDB | |
| Shared Package | |
| ML23242a275 | List: |
| References | |
| EPID L-2022-LLA-0160 | |
| Download: ML23242A274 (12) | |
Text
Enclosure 2 Amendment No. 275 Renewed Operating License DPR-64 HOLTEC DECOMMISSIONING INTERNATIONAL, LLC AND HOLTEC INDIAN POINT 3, LLC DOCKET NO. 50-286 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO RENEWED FACILITY LICENSE Renewed License No. DPR-64 Amendment No. 275 (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. 3 (IP3) at the Indian Point Energy Center (IPEC) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 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 receipt, possession and use of source, byproduct and special nuclear material as authorized by this renewed license will be in accordance with the Commissions regulations in 10 CFR Parts 30,40 and 70 including 10 CFR Sections 30.33, 40.32, 70.23 and 70.31; F. The issuance of this renewed license is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
(2)
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by changes to IP3 License Condition 1.I and the paragraphs under 2.C.(2) of Renewed Facility License No. DPR-64 is hereby amended to read as follows:
Amendment No. 275 Renewed Operating License DPR-64 The Technical Specifications contained in Appendices A, as revised through Amendment No. 275, are hereby incorporated in the renewed license. HDI shall maintain the facility in accordance with the Technical Specifications.
Further, Renewed Facility License No. DPR-64 is hereby amended to:
Deletion of IP2 License Condition 1.J requirements for actions to manage the effects of aging during the period of extended operation on the functionality of structures and components; and Revise the paragraphs in 2.C.(2) with updated references, deletion of the Mitigation Strategy License Conditions, and License Renewal License Condition; and Renaming of IP3 Appendix A, Permanently Defueled Technical Specifications (PDTS) to ISFSI Only Technical Specifications (IOTS); and Relocate various PDTS Appendix A sections to the IP2 Defueled Safety Analysis Reports (DSAR); and Deletion of the IP3 Appendix C Technical Specifications in their entirety.
- 3.
This license amendment is effective upon the date of submittal of written notification to the NRC, pursuant to 10 CFR 50.82(a), Termination of license - For power reactor licensees, that all spent nuclear fuel assemblies have been transferred out of the Indian Point Nuclear Generating Station, Unit No. 3 SFP and placed in dry storage within the onsite independent spent fuel storage installation, and shall be implemented within 30 days following that date.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
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 29, 2023
Amendment No. 275 ATTACHMENT TO LICENSE AMENDMENT NO. 275 INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 RENEWED FACILITY LICENSE NO. DPR-64 DOCKET NO. 50-286 Replace the following pages of Renewed Facility License No. DPR-64 and Appendix A, Technical Specifications. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
Renewed Facility License No. DPR-64 REMOVE INSERT Page 2 Page 2 Page 3 Page 3 Page 4 Page 4 Page 5 Page 5 Page 6 Page 6 Appendix A, Technical Specifications REMOVE INSERT Title Page All Pages Page i (Including title page)
Page 4.0-1 Page 5.0-14 RELOCATE Page 5.0-1 To DSAR Page 5.0-2 Page 5.0-4 through 5.0-9 Page 5.0-11 Appendix C, Technical Specifications REMOVE INSERT Cover Sheet, and i through 5.0-4
-No Pages-Amendment No. 275 H. The issuance of this renewed license is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
Deleted per Amendment No. 275.
- 2. Accordingly, Renewed Facility License No. DPR-64 is hereby issued to Holtec IP3 and HDI to read as follows:
A. This renewed license applies to the Indian Point Nuclear Generating Unit No. 3, a pressurized water nuclear reactor and associated equipment (the facility), which is owned by Holtec IP3 and maintained by HDI. The facility is located in Westchester County, New York, on the east bank of the Hudson River in the Village of Buchanan, and is described in the Defueled Safety Analysis Report as supplemented and amended, and the Environmental Report, as amended.
B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1)
Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," (a) Holtec IP2 to possess and use, and (b) HDI to possess and use, the facility at the designated location in Westchester County, New York, in accordance with the procedures and limitations set forth in this renewed license; (2)
HDI pursuant to the Act and 10 CFR Part 70, to possess at any time special nuclear material that was used as reactor fuel, in accordance with the limitations for storage, as described in the Defueled Safety Analysis Report, as supplemented and amended.
(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 calibration of reactor instrumentation and are used in the calibration of radiation monitoring equipment, and that were used as fission detectors in amounts as required; Amendment No. 275 (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 below:
(1)
Deleted per Amendment No. 270.
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 275, are hereby incorporated in the renewed license. HDI shall maintain the facility in accordance with the Technical Specifications.
D. (DELETED)
E. (DELETED)
F. This renewed license is also subject to appropriate conditions by the New York State Department of Environmental Conservation in its letter granting a Section 401 certification under the Federal Water Pollution Control Act Amendments of 1972.
G. HDI shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and to the authority of 10 CFR 50.90 and CFR 50.54(p). The combined set of plans1 for the Indian Point Energy Center, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0, and was submitted by letter dated October 14, 2004, as supplemented by letter dated May 18, 2006.
1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan.
Amendment No. 275 HDI has been granted Commission authorization to use "stand alone preemption authority" under Section 161A of the Atomic Energy Act, 42 U.S.C. 2201a with respect to the weapons described in Section II supplemented with Section Ill of to its application submitted by letter dated August 20, 2013, as supplemented by letters dated November 21, 2013, and July 24, 2014, and citing letters dated April 27, 2011, and January 4, 2012. HDI shall fully implement and maintain in effect the provisions of the Commission-approved authorization.
Amendment No. 275 W. thru AE. Deleted on Page 5 as per Amendment No. 275.
Amendment No. 275 AF. Deleted as per Amendment 275.
- 3.
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 - ISFSI Only Technical Specifications Appendix B - Environmental Technical Specification Requirements Date of Issuance: September 17, 2018
Amendment No. 275 APPENDIX A TO RENEWED FACILITY LICENSE DPR-64 ISFSI ONLY TECHNICAL SPECIFICATIONS FOR THE INDIAN POINT 3 NUCLEAR GENERATING UNIT NO. 3 WESTCHESTER COUNTY, NEW YORK HOLTEC INDIAN POINT 3, LLC (HOLTEC IP3)
AND HOLTEC DECOMMISSIONING INTERNATIONAL, LLC, (HDI)
DOCKET NO. 50-286 Date of Issuance:
April 15, 1976
RENEWED FACILITY LICENSE No. DPR-64 Appendix A - ISFSI Only Technical Specifications Indian Point 3 i
Amendment No. 275 Table of Contents 4.0 DESIGN FEATURES 4.1 Site Location 4.2 Deleted 4.3 Fuel Storage 5.0 AMINISTRATIVE CONTROLS 5.7 High Radiation Level
Indian Point 3 4.0 - 1 Amendment No. 275 Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location IP3 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.
4.2 Deleted 4.3 Fuel Storage Spent fuel shall not be stored in the IP3 Spent Fuel Pit.
Indian Point 3 5.0 - 14 Amendment No. 275 High Radiation Area 5.7 5.7 High Radiation Area 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 lead licensee representative on shift, 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.
- b.
Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
- c.
Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following facility radiation protection procedures for entry to, exit from, and work in such areas.
- d.
Each individual or group entering such an area shall possess:
- 1.
A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or
- 2.
A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or