ML19282A403
ML19282A403 | |
Person / Time | |
---|---|
Site: | Braidwood |
Issue date: | 10/09/2019 |
From: | Marchionda-Palmer M Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
References | |
BW190096 | |
Download: ML19282A403 (1) | |
Similar Documents at Braidwood | |
---|---|
Category:Annual Operating Report
MONTHYEARRS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024
[Table view]Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24071A1152024-03-31031 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 BW220029, Annual Radiological Environmental Operating Report, 1 January Through 31 December 20212022-05-31031 May 2022 Annual Radiological Environmental Operating Report, 1 January Through 31 December 2021 RS-21-046, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-04-0808 April 2021 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors BW200037, Annual Radiological Environmental Operating Report2020-05-31031 May 2020 Annual Radiological Environmental Operating Report RS-20-043, 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2020-04-0909 April 2020 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML19282A4032019-10-0909 October 2019 10 CFR 72.48 Evaluation Summary Report RS-19-042, Submittal of Annual 1O CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2019-04-0909 April 2019 Submittal of Annual 1O CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-18-039, Stations - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2018-04-0909 April 2018 Stations - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17132A3892017-05-12012 May 2017 2016 Annual Radiological Environmental Operating Report RS-15-104, Annual Property Insurance Status Report2015-04-0101 April 2015 Annual Property Insurance Status Report ML13137A1052013-05-14014 May 2013 Submittal of 2012 Annual Radiological Environmental Operating Report ML13134A0492013-04-30030 April 2013 Submittal of 2012 Radioactive Effluent Release Report RS-13-090, and Byron Station - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2013-04-0505 April 2013 and Byron Station - Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-14-029, Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 20122012-12-31031 December 2012 Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2012 ML14030A2942012-12-31031 December 2012 Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2012 ML12137A3042012-05-14014 May 2012 Submittal of 2011 Annual Radiological Environmental Operating Report ML12130A1982012-04-26026 April 2012 2011 Radioactive Effluent Release Report RS-12-054, Submittal of Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2012-04-0606 April 2012 Submittal of Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-14-029, Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 20112011-12-31031 December 2011 Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2011 ML14030A2932011-12-31031 December 2011 Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2011 RS-14-029, Transmittal of Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 20102011-04-22022 April 2011 Transmittal of Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2010 ML14030A2922011-04-22022 April 2011 Transmittal of Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2010 RS-11-052, Units 1 and 2 - Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2011-04-0606 April 2011 Units 1 and 2 - Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors ML1013904752010-05-14014 May 2010 Annual Radiological Environmental Operating Report RS-10-075, Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2010-04-0808 April 2010 Annual 10 CFR 50.46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-09-051, Annual 10 CFR 50 .46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors2009-04-0909 April 2009 Annual 10 CFR 50 .46 Report of the Emergency Core Cooling System Evaluation Model Changes and Errors RS-14-029, Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 20082008-12-31031 December 2008 Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2008 ML14030A2902008-12-31031 December 2008 Annual Report on the Meteorological Monitoring Program at the Braidwood Nuclear Power Station 2008 RS-08-053, Annual & Thirty Day Reports of the Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems..2008-04-11011 April 2008 Annual & Thirty Day Reports of the Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems.. RS-07-052, Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors.2007-04-13013 April 2007 Annual Report of the Emergency Core Cooling System Evaluation Model Changes and Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. ML0435705032004-12-16016 December 2004 10 CFR 50.59 Biennial Report ML0413902102004-05-14014 May 2004 2003 Annual Radiological Environmental Operating Report RS-04-051, Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for light-water Nuclear Power Reactors.2004-04-14014 April 2004 Annual Report of Emergency Core Cooling System Evaluation Model Changes & Errors Required by 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for light-water Nuclear Power Reactors. 2024-04-10 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
[Table view]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 |
Text
=~Exelon Generation Exelon Generation Company, LLC Braidwood Station 35100 South Route 53, Suite 84 Braceville, IL 60407-9619 October 9, 2019 10 CFR 72.48 BW190096 ATTN: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. 50-456. 50-457 and 72-73
Subject:
10 CFR 72.48 Evaluation Summary Report The purpose of this letter is to submit the biennial report of changes, tests, or experiments, performed by Exelon Generation Company, LLC (EGC) for the Braidwood Station (Braidwood)
Independent Spent Fuel Storage Installation (ISFSI), as required by 10 CFR 72.48, "Changes, tests, and experiments," paragraph (d)(2). EGC submitted the previous biennial report on October 9, 2017. Accordingly, this submittal is due by October 9, 2019.
This report addresses the period from October 1, 2017 through September 30, 2019. There were no 10 CFR 72.48 Evaluations performed for the Braidwood ISFSI during this period. Thus, no 10 CFR 72.48 Evaluation summaries are provided.
There are no regulatory commitments contained within this letter.
Should you have any questions, please contact Mr. Kevin Lueshen, Regulatory Assurance Manager, at (815) 417-2800.
Respectfully, Marri Marchionda-Palmer Site Vice President Braidwood Station