Letter Sequence Draft Approval |
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MONTHYEARML17142A0732016-10-19019 October 2016 Letter to P. Schmidt Review of the Draft Environmental Assessment and Finding of No Significant Impact for the Point Beach Nuclear Independent Spent Fuel Storage Installation Decommissioning Funding Plan (ML16293A165-RLSO) Project stage: Draft Approval 2016-10-19
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Category:Letter
MONTHYEARIR 05000266/20240032024-11-0505 November 2024 Integrated Inspection Report 05000266/2024003 and 05000301/2024003 ML24295A1142024-10-31031 October 2024 Suppl Env Audit Summary Letter W/Enclosure 1 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)2024-10-21021 October 2024 Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41) ML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 2024-09-09
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PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE WISCONSIN RADIATION PROTECTION SECTION. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 19, 2016 Paul Schmidt, Manager Radiation Protection Section Division of Public Health Dept. of Health Services P.O. Box 2659 Madison, WI 53701-2659
SUBJECT:
REVIEW OF THE DRAFT ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR THE POINT BEACH NUCLEAR INDEPENDENT SPENT FUEL STORAGE INSTALLATION DECOMMISSIONING FUNDING PLAN
Dear Mr. Schmidt:
By letters dated December 17, 2012, and March 27, 2015, NextEra Energy (NextEra) submitted decommissioning funding plans (DFP) for the Point Beach Independent Spent Fuel Storage Installation (ISFSI), located in Ohio, for U.S. Nuclear Regulatory Commission (NRC) staff review and approval.
The NRC regulations at Title 10 of the Code of Federal Regulations (10 CFR) Part 72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste, govern the storage of spent nuclear fuel (spent fuel) generated at commercial nuclear power reactors licensed by the NRC. Spent fuel that has been removed from the reactors spent fuel pool is typically stored at a nuclear power plants ISFSI.
The NRC requires its licensees to plan for the eventual decommissioning of their licensed facilities prior to license termination. On June 17, 2011, the NRC published a final rule amending its decommissioning planning regulations (76 Federal Register (FR) 35512). The final rule amended the NRC regulation, 10 CFR 72.30, which concerns financial assurance and decommissioning for ISFSIs. This regulation now requires each holder of, or applicant for, a license under 10 CFR Part 72 to submit, for NRC review and approval, a DFP. The purpose of the DFP is to demonstrate the licensees financial assurance, i.e., that funds will be available to decommission the ISFSI. The NRC staff is reviewing the information submitted by NextEra.
Specifically, the NRC must determine whether NextEra DFP contains the information required by 10 CFR 72.30(b) and 10 CFR 72.30(c) Tri-Annual Update and whether NextEra has provided reasonable assurance that funds will be available to decommission the ISFSI.
The NextEra ISFSI DFP is publicly available in the NRCs Agencywide Documents Access and Management System (ADAMS) accessible at http://www.nrc.gov/reading-rm/adams.html.
PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE WISCONSIN RADIATION PROTECTION SECTION. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE WISCONSIN RADIATION PROTECTION SECTION. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
P. Schmidt The ADAMS accession number for the application package is ML12354A134 for the 2012 submittal and ML15090A114 for the 2015 submittal.
In accordance with 10 CFR Part 51, the NRC regulations that implement the National Environmental Policy Act of 1969, as amended, the agency has prepared a draft environmental assessment (EA) for the proposed action (enclosed). We are providing your office with the opportunity to review the draft EA and comment on environmental issues prior to the public issuance and publication of the EA. We request that distribution and use of the enclosed draft EA be limited only to those staff involved in the review and comment process.
Please submit any comments within 30 days of the receipt of this letter to the U.S. Nuclear Regulatory Commission, Document Control Desk, ATTN: John McKirgan, Mail Stop:
TWFN 4B-34, U.S. Nuclear Regulatory Commission, Washington, DC 20555. If you have any questions, please contact Mr. Richard Baum of my staff by telephone at 301-415-0018, or by e-mail at richard.baum@nrc.gov. The NRC staff will consider your timely comments and will revise the EA, as appropriate, before its final issuance and publication. Thank you for your assistance.
Sincerely,
/RA/
John McKirgan, Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards Docket No.: 72-05 CAC No.: L24840
Enclosure:
Draft Environmental Assessment PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE WISCONSIN RADIATION PROTECTION SECTION. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
ML16293A163 Letter: ML16293A165
Enclosure:
ML16293A168 OFC DSFM DSFM DSFM NAME RBaum WWheatley JMcKirgan DATE 09/29/16 09/29/16 10/19/16 C = COVER E = COVER & ENCLOSURE N = NO COPY