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MONTHYEARRS-14-194, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-07-14014 July 2014 Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report Project stage: Response to RAI RS-15-064, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2015-03-12012 March 2015 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report Project stage: Request ML15093A3152015-03-23023 March 2015 NRR E-mail Capture - Resend: Request for Additional Information: Braidwood Flooding Hazard Reevaluation Report Project stage: RAI ML15148A2862015-07-21021 July 2015 Nuclear Regulatory Commission Plan for the Audit of Exelon Generation Company, Llc'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 -Flooding Project stage: Other ML15211A3632015-09-0303 September 2015 Interim Staff Response to Reevaluated Floor Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other ML15230A2362015-09-0303 September 2015 Tables 1 and 2 Project stage: Request RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal Project stage: Other 2015-03-23
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Category:Letter type:RS
MONTHYEARRS-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 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 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary 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 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) 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 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 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 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 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 2024-06-04
[Table view] Category:Report
MONTHYEARRS-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 BW240017, EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements2024-04-0303 April 2024 EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements ML24094A2702024-04-0303 April 2024 MDMP Deviation Form 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 BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18348A9792018-12-14014 December 2018 Transmittal of 10 CFR 50.59 Summary Report ML18348A9722018-12-12012 December 2018 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-223, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2016-12-0707 December 2016 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... ML16356A0202016-10-0707 October 2016 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17360A1742016-10-0707 October 2016 Attachment 6: Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations (Non-Proprietary) ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal ML16250A5182016-04-30030 April 2016 Technical Evaluation Report Related to the Exelon Generation Company, LLC, License Amendment Request to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink. Docket Nos. Stn 50-456 & 457 RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-16-057, Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds2016-03-15015 March 2016 Supplement to Response to Requests for Additional Information for Relief for Alternate Requirements for Repair of Reactor Vessel Head Penetrations with Nozzles Having Pressure-Retaining Partial-Penetration J-Groove Welds ML16014A1882016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-259, Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge.2015-09-30030 September 2015 Final Report: Five Year Post-Construction Monitoring of the Unionid Community Near the Braidwood Station Kankakee River Discharge. RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application 2024-05-28
[Table view] Category:Miscellaneous
MONTHYEARRS-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 ML24094A2702024-04-0303 April 2024 MDMP Deviation Form ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting RS-17-048, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2017-04-0707 April 2017 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 RS-16-174, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review...2016-11-0303 November 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review... RS-17-039, Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations.2016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17095A2692016-10-0707 October 2016 Attachment 6, Areva Document 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML17170A1472016-10-0707 October 2016 Areva, 51-9263014-000, PWSCC Evaluation of Uhp Cavitation Peening for Byron and Braidwood Reactor Vessel Head Penetrations. ML16236A2082016-08-23023 August 2016 Report of Backfit Appeal Review Panel ML16214A1992016-08-11011 August 2016 an Assessment of Core Damage Frequency for Byron/Braidwood Backit Appeal Review RS-16-099, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal RS-16-073, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2016-04-0707 April 2016 Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML16014A1882016-01-22022 January 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review of Insights ML15344A1592015-12-10010 December 2015 Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7 ML15322A3172015-11-18018 November 2015 Record of Decision ML15237A3822015-10-15015 October 2015 Pressure and Temperature Limits Report for Measurement Uncertainty Recapture Power Uprate RS-15-129, Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 20152015-04-30030 April 2015 Westinghouse Report CCE-15-27, Revision 1, Braidwood Units 1 and 2 - Responses to NRC Request for Additional Information (Rai)Regarding Ultimate Heat Sink Temperature Increase License Amendment Request, April 2015 RS-14-348, Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application2014-12-15015 December 2014 Comments on the Safety Evaluation Report with Open Items, Related to the License Renewal Application ML14349A6572014-12-15015 December 2014 CFR 50.59 Changes, Tests, and Experiments, Paragraph (d)(2), Summary Report ML14141A1332014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14101A3522014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14101A4452014-06-0404 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (Tac No. MF0095) ML14127A1742014-05-0707 May 2014 Startup Report for the Measurement Uncertainty Recapture Power Uprate ML14120A0392014-04-24024 April 2014 Units 1 & 2 - License Amendment Request to Install New Low Degraded Voltage Relays & Timers on the 4.16 Kv Engineered Safety Features (ESF) Buses ML14066A4792014-03-0404 March 2014 Clarification of Licensing Basis Assumptions for a Natural Circulation Cooldown Event ML14059A1242014-02-28028 February 2014 Pressure and Temperature Limits Reports (Ptlrs) IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12349A3632012-12-14014 December 2012 10 CFR 50.59 Summary Report for June 19, 2010 Through June 18, 2012 ML12339A2212012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 4 of 5 ML12339A2202012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 3 of 5 ML12339A2192012-11-16016 November 2012 12Q0108.10-R-001, Revision 0, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Braidwood Station, Unit 1. Part 2 of 5 2024-05-28
[Table view] |
Text
"1011111111- P, Amow Exelon Generation.
RS-16-099 Order No. EA-12-049 June 30, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457
Subject:
Mitigating Strategies Flood Hazard Assessment (MSFHA) Submittal
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident; dated March 12, 2012
- 2. Exelon Generation Company, LLC Letter to USNRC, Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flooding Hazard Reevaluation Report, dated March 12, 2014 (RS-14-052)
- 3. Exelon Generation Company, LLC Letter to USNRC, Response to Request for Additional Information Regarding Fukushima Lessons Learned Flood Hazard Reevaluation Report, dated July 14, 2014 (RS-14-194)
- 4. Exelon Generation Company, LLC Letter to USNRC, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned Flood Hazard Reevaluation Report, dated February 17, 2015 (RS-15-050)
- 5. Exelon Generation Company, LLC Letter to USNRC, Response to Request for Additional Information Regarding Fukushima Lessons Learned Flood Hazard Reevaluation Report, dated June 24, 2015 (RS-15-112)
- 6. NRC Letter, Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 1, 2013
- 7. NRC Staff Requirements Memoranda to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards", dated March 30, 2015
U.S. Nuclear Regulatory Commission Mitigating Strategies Flood Hazard Assessment (MSFHA) Submittal June 30, 2016 Page 2
- 8. NRC Letter, Coordination of Requests for Information Regarding Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events, dated September 1, 2015
- 9. Nuclear Energy Institute (NEI), Report NEI 12-06 [Rev 2], Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated December 2015 10.U.S. Nuclear Regulatory Commission, JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events, dated January 22, 2016 11.NRC Letter, Braidwood Station, Units 1 and 2 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request Flood-Causing Mechanism Reevaluation JAC Nos. MF3895 and MF3896), dated September 3, 2015 On March 12, 2012, the NRC issued Reference 1 to request information associated with Near-Term Task Force (NTTF) Recommendation 2.1 for Flooding. One of the Required Responses in Reference 1 directed licensees to submit a Flood Hazard Reevaluation Report (FHRR). For Braidwood Station, Units 1 and 2, the FHRR was submitted on March 12, 2014 (Reference 2).
Additional information was provided with References 3, 4, and 5. Per Reference 6, the NRC considers the reevaluated flood hazard to be "beyond the current design/licensing basis of operating plants".
Concurrent to the flood hazard reevaluation, Braidwood Station, Units 1 and 2, developed and implemented mitigating strategies in accordance with NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events". In Reference 7, the NRC affirmed that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis (BDB) external events. This requirement was confirmed by the NRC in Reference 8. Guidance for performing mitigating strategies flood hazard assessments (MSFHAs) is contained in Appendix G of Reference 9, endorsed by the NRC in Reference 10. For the purpose of the MSFHAs and in Reference 8, the NRC termed the reevaluated flood hazard, summarized in Reference 11, as the "Mitigating Strategies Flood Hazard Information" (MSFHI). Reference 9, Appendix G, describes the MSFHA for flooding as containing the following elements:
- Section G.2 Characterization of the MSFHI
- Section G.3 Basis for Mitigating Strategy Assessment
- Section GA1 Assessment of Current FLEX Strategies (if necessary)
- Section GA2 Assessment for Modifying FLEX Strategies (if necessary)
- Section G.4.3 Assessment of Alternative Mitigating Strategies (if necessary)
- Section G.4.4 Assessment of Targeted Hazard Mitigating Strategies (if necessary)
In Reference 11, the NRC concluded that the "reevaluated flood hazards information, as summarized in Enclosure 1 [to Reference 11 ], is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049" for Braidwood Station, Units 1 and 2.
U.S. Nuclear Regulatory Commission Mitigating Strategies Flood Hazard Assessment (MSFHA) Submittal June 30, 2016 Page 3 The enclosure to this letter provides the Mitigating Strategies Assessments for Flooding Report for the Braidwood Station, Units 1 and 2. The assessment concluded that the current FLEX strategy can be deployed as designed. FLEX was designed for the current design basis Local Intense Precipitation (LIP) flood, which bounds the MSFHI for LIP. Site topography, cooling pond dike, and other features protect the plant and FLEX strategy from being impacted by non-bounding flood hazards associated with the Mazon River and cooling pond. Therefore, the current FLEX strategies can be successfully deployed as designed for all applicable flood-causing mechanisms and no further actions, including modifications to FLEX, are required.
This letter contains no new regulatory commitments. If you have any questions regarding this report, please contact David P. Helker at (610) 765-5525.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 30th day of June 2016.
Respectfully submitted, Glen T. Kaegi Director - Licensing & Regulatory Affairs Exelon Generation Company, LLC
Enclosure:
Braidwood Nuclear Power Station, Mitigating Strategies Assessments for Flooding Report, dated June 30, 2016 cc: Director, Office of Nuclear Reactor Regulation NRC Regional Administrator - Region III NRC Senior Resident Inspector Braidwood Station NRC Project Manager, NRR Braidwood Station Ms. Tekia Govan, NRR/JLD/JHMB, NRC Mr. John D. Hughey, NRR/JLD/JOMB, NRC Illinois Emergency Management Agency - Division of Nuclear Safety
Enclosure Braidwood Nuclear Power Station Mitigating Strategies Assessments for Flooding Report dated June 30, 2016 (9 Pages)
Mitigating Strategies Assessments for Flooding Braidwood Nuclear Power Station
=' Exelon.
June 30, 2016
"'W"Iraidwood MSA for***
- Page of 9 Contents 1 Executive Summary ............................................................................................. 3 2 List of Acronyms ................................................................................................. 3 3 Background ........................................................................................................ 4 3.1 Purpose ....................................................................................................... 4 3.2 Site Description ............................................................................................ 4 3.3 Overview of FLEX Strategy ............................................................................. 5 4 Characterization of MSFHI (NEI 12-06, Rev 2, Section G.2) ...................................... 5 5 Basis for Mitigating Strategy Assessment (NEI 12-06, Rev 2, Section G.3) ................. 6 6 Assessment of Current Flex Strategy (NEI 12-06, Rev 2, Section G.4.1) .................... 6 6.1 Assessment Methodology, Process, and Results ................................................ 6 6.2 Conclusions .................................................................................................. 7 7 References ......................................................................................................... 8
Blnn1dvvoodMSA for Flooding Page 3 of 9
~~~~~~0~~~1~~~~~~ Summa ry
~ Executive
~K The Braidwood Nuclear Power Stat i on (BNPS) FLEX design basis (DB) flood includes only the current design basis (CC`B) Local Intense Precipitation (LIP) event (localized Probable rnax1rnurn precipitation event). The Mitigating Strategies Rood Hazard Information (MSFHI), submitted with the Flood Hazard Reevaluation Report /FMRRl, showed that the CDB and / by relationship, the FLEX DB completely bounds the MSFHI for LIP. Therefore, a Mitigating Strategies Assessment (MSA) for LIP ls not required. Although the MSFHI for the Probable Maximum Flood (PMF) on the Cooling Pond and Mazon River were not bounded by the C[}B and FLEX [>B / the y4SAshovved that all aspects ofthe FLEX strategy, as designed, are protected (by plant grade for the Mazon River PMF and dike for the Cooling Pond PMF) from these non-bounded flood-causing mechanisms. No changes tothe FLEX strategy were required to address the MBFHI for all flood-causing mechanisms.
2 List of Acronyms w B[}BEE- Beyond Design Basis External Events w BNPS - Bnuldwmod Nuclear Power Station w CDB- Current Design Basis
- CNMT - Contolnrnent w OB - Des\gnBasls w ELAP - Extended Loss ofA/C Power w FHRR- Flood Hazard Reevaluation Report
- FLEX DB - FLEX Design Basis (flood hazard); the controlling flood parameters used to develop the FLEX flood strategies w LIP- Local Intense Precipitation
- LUHS - Loss of Ultimate Heat Sink w MSA - Mitigation Strategy Assessment w MSFHA- Mitigating Strategies Flood Hazard Assessment w MSFHI- Mitigating Strategies Flood Hazard Information
- MSL - MemnSea Level w NTTF- Near-Term Task Force w PMF- Probable Maximum Flood w SAFER - Strategic Alliance for FLEX Emergency Response w S0- Steam Generator w RCS - F\emctorCoolantSystenl w SI - Safety Injection
Braldvvood MSA for Flooding Page 4 of 9 3.1 Purpose On March 12 / 2012 / the NRC issued Reference 1 to request information associated with Near-Term Task Force Recommendation 2.1 for Flooding. One of the Required Responses in Reference 1 directed licensees to submit Flood Hazard Reevaluation Report. The BNP8 FMRRvvas submitted on March 12, 2014 /Reference 2l. Additional information was provided in References 3, 4 and 5. Per Reference 6, the NRC considers the reevaluated flood hazard tobe"beyondthe current design/licensing basis of operating plonts".
Concurrent to the flood hazard reevaluation, BNP8 developed and implemented mitigating strategies in accordance with NRCC}rder EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond- [}eslgn-Basis External Events". In Reference 7, the Commission recommended that licensees need to address the reevaluated flooding hazards within their rnlt1QaUng strategies for B[)BEEs. This requirement was confirmed by the NRC in Reference 0. Guidance for performing MSFHAs is contained in Appendix G of Reference 9 / endorsed by the NRC in Reference 10. For the purpose of the y4SFHAsand in Reference 8, the NRCterrned the reevaluated flood hazard, summarized in References 11 / as the '"Mitigating Strategies Flood Hazard Inforrnatlon". Reference Q, Appendix G, describes the MGFHA for flooding as containing the following elements:
- Section C].2- Characterization of the MSFHI w Section G.3- Basis for Mitigating Strategy Assessment w Section G.4.1 - Assessment of Current FLEX Strategies (if necessary)
- Section G.4.2 - Assessment for Modifying FLEX Strategies (if necessary)
- Section G.4.3 - Assessment of Alternative Mitigating Strategies /lf necessary) w Section {;.4.4 - Assessment of Targeted Hazard Mitigating Strategies (l[ necessary)
If a Section G.3 assessment shows that the FLEX DB flood completely bounds the reevaluated flood /M8PHIl, only documentation for Sections G.2 and G.3 are required; assessments and documentation for the remaining sections (G.4.1 through G.4.4) are not necessary.
3.2 Site Description B0P8 is located in the southwestern portion of Will County, 1.5 rnlles southwest of the City ofBroldvvood, Illinois. The Kankakee River is approximately 4.5 rn1les Northeast ofB0PS vvhlle the y4azon River is approximately one rn1le Southwest of the site.
Condenser water is cooled by water supplied by m cooling pond. The surface area of the cooling pond at its normal pool elevation of 595 ft y4SL is 2,475 acres (USFAR Subsection 2.4.1.1). The pond is impounded by constructed exterior dikes with the top of the dike elevation varying from 600.0 to 602.5 ft MSL (USFAR Subsection 2.4.1.1). Makeup water for the cooling pond ls pumped from the Kankakee River. Blovvdovvn water lsdischarged from the plant by pipeline to the outfall structure and then to the discharge flume into the Kankakee River.
The nominal plant grade and floor elevations are 600.0 ft MSL and 601.0 ft MSL, respectively (USFARSubsectlon 2.4.2.3).
The plant grade elevation (600.0 ft MSL) is 5ft above the normal pool elevation in the cooling pond, equal to5Q5.OftMSL(USFAR Subsection 2.4.1.1).The site plant grade elevation is 2Oft above the mean water level in Lake Michigan, equal to approximately 580 ft y4SL(F(eference 13).
Braidwood MSA for Flooding Page 5 of 9 3.3 Overview of FLEX Strategy The FLEX strategy was developed to mitigate an ELAP and LUHS concurrent with an external even[ (i.e. flood, earthquake / tornado / etc.).
Redundant 350kW diesel generators can provide the power required for vital instrumentation and all FLEX equipment. The FLEX diesel fuel supply ls two 25 / OOOgallon tanks (Unit 1) or one 50,000 gallon tank (Unit 2) which would not be adversely affected by o flooding event.
Control room indications ofvital instruments (including core temperature, RCS pressure, Pressurizer level, SG water level and SG pressure, Post-Accident Neutron Monitor, Reactor Vessel Level, and CNMl[ Pressure) are initially powered by the station batteries and eventually by the FLEX diesel generators.
Core cooling is maintained by ensuring adequate RCS inventory for RCS natural circulation with S{] heat removal. 80 Feedvvmterls provided by either the Diesel Driven Auxiliary Feedvvmter pump orthe Medium Pressure FLEX pump. RCS inventory is maintained lnldally by the SI accumulator then by the High Head FLEX pump. SG Steam relief is through the Atmospheric Dump Valves.
Condensate for SG feedvvaterls obtained from the Condensate Storage Tanks, orthe Ultimate Heat Sink.
Sufficient diesel oil fuel reserves are onsite to support more than 3O days ofisolated operation. SAFER can air lift fuel and effectively maintain a diesel fuel supply indefinitely.
The Refueling Water Storage Tank provides the source for RCS makeup and will not be affected by site flood event. A boratlon skid from the National SAFER Response Center will provide a long term bonntlon and makeup source.
The FLEX strategy is fully integrated within the emergency procedure architecture. The Emergency Operating Procedures provides the primary direction for mitigation of the ELAP.
The Emergency Support Procedures provide specific guidance for task needed to implement the mitigation strategy. The Abnormal Event Operating Procedures provide event specific guidance for floods, earthquake, tornado, etc.
4 Characterization of MSFHI (NEI 12-06,, Rev 2,, Section NRC has completed the ""Interim Staff Response to Reevaluated Rood Hazards" submitted in the BNPB FHRR /Reference 2l. In Reference 11, the NRC concluded that ""the licensee's reevaluated flood hazards information, as summarized in Enclosure 1 [of Reference 11], is suitable for the assessment of mitigating strategies." Enclosure 1 of Reference 11 includes Table 1 and Table 2 that summarize the current design basis and reevaluated flood hazard parameters, respectively. In Table 1 of Reference 11, Enclosure 1, the NRC lists the following flood-causing mechanisms for the current design basis flood:
w Local Intense Precipitation; w Streams and Rivers (Py4Fon the Cooling Pond and Mazon River);
w Failure of Dams and [)ns1to VVaterControl/Stormge Structures; w Storm Surge; w Selche)
- Tsunami; w Ice Induced Flooding; and
BrmldvvoodMSA for Flooding Page 6of9
- Channel Migrations/Diversions.
In Table 2 of Reference 11, Enclosure 1, the 0RC lists "'Streams and Rivers (PMF on the Cooling Pond and Mazon River)" as the only reevaluated flood-causing mechanism that should be addressed in the MSA. The pMF for this mechanism is based on NUREG/CR-7046 /
Section H.1 precipitation event combinations with hydrologic dam failure. Per Note 2 of Table 2 / Enclosure 1, Reference 11, ""reevaluated hazard mechanisms bounded by the current design basis are not included in this table". A more detailed description of this reevaluated flood-causing mechanism,, along with the basis for inputs / assumptions, methodologies, and models, is provided in Section 3.2 and 3.3 of Reference 2 / Enclosure 1.
Also, Combined-Effect floods and a summary of resulting flood parameters related to the "Streams and Rivers" flood-causing mechanism are provided in Sections 3.6 and 4.0 /
respectively, of Reference 2, Enclosure 1. Additional information is provided in References 3 / 4/ and 5 (responses to requests for additional information). Specifically, Enclosure 2 of Reference 5 contains updated flood hazard reevaluation information, specifically for the LIP, Storm Surge, Saiohe / Tsunami,, and Combined-Effects flood-causing mechanisms. As indicated in Reference 5, the updated flood hazard parameters are bounded by the original FHRR submittal (Reference 2). Enclosure 1, Table 2 of the NRC's interim response letter (Reference 11) contains results from the updated submittal in Reference 5.
5 Basis for Mitigating Strategy Assessment (NEI 12-06, Rev 2 Section G 3)
For BNPS, Units 1 hk2 / the FLEX DB flood, described in Reference 12, ls equivalent tothe plant's COB flood for LIP event of 601.91 ft MSL. As indicated in Section 4 of Reference 5, / the MSFHI is completely bounded by the COB and, by relationship, FLEX DB for LIP. This is affirmed by the 0RC in Reference 11. Therefore, no further assessment of FLEX for LIP flooding are required or included in the MSA.
The FLEX OB did not consider flood-causing mechanisms other than LIP and,, as a result, not bound the MSPHI. As indicated in Section 4, only the "Streams and Rivers (PMF on the Cooling Pond and Mazon River)", and related Corn b1ned-Effects, flood-causing mechanism should be addressed in the MSA. Therefore,, since this mechanism (""Streams and Rivers" (PMF on the Cooling Pond and Mazon River)) is not bounded by the FLEX DB, further assessment of FLEX for this mechanism is included in Section 8.
6 Assessment of Current Flex Strategy (NEI 12-06, Rev 6.1 Assessment Methodology, Process, and Results For the Mazon River PMF (based on the NUREG/CR-7046, Section H.1 / event combinations with hydrologic dam failure), both the reevaluated rnaxlrnurn stlllvvoterelevatlon (594.25-ft MSL] and wind-wave runup elevation (595.83-ft M8L), per Table 4.3 of Reference 5 (Enclosure 2), are not bounded by the CO8 and, because of its exclusion, the FLEX OB. Site topography provides m reliable permanent and passive flood protection barrier for this flood-causing rneohmnlsnn, a rnlnlrnurn of 4.17 feet ofavailable margin above the wind-wave runup flood elevation of 595.83-ft MGL. A"Llrnlted Integrated Assessment for External Flooding"' report, included with the FHRRsubrnlttal (Enclosure 2, Reference 2), determined that site topography is reliable and has adequate margin in providing flood protection to
Braidwood MSA for Flooding Page 7 of 9 plant grade elevation 6004t MSL for the Mazon River PMF. [Gee Section 5.1 of Reference 2, Enclosure 2.)
For the Cooling Pond PMF /based on the 0UREG/CR-7046, Section H.1, event combinations with hydrologic darn failure),, only the reevaluated rnaxlrnunn stlUvvmter elevation (599.364t MSL], per Table 4.4 of Reference 5, is not bounded by the CDB and / because of its exclusion, the FLEX C`B. The reevaluated maximum wind-wave runup elevation (601.08-ft y4SL\ / per Table 4.5 of Reference 5 (Enclosure 2) / is bounded by the CDBwind-wave runup elevation [602.34-ft MSQ. The Cooling Pond is impounded by on exterior dike with the Lop elevation varying from 600.0-ft MSL to 602.5-ft MSL. The northern section of the dike at elevation 602.5-ft MSL was designed to protect the plant from wind-wave runup.
The "Limited Integrated Assessment for External Hoodlng" report, included with the FHRR submittal (Enclosure 2, Reference 2), identified three flood protection features for the Cooling Pond; site topography (plant grade) and slurry trench (stlllvvater) / northern dike system (wind-wave runup), and protection against ingress through Essential Service Water Discharge and Circulating Water Discharge pipe pathways (stillvvater) and showed that these features are reliable and have adequate margin in providing flood protection for the Cooling Pond flood-causing mechanisms. (See Section 5.2 of Reference 2 / Enclosure 2.)
The only portion of the FLEX strategy not protected by the dike is the deployment location of the low pressure pumps at the lake screen house. The location of the pump will be at elevation 602.83-ft MSL (Reference 14). This exceeds the C[>B and MGpHI for wind-wave runup so no further evaluation is required. Otherwise, the FLEX strategy, as designed, can be successfully executed since:
- All FLEX equipment is stored, and therefore protected / at above elevation 802-ft MSL (Reference 12);
w All equipment relied on for the FLEX Strategy below elevation 800-ft MSL is located within Safety-Related Buildings passively protected from flooding by reinforced concrete curbs or steel barriers (UFBAR 2.4.2.3);
- All manual actions and haul routes are located at and above grade elevation 800-ft MSL (UFSAR2.4.2.3); and
- All FLEX connection points at or be/ow elevation 600-ft MSL are within m Safety-Related Buildings passively protected from flooding by reinforced concrete curbs or steel barriers (UF8AR2.4.2.3).
Reference 2, Enclosure 2 also satisfies the performance criteria for flood protection in Section G.5 ofNEI 12-08 / Rev 2, Appendix (Reference 9), including below-grade walls and seals, for FLEX equipment, connection points, etc. located below elevation of 600-ft MSL As indicated in Reference 2, Enclosure 2, the COB forB0PS assumes groundwater level at plant grade. Adequacy of below-grade CDB plugs and penetration seals were addressed with the 0TTFRecornnnendatlon 2.3 Flooding VValkdowns(Reference 15@k18).
6.2 Conclusions FLEX was designed for BNPGis CDB LIP flood, vvhloh bounds the MSFHI for LIP. Site topography/ cooling pond dike, and other features (discussed above) protect the plant and FLEX strategy from being impacted by non-bounding flood hazards associated with the Mazon River and Cooling Pond. Therefore, the current FLEX strategies can be successfully deployed as designed for all applicable flood-causing mechanisms and no further actions,
Braidwood MSA for Flooding Page 8 of 9
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident; dated March 12, 2012.
- 2. Exelon Generation Company, LLC Letter to USNRC, Response to March 12, 2012 Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flooding Hazard Reevaluation Report, dated March 12, 2014 (RS 052)
- 3. Exelon Generation Company, LLC Letter to USNRC, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report, dated July 14, 2014 (RS-14-194).
- 4. Exelon Generation Company, LLC Letter to USNRC, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report, dated February 17, 2015 (RS-15-050).
- 5. Exelon Generation Company, LLC Letter to USNRC, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report, dated June 24, 2015 (RS-15-112).
- 6. NRC Letter, Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 1, 2013.
- 7. NRC Staff Requirements Memoranda to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards", dated March 30, 2015.
- 8. NRC Letter, Coordination of Requests for Information Regarding Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events, dated September 1, 2015.
- 9. Nuclear Energy Institute (NEI), Report NEI 12-06 [Rev 2], Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, dated December 2015.
- 10. U.S. Nuclear Regulatory Commission, JLD-ISG-2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events, dated January 22, 2016 [Effective February 29, 2016 per Federal Register / Vol. 81, No. 39].
- 11. NRC Letter to Exelon, "Braidwood Station, Unit 1 and 2 - Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanisms Reevaluation (TAC NOS. MF3895 and MF3896),
dated September 3, 2015 (ADAMS ML16091A091).
Braidwood MSA for Flooding Page 9 of 9
- 12. CC-BR-118-1001, REV. 01 "Site Implementation of Diverse and Flexible Coping Strategies (FLEX) and Spent Fuel Pool Instrumentation Program".
- 13. U.S Army Corps of Engineers,, Detroit District, Great Lakes Water Levels website, available at http://w3.lre.usace.army.mil/hh/GreatLakesWaterLevels/GLWL-CurrentMonth-Feet.pdf, accessed June 2016.
- 14. Drawing A-512, Rev. AM "Lake Screen House Floor Plan EL. 602-10 Area 1."
- 15. Exelon Generation Company, LLC Letter to USNRC, Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated November 27, 2012 (RS-12-160).
- 16. Exelon Generation Company, LLC Letter to USNRC, Supplemental Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated January 13, 2014 (RS-14-005).