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Category:Report
MONTHYEARRS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies 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-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel SVP-21-041, Regulatory Commitment Change Summary Report2021-07-15015 July 2021 Regulatory Commitment Change Summary Report 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 ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting SVP-20-074, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report2020-10-0808 October 2020 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report RS-20-086, Renewed Facility Operating License Nos. DPR-29 and DPR-302020-09-24024 September 2020 Renewed Facility Operating License Nos. DPR-29 and DPR-30 ML19168A1962019-08-29029 August 2019 Staff Assessment of Flood Hazard Integrated Assessment RS-19-049, Submittal of 10 CFR 50.46 Annual Report2019-05-0202 May 2019 Submittal of 10 CFR 50.46 Annual Report ML19064B3712019-03-0505 March 2019 Enclosure B - QDC-0000-N-1481, Revision 3, Quad Cities Units 1 & 2 Post-LOCA Eab, LPZ, and CR Dose - AST Analysis. ML19064B3702019-03-0505 March 2019 Enclosure a - QDC-7500-M-2341, Revision 0, Quad Cities Units 1 & 2 Secondary Containment Drawdown Analysis. SVP-19-002, Submittal of 10 CFR 50.59, 10 CFR 72.48 Summary Report2019-01-0404 January 2019 Submittal of 10 CFR 50.59, 10 CFR 72.48 Summary Report RS-18-089, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109)2018-08-14014 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109) RS-18-087, 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)2018-08-14014 August 2018 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-18-048, Submittal of 10 CFR 50.46 Annual Report Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors.2018-05-0202 May 2018 Submittal of 10 CFR 50.46 Annual Report Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors. SVP-17-046, Regulatory Commitment Change Summary Report2017-07-0606 July 2017 Regulatory Commitment Change Summary Report ML16271A3242016-10-31031 October 2016 Technical Review Documentation for Flooding Hazard Reevaluation of Quad Cities Nuclear Power Station, Units 1 and 2 RS-16-044, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-19019 February 2016 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. ML15309A4932016-02-10010 February 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 2.1 of the Near-Term Task Force ML15251A3842015-08-31031 August 2015 Attachment 9 - NP-3305NP, Revision 1, Mechanical Design Report for Quad Cities and Dresden Atrium 10XN Fuel Assemblies - Licensing Report. (Non-Proprietary) SVP-15-052, Submittal of Regulatory Commitment Change Summary Report2015-07-0808 July 2015 Submittal of Regulatory Commitment Change Summary Report RS-15-085, Provides Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentaiton (Order Number EA-12-051)2015-05-0707 May 2015 Provides Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentaiton (Order Number EA-12-051) RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 SVP-14-057, Owner'S Activity Report Submittal Fifth 10 Year Interval 2014 Refueling Outage Activities2014-08-0101 August 2014 Owner'S Activity Report Submittal Fifth 10 Year Interval 2014 Refueling Outage Activities ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14101A2282014-04-0707 April 2014 Holtec International Report No. HI-2125245, Revision 5, Licensing Report for Quad Cities Criticality Analysis for Inserts. RS-14-072, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights..2014-03-31031 March 2014 Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights.. RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. ML13317A9572013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Quad Cities Nuclear Power Station, TAC Nos.: MF1048 and MF1049 ML13199A0382013-07-16016 July 2013 Attachment 5 - Holtec International Report No. HI-2125245, Revision 2, Licensing Report for Quad Cities Criticality Analysis for Inserts - Non Proprietary Version 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 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 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 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 SVP-13-001, Summary Report of Completed Changes, Tests and Experiments for January 2011 - December 20122013-01-0404 January 2013 Summary Report of Completed Changes, Tests and Experiments for January 2011 - December 2012 ML12361A1002012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 1 of 10 ML12361A0952012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 12 of 15 ML12361A0942012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 11 of 15 ML12361A0932012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 10 of 15 2024-05-06
[Table view] Category:Technical
MONTHYEARRS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies 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-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel 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 SVP-20-074, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report2020-10-0808 October 2020 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report RS-20-086, Renewed Facility Operating License Nos. DPR-29 and DPR-302020-09-24024 September 2020 Renewed Facility Operating License Nos. DPR-29 and DPR-30 RS-19-049, Submittal of 10 CFR 50.46 Annual Report2019-05-0202 May 2019 Submittal of 10 CFR 50.46 Annual Report ML19064B3702019-03-0505 March 2019 Enclosure a - QDC-7500-M-2341, Revision 0, Quad Cities Units 1 & 2 Secondary Containment Drawdown Analysis. ML19064B3712019-03-0505 March 2019 Enclosure B - QDC-0000-N-1481, Revision 3, Quad Cities Units 1 & 2 Post-LOCA Eab, LPZ, and CR Dose - AST Analysis. RS-18-089, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109)2018-08-14014 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109) RS-18-087, 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)2018-08-14014 August 2018 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) ML16271A3242016-10-31031 October 2016 Technical Review Documentation for Flooding Hazard Reevaluation of Quad Cities Nuclear Power Station, Units 1 and 2 ML15251A3842015-08-31031 August 2015 Attachment 9 - NP-3305NP, Revision 1, Mechanical Design Report for Quad Cities and Dresden Atrium 10XN Fuel Assemblies - Licensing Report. (Non-Proprietary) RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14101A2282014-04-0707 April 2014 Holtec International Report No. HI-2125245, Revision 5, Licensing Report for Quad Cities Criticality Analysis for Inserts. RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. ML13317A9572013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Quad Cities Nuclear Power Station, TAC Nos.: MF1048 and MF1049 ML13199A0382013-07-16016 July 2013 Attachment 5 - Holtec International Report No. HI-2125245, Revision 2, Licensing Report for Quad Cities Criticality Analysis for Inserts - Non Proprietary Version ML12361A0932012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 10 of 15 ML12361A0862012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 4 of 15 ML12361A0872012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 5 of 15 ML12361A0892012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 6 of 15 ML12361A0902012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 7 of 15 ML12361A0912012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 8 of 15 ML12361A0922012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 9 of 15 ML12361A0952012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 12 of 15 ML12361A1102012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 10 of 10 ML12361A1112012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 1 of 15 ML12361A1092012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 9 of 10 ML12361A1082012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 8 of 10 ML12361A1072012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 7 of 10 ML12361A1122012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 2 of 15 RS-12-169, Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 3 of 152012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 3 of 15 ML12361A1062012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 6 of 10 ML12361A0942012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 11 of 15 ML12361A1052012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 5 of 10 ML12361A1042012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 4 of 10 ML12361A1032012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 3 of 10 ML12361A1012012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 2 of 10 ML12361A1002012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 1 of 10 ML12361A0992012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 15 of 15 ML12361A0982012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 14 of 15 ML12361A0962012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 13 of 15 ML13199A0392009-07-30030 July 2009 Attachment 8 - Netco Report NET-259-03, Revision 5, Material Qualification of Alcan Composite for Spent Fuel Storage ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 RS-07-157, Request for Technical Specification Change for Minimum Power Ratio Safety Limit2007-11-20020 November 2007 Request for Technical Specification Change for Minimum Power Ratio Safety Limit SVP-07-027, 90-Day Post Outage ISI Letter, Dated July 14, 20062007-05-0505 May 2007 90-Day Post Outage ISI Letter, Dated July 14, 2006 2024-05-06
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ENCLOSURE 2 Attachment 8 C.D.I. Technical Note No. 05-34,"Test Condition TC15a Load Comparison for Quad Cities Unit 1," Revision 0, dated August 2005
C.D.I. Technical Note No. 05-34 Test Condition TC I5a Load Comparison for Quad Cities Unit I Revision 0 Prepared by Continuum Dynamics, Inc.
34 Lexington Avenue Ewing, NJ 08618 Prepared under Purchase Order No. 85758 for Exelon Generation LLC 4300 Winfield Road Warrenville, IL 60555 Approved by 014 Alan J. Bilanin R
August 2005
SUMMAR Y To date, two high resolution loads have been developed for Quad Cities Unit I (QCI) at Test Condition TCI5a, as shown below.
Test Condition Strain Gage (SG) Correction Acoustic Circuit Model Identifier Technique Used TC15a Reduced 80 Hz on C main Minimum Error Model steam line, averaged single SG S32/S34 with SG pair S3 1/S33 on C main steam line only TC15a-2 Reduced 80 Hz on A and C Modified Benchmark main steam lines, averaged Model single SG with SG pairs for all failed strain gage locations Justification for reducing the 80 Hz frequency peak (+/- 4 Hz on either side) may be found in [1],
while justification for averaging a single strain gage with a corresponding strain gage pair may be found in [2]. A description of the Modified Benchmark and the Minimum Error models may be found in [3].
C.D.I. has been asked by Exelon to develop the QCI high resolution load Test Condition Strain Gage (SG) Correction Acoustic Circuit Model Identifier Technique Used TC15a-3 Reduced 80 Hz on A and C Minimum Error Model main steam lines, averaged single SG with SG pairs for all failed strain gage locations and compare its predictions against TC15a, the other Minimum Error model. This report summarizes the low resolution results for TC15a_3 compared against TC I5a, in preparation for delivery of a high resolution load for structural analysis.
MODELING RESULTS Table I compares the minimum, maximum, and RMS pressure levels for TC15a_3 and TCl5a at 27 locations on the QCI dryer. Also included in this table is the comparison for two sensor differences from the outside to the inside of the outer bank hoods at the same location: P3 - P13 (the A-B side of the dryer) and P20 - P14 (the C-D side of the dryer). Figure I plots the values presented in Table 1.
A comparison of these values at the 27 locations shows that the differences between the two load cases translate into an average reduction of the minimum pressure by 0.066 psid (the average minimum pressure in TCI5a_3 is less minimum than the average minimum pressure in TCI5a),
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an average reduction of the maximum pressure by 0.027 psid (the average maximum pressure in TCl5a_3 is less maximum than the average maximum pressure in TC15a), and an average increase of the RMS pressure of 0.002 psid (the RMS pressure in TC15a_3 is slightly larger than the RMS pressure in TCI5a).
Correspondingly, for the pressure difference P3 - P13, the minimum pressure in TC15a_3 is less minimum than the minimum pressure in TC15a (by 0.056 psid), the maximum pressure in TC15a_3 is larger than the maximum pressure in TCI5a (by 0.021 psid), and the RMS pressure in TC15a_3 is smaller than the RMS pressure in TC15a (by 0.042 psid). For the pressure difference P20 - P14, the minimum pressure in TC15a_3 is more minimum than the minimum pressure in TCI5a (by 0.161 psid), the maximum pressure in TC15a_3 is larger than the maximum pressure in TC15a (by 0.219 psid), and the RMS pressure in TC15a_3 is larger than the RMS pressure in TCI5a (by 0.056 psid).
Figures 2 to 28 show the PSD comparisons for locations P1 to P27. Figures 29 and 30 show the PSD comparisons for P3 - P13 and P20 - P14, respectively. It is seen that the two load cases are very similar, with a noticeable, yet slight, 80 Hz signal in TC15a (possibly resulting from the fact that no adjustment was made to the A main steam line strain gage data).
REFERENCES
- 1. Exelon Generation Company. 2005. QCI Evaluation to Remove 80 Hz from Strain Gage Data. White Paper.
- 2. Structural Integrity Associates, Inc. 2005. Quad Cities Unit 1 Main Steam Line Strain Gage Reductions. Letter Report No. SIR-05-208 Revision 2 (draft), KKF-05-034.
- 3. Continuum Dynamics, Inc. 2005. Evaluation of Continuum Dynamics, Inc. Steam Dryer Load Methodology Against Quad Cities Unit 2 In-Plant Data. C.D.I. Report No. 05-10.
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Table 1. Summary of pressure predictions at 27 sensors on the QCI dryer, based on the first 65 seconds of data collected.
Pressure TC15a TC15a TCISa TC15a_3 TC15a_3 TC15a_3 Sensor Minimum Maximum RMS Minimum Maximum RMS Number (psid) (psid) (psid) (psid) (psid) (psid)
P1 -1.342 1.341 0.438 -1.355 1.440 0.464 P2 -1.028 1.010 0.224 -1.121 1.140 0.270 P3 -1.938 1.830 0.504 -1.776 1.688 0.467 P4 -0.723 0.755 0.177 -0.777 0.728 0.182 P5 -1.038 0.813 0.199 -0.766 0.799 0.194 P6 -1.301 1.267 0.347 -1.164 1.171 0.312 P7 -1.054 1.038 0.338 -1.125 1.179 0.386 P8 -0.837 0.809 0.182 -0.678 0.713 0.161 P9 -1.674 1.695 0.510 -1.550 1.562 0.518 P1O -1.322 1.364 0.436 -1.361 1.393 0.458 Pl1 -0.946 0.866 0.209 -0.789 0.848 0.193 P12 -2.335 2.231 0.678 -2.069 2.116 0.741 P13 -0.549 0.403 0.106 -0.355 0.343 0.087 P14 -0.461 0.512 0.114 -0.452 0.489 0.106 P15 -2.027 1.896 0.569 -2.012 1.882 0.572 P16 -0.366 0.289 0.078 -0.304 0.262 0.063 P17 -1.160 1.135 0.275 -1.112 1.014 0.287 P18 -1.691 1.696 0.501 -1.617 1.701 0.517 P19 -1.986 1.894 0.589 -2.031 1.941 0.613 P20 -3.342 3.621 1.075 -3.503 3.781 1.124 P21 -1.641 1.461 0.407 -1.503 1.462 0.395 P22 -1.439 1.527 0.435 -1.407 1.351 0.445 P23 -0.332 0.257 0.073 -0.251 0.204 0.056 P24 -1.138 1.193 0.280 -1.029 1.125 0.257 P25 -1.342 1.348 0.328 -1.260 1.258 0.295 P26 -0.294 0.280 0.077 -0.238 0.245 0.064 P27 -0.335 0.285 0.074 -0.242 0.231 0.059 Average -1.246 1.215 0.342 -1.180 1.188 0.344 P3-P13 -1.984 1.952 0.553 -1.928 1.973 0.511 P20 - P14 -3.660 3.877 1.148 -3.821 4.096 1.204 4
0
.7:1..q cn -0.5 15 (1)
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-1 rn -1.5 cn (1)
-2 9Lq
-2.5 9
E -3
.-O -3.5 I -4 0 5 10 15 20 25 30 Pressure Sensor Number Figure la. Comparison between TC15a and TC 15a_3 (minimum pressure). Pressure sensor number P28 = P3 - P13, while pressure sensor number P29 = P20 - P14.
4 co a.)
3
- .4
- X
- 2 Gn 1
0 0 5 10 15 20 25 30 Pressure Sensor Number Figure lb. Comparison between TC15a and TC15a_3 (maximum pressure). Pressure sensor number P28 = P3 - P13, while pressure sensor number P29 = P20 - P14.
5 cof
1.4 1.2 c)O 1 0.8 en 0.6 :;
0.4 0.2 0
0 5 10 15 20 25 30 Pressure Sensor Number Figure ic. Comparison between TC15a and TC15a_3 (RMS pressure). Pressure sensor number P28 = P3 - P13, while pressure sensor number P29 = P20 - P14.
0.1 0.01 N
-o 0.001
- 44 0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 2. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number PI.
6
0.1 0.01 N
t1 C14 7.-
0.001 4
Cn I-0.0001 V)
P--
10 5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 3. PSD comparison between TCI5a (black curve) and TCI5a_3 (blue curve) for pressure sensor number P2.
0.1 0.01 N
0.001
10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 4. PSD comparison between TC15a (black curve) and TCl5a_3 (blue curve) for pressure sensor number P3.
7 CO)
0.01 N 0.001
-o 0.0001 crA 10-5 10-6 1 QI . . . i 0 51 200 Figure 5. PSD comparison between TC15a (black curve) and TCl5a 3 (blue curve) for pressure sensor number P4.
0.01 N 0.001
.1 0.0001 car V) 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 6. PSD comparison between TCl5a (black curve) and TC15a_3 (blue curve) for pressure sensor number P5.
8 CO'f
I 0.1 0.01 N
0.001 C,'
0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 7. PSD comparison between TC 15a (black curve) and TCI 5a_3 (blue curve) for pressure sensor number P6.
0.1 0.01 N
0.001 C,4 0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 8. PSD comparison between TC15a (black curve) and TCl5a_3 (blue curve) for pressure sensor number P7.
9 c o5>
0.01 N 0.001 rA 0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 9. PSD comparison between TC15a (black curve) and TC 15a3 (blue curve) for pressure sensor number P8.
0.1 0.01 N
VC 0.001 P-o 0.0001 10 10-6 0 50 100 150 200 Frequency (Hz)
Figure 10. PSD comparison between TC15a (black curve) and TCI'5a_3 (blue curve) for pressure sensor number P9.
10 COO(
0.1 0.01
- - 0.00 1 v: 0.0001 10-5 10-6 1 V . . I ._I 0 50 100 150 200 Frequency( 'Hz)
Figure 11. PSD comparison between TC 15a (black curve) and TC 15a3 (blue curve) for pressure sensor number PIO.
0.01 I I I I I I I I I I I N 0.001 t-
".r co--
0.0001 o
10 10-6 0 50 100 150 200 Frequency (Hz)
Figure 12. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P11.
11 co(
1 0.1 N
-11 0.01 0.001 P-4 0.0001 10-5 10-6 t , I . . . . . .
0 50 100 150 200 Frequency((Hz)
Figure 13. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P12.
0.001 7 I l 1 i I I I I I I N 0.0001 u-L: 10o 0-6 10-7 0 50 100 150 200 Frequency (Hz)
Figure 14. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P13.
12 co%
0.01 0.001 N
-o,7: 0.0001 ci: 10-5 10-6 0-7 1 , - I I I I I I I 0 50 100 150 200 Frequency( (Hz)
Figure 15. PSD comparison between TC15a (black curve) and TC 15a3 (blue curve) for pressure sensor number P14.
0.1 0.01 N
0.001 ma 0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 16. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P1 5.
13 COQ
0.001 N 0.0001 C-4
- n 10-5 10-6 10-7 0 50 1100 150 200 Freque ncy (Hz)
Figure 17. PSD comparison between TC15a (black curve) and TC 15a3 (blue curve) for pressure sensor number P 16.
0.1 0.01 N
0.001 t-.
0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 18. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P17.
14 CIO
0.1 0.01 N
0.001 1=4 0.0001 U)
A- 10-5 10-6 10-7 0 50 100 150 200 Frequency (Hz)
Figure 19. PSD comparison between TC15a (black curve) and TC 15a_3 (blue curve) for pressure sensor number P18.
0.1 0.01 N
0.001 7:$
0.0001 10-5 V:
10-6 10-7 0 50 100 150 200 Frequency (Hz)
Figure 20. PSD comparison between TC 15a (black curve) and TC I a_3 (blue curve) for pressure sensor number P19.
15 C11
1 0.1 N
0.01
"-C
.1-Cnt 0.001 1: 0.0001 10 10-6 0 50 100 150 200 Frequency (Hz)
Figure 21. PSD comparison between TC 15a (black curve) and TC 15a 3 (blue curve) for pressure sensor number P20.
0.1 0.01 N
.-e 0.00 1 0.0001 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 22. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P2 1.
16
0.1 0.01 N
0.001 C4 0.0001 v:
10-5 1 0 -6 1 . . . . I . ' I . . . . I I I I I I 0 50 100 150 200 Frequency (Hz)
Figure 23. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P22.
0.001 0.0001 N
10-5 co~
10-6 10-7 10-8 0 50 100 150 200 Frequency (Hz)
Figure 24. PSD comparison between TC15a (black curve) and TC 15a_3 (blue curve) for pressure sensor number P23.
17
0.1 0.01 N
0.001
C"4 0.0001 v:
10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 25. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P24.
0.01 N 0.001 0.0001 ca V:O 10 10-6 0 50 100 150 200 Frequency (Hz)
Figure 26. PSD comparison between TC15a (black curve) and TCl5a-3 (blue curve) for pressure sensor number P25.
18
0.001 N 0.0001 is
- C 10o AL4 10-6 10-7 1 Y I I I I 1 V I I I I I 0 50 100 200 Frequency (Hz' Figure 27. PSD comparison between TC15a (black curve) and TC 15a3 (blue curve) for pressure sensor number P26.
0.001 I ' I I 0.0001 N
10-5 Cl4 P-e 10-6 10-7 10-8 0 100 200 Frequency (Hz)
Figure 28. PSD comparison between TC15a (black curve) and TC15a_3 (blue curve) for pressure sensor number P27.
19
I 0.1 0.01 N
0.001 coi 0.0001 v::
10o 10-6 0 50 100 150 200 Frequency (Hz)
Figure 29. PSD comparison between TC15a (black curve) and TC15a 3 (blue curve) for the difference between pressure sensor number P3 and pressure sensor number PI3.
1 0.1 N
".O 0.01
.- 4 Qn 0.001 CO aCn 0.0001 0-4 10-5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 30. PSD comparison between TC15a (black curve) and TC15a 3 (blue curve) for the difference between pressure sensor number P20 and pressure sensor number P14.
20