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Category:Letter
MONTHYEARRS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24291A0012024-10-17017 October 2024 Submittal of Core Operating Limits Report, Cycle 25 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 2024-09-23
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PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE ILLINOIS EMERGENCY MANAGEMENT AGENCY. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 22, 2016 Joseph G. Klinger, Assistant Director Illinois Emergency Management Agency Division of Nuclear Safety 2200 S. Dirksen Parkway Springfield, IL 62703
SUBJECT:
REVIEW OF THE DRAFT ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT FOR THE BRAIDWOOD STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION DECOMMISSIONING FUNDING PLAN
Dear Mr. Klinger:
By letters dated December 17, 2012, and March 31, 2015, Exelon Generation (EG) submitted decommissioning funding plans (DFP) for the Braidwood Station Units 1 and 2 Independent Spent Fuel Storage Installation (ISFSI), located in Illinois, 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 EG, Specifically, the NRC must determine whether EG DFP contains the information required by 10 CFR 72.30(b) and 10 CFR 72.30 (c) Tri-Annual Update and whether EG has provided reasonable assurance that funds will be available to decommission the ISFSI.
The EG 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 ILLINOIS EMERGENCY MANAGEMENT AGENCY. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE ILLINOIS EMERGENCY MANAGEMENT AGENCY. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
J. Klinger The ADAMS accession number for the application package is ML12353A488 for the 2012 submittal and ML15090A537 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 4-B34, 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.: 72-73 CAC No.: L24788
Enclosure:
Draft Environmental Assessment PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE ILLINOIS EMERGENCY MANAGEMENT AGENCY. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE ILLINOIS EMERGENCY MANAGEMENT AGENCY. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.
J. Klinger The ADAMS accession number for the application package is ML12353A488 for the 2012 submittal and ML15090A538 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 4-B34, 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.: 72-73 CAC No.: L24788
Enclosure:
Draft Environmental Assessment G:SFST\72.30 Decommissioning Funding Plans\2015 Submission Part 70.30 (c)\Braidwood Station DFP Consultation Letter to State.docx G:SFST\72.30 Decommissioning Funding Plans\2015 Submission Part 70.30 (c)\Braidwood Station Draft EA for Consultation.docx ADAMS P8 Accession No.: ML16174A429 Letter: ML16174A437
Enclosure:
ML16174A438 OFC DSFM DSFM DSFM DSFM NAME RBaum WWheatley JMcKirgan DATE 6/14/16 6/21/16 6/22/16 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY PRE-DECISIONAL INFORMATION. THIS INFORMATION IS LIMITED TO USE BY THE ILLINOIS EMERGENCY MANAGEMENT AGENCY. THIS INFORMATION SHALL NOT BE DISCLOSED WITHOUT PRIOR NRC PERMISSION.