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Category:Report
MONTHYEARRS-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-18-087, 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-18-089, 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-18-048, 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 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 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 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 2022-07-13
[Table view] Category:Technical
MONTHYEARRS-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 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. 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 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 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 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 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 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 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 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 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 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 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 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 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 LR-N07-0034, C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions.2007-01-31031 January 2007 C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier 2022-07-13
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ENCLOSURE 2 Attachment 3 Exelon Report Number AM-2005-003, "Engineering Evaluation of Reduced Strain Gage Data Sets on the Quad Cities Unit 1 Test Condition 15A," dated June 29, 2005
Engineering Evaluation of Reduced Strain Gage Data Sets on the Quad Cities Unit 1 Test Condition 15A Document Number A M-2005-003 Nuclear Engineering Department Exelon Nuclear Generating Co.
Prepared by: VLI 4? -I-Kevin B. Ramsden Date: ____/ _ _9 _
Reviewed by: /
Date: 7/z>7/
Approved by: .0Ptut Gi 2 . Date: 6_______
(Date Issued)
Report No. AM-2005-003, Rcvision 0 Abstract This report documents the data review and engineering judgments applied to the strain gage data taken at QC1 during Test Condition 15A. The failure of 5 strain gages on 3 steam lines has been determined to have the potential to introduce erroneous pressure information into the Acoustic Circuit Model. The steps taken to confirm and appropriately address this condition are the principal content of this report.
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Report No. AM-2005-003, Rcvision 0 Abstract...........................................................................................................................1
- 1. Introduction ............................................... 3
- 2. Methodology ............................................... 4 2.1 CDI Acoustic Circuit Analysis .............................................. 4 2.2 QC 1 Test Condition 15A Description ............................................. 4 2.2.1 Power level ............................................... 4 2.2.2 MSL Strain Gauge Inputs: ............................................. 4 2.2.3 In-Vessel Instrumentation ............................................ 5 2.1.1 Additional MSL Instrumentation ............................................. 5
- 3. Calculations .............................................. 6 3.1 Calculation Approach ....... 6......................
- 4. Results .............................................. 7 4.1 Observations from the U-2 790 MWe Blind Comparison and Model Correction 7 4.1.1 Model Configuration .............................................. 7 4.1.2 Comparison of the Blind to the Revised Case ........................................ 7 4.2 Unit 1 TC 15A C MSL Single SG Pair Prediction .............................................. 7 4.3 Vessel Level Sensor Pressure Tap Data ........................... .................... 8 4.4 C MSL 624' Elevation Data ............................................. 8 4.5 C MSL Accelerometer Data ............................................. 8
- 5. Conclusions/Discussion .............................................. 9
- 6. References............................................................................................................. 10 2 of 22
Report No. AM-2005-003, Revision 0
- 1. Introduction This report documents the evaluation performed and engineering judgments applied to the QC1 Test Condition 15A strain gage data, used as input information to the Acoustic Circuit Models. Specifically, the failure of 5 strain gages in 3 of the steam lines (A,B, and C) yielded a degraded data set that proved to be unusable without modification.
The C-line data was the most seriously impacted, relative to the other lines and is the only data that has been determined necessary to be adjusted.
The effect of reducing the numbers of operable strain gages on the collected data was first noted in the first blind benchmark performed on QC 2 at 790 MWe [Reference 1].
The predicted data was based on the use of single pairs of strain gages at each location (2 locations per steam line, 651' and 624' elevations). The comparison to in-vessel measured pressure data showed that the single strain gage pair data yielded the key frequency content of the major acoustic loads (at 155 hz) reasonably. It further showed that significant frequency content not present in the in-vessel data appeared in the predictions. At approximately 80 hz, the prediction included a large magnitude peak that was not reflected in the plant data. Subsequent QC 2 predictions employed the combination of two strain gage pairs at each location, and the results showed that the 80 hz signal was effectively eliminated.
For the QC 1 Test Condition 15A data, a single pair of strain gages is available on the C-line at the 651' elevation. Review of the predicted pressures from this pair shows the same tendency as observed in QC 2, specifically the tendency to include large 80 hz frequency content. Since the opposite strain gage pair is faulted, the only options available are to use the data as is, or to apply correction to produce an appropriate load.
The former approach was attempted without success, due to sensitivity of the structural model to excitations in the 80 hz range. Therefore the challenge is to produce a load that is appropriate for use in structural analysis.
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Report No. AM-2005-003, Revision 0
- 2. Methodology 2.1 CDI Acoustic Circuit Analysis The CDI acoustic circuit analysis methodology employs strain gage data taken at a minimum of two locations on each steam line to establish a boundary condition and then project an inlet condition at the reactor vessel nozzle, using transfer function methods.
This approach captures sources in the steam lines as well as any present in the vessel, such as might be expected from a flow vortex entering the steam lines. The pressure field inside the vessel is calculated using a three dimensional Helmholtz equation solution and combining with the boundary conditions established at the nozzles. The output of the CDI analysis is the time dependent acoustic pressure field in the steam space of the reactor vessel. It is important to note that the acoustic circuit analysis is completely dependent on the dynamic pressure data derived from the strain gage data.
If non-acoustic pressures are predicted at the strain gage locations, they will be transferred forward and imply false loading conditions on the steam dryer. The CDI methodology is documented in Reference 2.
2.2 QC 1 Test Condition 15A Description 2.2.1 Power level Test Condition 15A was performed at a power level of 2887 MWt. It represents a maximum observed response achievable at the time of the testing.
2.2.2 MSL Strain Gauge Inputs:
Eight main steam line locations were instrumented with 16 pairs of strain gauge for the acoustic circuit analysis.
- MSL "A" Elevation 651 S1/S3 pair Elevation 624 S5/S5a pair
- MSL "B" Elevation 651 S7/S9 pair Elevation 624 S11/S11a pair
- MSL "C" Elevation 651 S31/S33 pair Elevation 624 S35/S35a pair
- MSL "D" Elevation 651 S37/S39 pair Elevation 624 S41/S41a pair 4 of 22
Report No. AM-2005-003, Revision 0
- MSL "A" Elevation 651 S2/S4 pair Elevation 624 S6/S6a pair
- MSL "B" Elevation 651 S8IS1O pair Elevation 624 S12/S12a pair
- MSL "C" Elevation 651 S32/S34 pair Elevation 624 S36/S36a pair
- MSL "D" Elevation 651 S38/S40 pair Elevation 624 S42/S42a pair The failed strain gages in the TC 15A test data condition are:
S3 (MSL "A" Elevation 651)
S6 (MSL "A" Elevation 624)
S11a (MSL "B" Elevation 624)
S31 (MSL "C" Elevation 651)
S36 (MSL "C" Elevation 624) 2.2.3 In-Vessel Instrumentation No In-vessel instrumentation was employed in the development of the dryer pressure loads on QC 1. High speed pressure data was recorded for the vessel level instrument taps (59A and 59B) located in the dryer skirt region. This data will be used to provide understanding of the acoustic pressure field being experienced in the vessel.
2.1.1 Additional MSL Instrumentation In addition to the strain gage placements described above, there were accelerometers installed and monitored on the Electromatic Relief Valve on line C. The data from these instruments will be reviewed for frequency content.
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- 3. Calculations 3.1 Calculation Approach Fast Fourier Transform were generated to allow characterization of the frequency content and power spectral density (PSD) of the strain gage data at both locations on the C MSL, as well as the vessel level tap data. The PSDs were generated using sample groups of 2000 samples per group, based on the data time step. Frequency content up to 200 hz was calculated to coincide with the frequency interval calculated by CDI and applied in the structural loads calculations.
The intent of the comparisons performed at multiple locations is to demonstrate whether non-acoustic loads are being introduced into the strain gage data at the remaining C MSL strain gage pair, and to determine an appropriate reduction factor if justified. The principal criteria applied in this evaluation are:
- 1. True acoustic pressure signals will be observed to propagate. Evidence of propagation will be sought in the vessel level tap data and the C MSL 624' elevation data.
- 2. Non-acoustic signals may be reduced to the general background amplitude of adjacent frequencies, but not below comparable data on the fully instrumented D MSL.
- 3. The frequency range for which a data correction is applied will be minimized to the maximum extent possible.
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- 4. Results The following section describes the data reviewed and the observations that resulted.
4.1 Observations from the U-2 790 MWe Blind Comparison and Model Correction 4.1.1 Model Configuration The CDI model for this case applied single strain gage pair data only for the blind comparison. The revised case applied both strain gage pairs at each measurement location. 60 and 180 hz narrowband noise was also filtered.
4.1.2 Comparison of the Blind to the Revised Case Plots of the predicted vs. measured pressures at sensors P-20 and P-21 for the QC 2 790 MWe blind benchmark and the revised case are shown in Figures 1 through 4.
Sensors P-20 and P-21 are on the dryer cover plate adjacent to the C and D MSLs. As noted above, the principal difference in the analytical prediction was the incorporation of both sets of strain gage data at each location measured. The blind comparison, based on a single pair showed significant signal strength at the 80 hz location, that was not reflected in the plant data. The revised calculation, employing both pairs of strain gages, shows a much more appropriate, although still conservative representation of the plant data at the 80 hz range. The following observations are salient:
- 1) Use of a single strain gage pair in estimating dynamic pressures in the MSL may yield signal frequency content that is not representative of the actual plant acoustic loading.
- 2) The plant data suggests that there is little or no acoustic loading at the 80 hz frequency range. Indicated pressure loads at this frequency range appear to be in the noise levels of the instrumentation.
4.2 Unit I TC 15A C MSL Single SG Pair Prediction The PSD of the single pair prediction for the 651' location on C MSL is shown in Figure
- 5. In Figure 6, this data is shown with similar data taken from the B and C MSLs on QC 2 where two pair data combination was performed. What is readily apparent is that the QC 1 C MSL strain gage data shows a large 80 hz signal that is not seen in either of the comparable QC 2 MSL points plotted. The 80 hz signal is large relative to the 157 hz acoustic loads present on all signals. As noted above, initial structural analyses based on the single pair data that utilized only a simplified amplitude correction based on the 157 hz signal strength were performed and showed that the structure was sensitive to 80 hz signal content. Therefore, conservatively ignoring the included signal has been considered and shown not to be a practical approach.
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Report No. AM-2005-003, Rcvision 0 4.3 Vessel Level Sensor Pressure Tap Data The vessel level taps are located in the dryer skirt region and provide an independent means of confirming the frequency content of the vessel pressure field. The data was taken simultaneous with the strain gage data. Figures 7 and 8 show the PSD plots of the CH59A and CH59B vessel level taps. What is clear from these plots is that the large acoustic load at approximately 157 hz is clearly present and dominant. The figures show that there is little if any signal present in the 80 hz range. This suggests that the 80 hz signal in the C MSL 651' pair is not the result of a propagating acoustic pressure. In contrast the 157 hz signal is clearly a propagating acoustic pressure.
4.4 C MSL 624' Elevation Data Figure 9 shows the PSD of the response of the functioning strain gage pair at the 624' elevation of the C MSL. Comparison of this plot to the 651' data on the same steam line in Figure 5 is beneficial. The following observations can be made:
- 1) There is some 80 hz content, but it is very near the background level.
- 2) The 140 hz signal component is more prominent at this location than the 157 hz signal.
These observations support that there is not a large propagating 80 hz acoustic pressure. The variation in the in the 140 hz vs 157 hz signals suggests that acoustic node points may be a factor. Therefore, this data point does not provide a singularly compelling argument by itself.
4.5 C MSL Accelerometer Data Figures 10, 11, and 12 provide the x,y, and z direction acceleration vs frequency data for locations at the ERV on the C MSL. The accelerometers clearly show the 140 hz and 157 hz signals. These signals are the only peaks that show in all three axes, which is consistent with the large magnitude of these signals evidenced in other data provided.
There is little or no 80 hz signal component in any of the accelerometer data. The lack of 80 hz components suggest that there is no propagating acoustic pressure at this frequency. Since this location is fairly near to the 624' elevation strain gage pair, it supports that the absence of 80 hz signal component in the strain gage data is due to the absence of a propagating signal, and not due to accidental location at an acoustic node point.
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- 5. Conclusions/Discussion This report has demonstrated the following:
- 1) Use of a single pair strain gage reading vs multiple pairs can introduce non-acoustic signals into the dynamic pressure time history being developed. This was demonstrated in the QC 2 790 MWe blind benchmark and revised 790 MWe predictions.
- 2) A large 80 hz signal is present in the single pair data developed from the QC 1 C MSL 651' location.
- 3) Vessel level tap pressure data suggests that there is no significant 80 hz signal present in the QC 1 dryer skirt region. This is consistent with observations at QC2.
- 4) Review of the frequency response at the C MSL 624' elevation does not show evidence of propagating 80 hz signals.
- 5) The accelerometer data from the C MSL ERV location shows no evidence of 80 hz signal.
These findings support the conclusion that the 80 hz signal in the C MSL 651' elevation is a result of local structural effects and does not reflect a propagating acoustic pressure. Therefore, if the single pair strain gage data must be used for dryer load prediction, it is appropriate to reduce the 80 hz signal to a level comparable to that of adjacent frequencies.
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- 6. References
- 1. "Acoustic Circuit Benchmark Quad Cities Unit 2 Instrumented Steam Path 790 MWe and 930 MWe Power Levels", Exelon Report AM-2005-002, Dated June 6/15/05
- 2. "Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes," CDI Report 04-09, May 2004.
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Report No. AM-2005-003, Revision 0 Figure 1 Sensor P-20 CDI 790 MWe Prediction PSD PSD of Sensor P20 Measured/Predicted 0.1 0.01 I -103 PSD-Dmk
.t1 PSD_DI k
-- 4 1*10-4 l ,l0-6 0 50 100 150 200 Freqk frequency hz
- measured
-- - predicted 11 of 22
Report No. AM-2005-003, Revision 0 Figure 2 Sensor P-21 CDI 790 MWe Prediction PSD PSD of Sensor P21 Measured/Predicted 0.1 0.01 I,
3 I .10-PSD-Dmk PSD_Dmk'*
I 10-5 I .10- 5 50 100 150 200 Freqk frequency hz measured
--- ' predicted 12 of 22
Report No. AM-2005-003, Revision 0 Figure 3 Sensor P-20 CDI 790 MWe Prediction PSD Revised PSD of Sensor P20 Measured/Predicted 0.1 0.01 I -103 PSDDmk N
- 5. PSDDl k 1 .10i 0 50 100 150 200 Freqk frequency hz measured
-- - predicted CoI 13 of 22
Report No. AM-2005-003, Revision 0 Figure 4 Sensor P-21 CDI 790 MWe Prediction PSO Revised PSD of Sensor P21 Measured/Predicted 0.01 0.01.
PSDDmk '
, PSD Dl -10 0 50 100 150 200 Freqk frequency hz
- measured
- - - predicted 14 of 22
Report No. AM-2005-003, Revision 0 Figure 5 U-1 C MSL 651' Single Pair data Samnpe Rate = 2000 Sps Power Spectral Density Date: 05-Jun-2005 Time Duration = 200.1995 sec File: Ul 2887 MWt T(r 15 Strain Ul Main Steam, TC-15a, MSL C651 S32/S34, Ch 16 1( _ --T- = = = - -- - - -
- - - - - - - -T -E_ - - -_ - - - - -___
- _- -_E
-E - - - - - - - - - - - - - - - - - -
7- - -- -- -- ------- - - - - - -- - ----- -
1( -1 _~ - - -r - - - - - - -
1 - - - - - -- -- - - - - - - -
1
- - - - - - - - - - 7 - - --- ----
-r : : :- r- - ,La I ------- ,_ - -- - - - - - - - Z e
-- - - - - - -- - -- - 7- -_--iT-. -_ - - - - - - - - - --
F- l-o 2W £ - _- _- _ - - -,- - - -
a) =-z- - - - - - -n
-O:3 10 I- - -- - - -- - --- - --
4 - - ----- - --- - -
10-5 z-x- -- ----- -x- - x--l- 7 4
-I :~- --- RMS= 1.1103 106 - -- i--Pk-Pk= 9.6295
--- Notch Filters On (6&10z
--- -- -- --- --- -- --- ---- Band Filter =2 to200 -Iz -
1o-7 C 20 40 60 80 100 120 140 160 180 200 Frequency [I-b]
CIIQ 5 15 of 22
Report No. AM-2005-003, Revision 0 Figure 6 Comparison of QC C MSL Single Pair Data to Q2 Two Pair Based Data MSL C 651 7TOOE-01
-U2 100% MSL B S8/S1O
-U2 100% MSL C S32/S34 6.OOE-01 Ul Test MSL C 651 S32/S34 .
5.OOE-01
, 4.00E-01 I-
' 3.00E-01 2 OOE-01 1.OOE-01 A kl i O OOE.00
^,A-AA 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
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Report No. AM-2005-003, Revision 0 Figure 7 PSD of Vessel Level CH 59A PSD of Level CH 59A t i 0.1 0.01 : : I . : 1 7 , :: =
71 . 7 I 7
- : I : :::: 0 17 a:
Yt: :' tl :: :l ' 10 ' f
<e PSD Di - ., 1,, * ,
r4 - l l10 I 191 n \
i i R s ll .
A.
5 z= =zzz
\ . .:.-:t:R.
--.- ^ ^ l =.VR:
t ,,
18 -
i t
1 R R RR-0 S 10WF ' \ :\n }' aM /M \
1 .10 -4
. v S I IV At1r-
- ::::: t {: :f:: :;: : 0 0 01 YS I 10-5 :C:::::X:X:C:X::X::S::
- V::V:V: :X:V:::V:V:::z:
Sf ::::V.a VVV ::: ::X::SzL-VV::V::VVVVV::VV:
- V:: z 50 100 150 200 Freqk frequency hz 17 of 22
Report No. AM-2005-003, Revision 0 Figure 8 PSD of Vessel Level CH 59B PSD of Level CH 59B 0.1 II 0.01 PSDD Ik -3
.;; _ I.1 0 I1L 1 io0-0 50 100 150 200 Freqk frequency hz 18 of 22
Report No. AM-2005-003, Revision 0 Figure 9 QC I C MSL 624' Elevation Single Pair Data Sample Rate = 2000 sps Power Spectral Density Date: 05-Jun-2005 Time Duration 200.1995 sec File: U1 2887 MWt TC 15 Strain U1 Main Steam, TC-15a, MSL C624 S35/S35A, Ch 12 10I _ _L: -_ r - -- T-- -* - - -- --- - -
-=-==
= = = = =r==== - -- -- - - - - - --- __
1I0 - - - - -
-r-- -------
r- -- -- -- --- -X-- -j- -- -- -- -- -- -- -- ---
-3 7---- --
Fr------
3 fl "A' i 0 r 10 _E - - - - 3 __ - -- -; - - = -=
I N - - - - - - - -
F -10 - - - -- - - - - -- - -I- - -- - -
C- - ---- - - - - -_- - - - - - - - - /-
. - - -- - z -- - -- - -
E
--- _ --------- _ --- ____- RMS =03--------
03 8 17 Pk-___Pk=k3.0105
__--Z-4-- -- Notch Filters On(60&18Hz)
\------I-----------_--------- - Band Filter = 2to200Hz 10-8 A_
0 20 40 60 80 100 120 140 160 180 200 Frequency [Hz]
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Report No. AM-2005-003, Revision 0 Figure 10 QC 1 C MSL ERV Accelerometer Data (X-direction)
Quad Cities U1 %- 6/5/05 14:50 PM -% 912 MWe Filtered Spectral Plot "C" ERV - X Direction Max Sec: 5 Second Composite grms = 0.20768 0.09.
0.081 0.06-C I I cvl I
.°0.05 -,I - -II - - - - - --
Cl) r - -,---
-- - - - _-- 0.0660.0417
- - - - - - _- - ____.2fi cn, II I 0.0 L------
0.02
t I t- -- - - -
0.02 t :.- 4i l' 0.01l 20 40 60 80 100 120 140 160 180 200 Frequency, Hz 20 of 22
Report No. AM-2005-003, Revision 0 Figure 11 QC I C MSL ERV Accelerometer Data (Y-direction)
Quad Cities U1 %- 6/5/05 14:50 PM -% 912 MWe Filtered Spectral Plot "C" ERV - Y Direction Max Sec: 49 Second Composite grms = 0.31935 0.04 - - --
0.035-,:
519 g I 0 0.025 0
0.02 . -- --- -- - - - - - - - - - - -- :- - -------- -----
0.025
< 0.015 -- I 0.005 0illt_--s i -__
O - ........ - A , ,m 0
20 40 60 80 100 120 140 160 180 200 Frequency, Hz ciF 21 of 22
Report No. AM-2005-003, Revision 0 Figure 12 QC I C MSL ERV Accelerometer Data (Z-direction)
Quad Cities U1 %- 6/5/05 14:50 PM -% 912 MWe Filtered Spectral Plot "C" ERV - Alt Z Direction Max Sec: 139 Second Composite grms = 0.25037 0.09 , I : -
0.08 i . -
0.07 0.065 g 158 HF 2 0.06 -- 1 -
._ 0.03 I I I '
O0.02 0)I I I I I.
3 0.06 -- . 4 ----------
0)- 0.04- - - - ---
0.0
-t--4--I-0.2 Ii 20 40 60 80 100 120 140 160 180 200 Frequency, Hz 22 of 22