|
---|
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
[Table view] |
Text
ENCLOSURE 2 Attachment 6 Exelon Report Number AM-2005-007, "AM-2005-007 Assessment of the Revised QC1 Minimum Error ACM Loads Using All Main Steam Line Strain Gages,"
Revision 0, dated August 2, 2005
AM-2005-007 Revision 0 AM-2005-007 Assessment of the Revised QC1 Minimum Error ACM Loads Using All Main Steam Line Strain Gages Document Number AM-2005-007 Revision 0 Nuclear Engineering Department Exelon Nuclear Generating Co.
Prepared by-. /Qan3,,, Guy DcBoo Date: ,,// 5 Reviewcd by AhI A , ! Kevin Rnsden Date: 3?/z / 0 s GE Confimnwtion f ON ( n by.
Ap b. 6* C. Pappone Dat. A%\rv -Z,2. C>
Apoved by". 414 Roman Gesior Date: _ l__o_
(Date Lssued) 1 of 14
AM-2005-007 Revision 0 Abstract This report documents an assessment of the minimum error acoustic circuit model loads that were developed by CDI using different main steam (MS) line pressure inputs. The assessment examines the differences between these two load cases to determine which would produce bounding dryer stresses.
2 of 14
AM-2005-007 Revision 0 Abstract.............................................................................................................................................2
- 1. Introduction .4
- 2. Description of Assessment Criteria .5
- 3. Assessment of TC I5a and TC I5a_3 Load Cases .6 Table 1: Pressure Comparisons for TCI Sa and TC I 5a_3 Load Cases .6 Figure 1: P22 PSD - Black Curve is TCl5a & Blue Curve is TC I5a_ . 7 Figure 2: P24 PSD - Black Curve is TCI5a & Blue Curve is TC I5a3 . 8
- 4. Conclusions and Recommendations .13
- 5. References .14 3 of 14
AM-2005-007 Revision 0
- 1. Introduction This report assesses the magnitudes and frequency content of the steam dryer pressure loads predicted by the CDI minimum error acoustic circuit model (ACM) for Quad Cities Unit 1 (QC1) as reported in Reference 1. Two sets of dryer pressure loads developed using the same acoustic circuit model with different main steam line pressure inputs were compared and assessed to determine which load case is bounding. Details of the CDI minimum error acoustic circuit model are found in Reference 2, Section 5.6. The difference between the two pressure load cases being compared is the treatment of the failed strain gage data used to develop the main steam line pressures. A detailed description of the differences in the main steam line pressures used to develop these two load cases is found in Reference 1.
The load case identified as TC15a in Reference 1 has been used in the finite element analysis of the dryer to qualify the dryer skirt. The GE finite element analysis results are designated as QC1B. The load case identified as TCI5a_3 in Reference 1 represents the dryer loads that best represent the pressures acting on the Unit 1 dryer. This is based on the conclusions developed in References 2 and 3 for the acoustic circuit model, and the recommendations for defining the QC1 main steam line pressure input to these models given in Reference 4.
The purpose of this assessment is to determine which of the two load cases would produce bounding dryer stresses. It will examine the differences in pressures at specified locations on the dryer to determine changes in pressure magnitudes and frequencies. The pressure loads on the dryer skirt and outer hoods are the specific locations to examine, as these are the locations of the largest pressures and highest stresses on the dryer.
4 of 14
AM-2005-007 Revision 0
- 2. Description of Assessment Criteria The purpose of this assessment is to determine the relative magnitudes and frequencies of the two load cases. The locations of primary interest are:
- 1) Skirt Locations P22, P24, and P25
- 2) Dryer external locations P3, P12, P20, and P21 (these are the highest load points opposite the nozzles)
- 3) Other external dryer locations may also be reviewed as necessary
- 4) Internal pressures at P13, P14 will be compared in combination with P3 and P20 to establish hood differential pressure behavior.
These locations were chosen because they best represent the pressure loads acting on the skirt (i.e., P22, P24 andP25) and the largest pressure loads acting on the outer hoods (i.e., P3, P12, P20 and P21).
The following criteria were applied for the initial comparison:
- 1) Root mean square (RMS) pressures - TC1 5a case should be within -5%
or greater than the TC15a_3 load case.
- 2) Peak pressures - TC 5a case should be within -3% or greater than the TCI5a_3 load case.
- 3) Differential pressure indications should be conservative for TC15a case relative to TC 5a_3 load case.
- 4) Power Spectral Densities (PSDs) will be compared at critical structural frequencies for the elements in question: For the skirt, this frequency is 33 Hz +/- 5Hz. For the hood, the frequencies of interest are 80-110 Hz, 140 Hz +/- 5Hz, and 155 Hz +/- 5hz. The expectation is that the TC15a case will show comparable or conservative PSD amplitude values compared to the TC15a_3 load case.
If these criteria are satisfied, the TC 5a load case is considered to be an acceptable load definition for determining the FIV stresses in the dryer.
5 of 14
AM-2005-007 Revision 0
- 3. Assessment of TC15a and TC15a_3 Load Cases The summary pressures and PSDs for the two load cases are documented in Reference 1. To assess these results, Table 1 below provides the minimum, maximum, and RMS pressures for both load cases at each of the QC2 dryer pressure transducer locations.
Pressure TC15a_3: % TC15a: TC15a_3: % TC 15a: TC 15a_3: %
Sensor TC15a: Minimum Change Maximum Maximum Change RMS RMS Change Number Minimum psi psi Minimum psi psi Maximum psi psi RMS P1 -1.342 -1.355 -0.959 1.341 1.440 -6.875 0.438 0.464 -5.603 P2 -1.028 -1.121 -8.296 1.010 1.140 -11.404 0.224 0.270 -17.037
.C.>00P300* -1,938 -A0W 122 183 8 8A1 f0.54 0A6 7.23.
P4 -0.723 -0.777 -6.950 0.755 0.728 3.709 0.177 0.182 -2.747 P5 -1.038 -0.766 35.509 0.813 0.799 1.752 0.199 0.194 2.577 P6 -1.301 -1.164 11.770 1.267 1.171 8.198 0.347 0.312 11.218 P7 -1.054 -1.125 -6.311 1.038 1.179 -11.959 0.338 0.386 -12.435 P8 -0.837 -0.678 23.451 0.809 0.713 13.464 0.182 0.161 13.043 P9 -1.674 -1.550 8.000 1.695 1.562 8.515 0.510 0.518 -1.544 P10 -1.322 -1.361 -2.866 1.364 1.393 -2.082 0.436 0.458 -4.803 P11 -0.946 -0.789 19.899 0.866 0.848 2.123 0.209 0.193 8.290 P1.28 -235 -a 089 185 2.21 2.10 l5Ai' .678
'%3 07 Eu.502 P13 -0.549 -0.355 54.648 0.403 0.343 17.493 0.106 0.087 21.839 P14 -0.461 -0.452 1.991 0.512 0.489 4.703 0.114 0.106 7.547 P15 -2.027 -2.012 0.746 1.896 1.882 0.744 0.569 0.572 -0.524 P16 -0.366 -0.304 20.395 0.289 0.262 10.305 0.078 0.063 23.810 P17 -1.160 -1.112 4.317 1.135 1.014 11.933 0.275 0.287 -4.181 P18 -1.691 -1.617 4.576 1.696 1.701 -0.294 0.501 0.517 -3.095 P19 Not functional P22 -1.439 -1.407 2.274 1.527 1.351 13.027 0.435 0.445 -2.247 P23 -0.332 -0.251 32.271 0.257 0.204 25.980 0.073 0.056 30.357 P24 -1.138 -1.029 10.593 1.193 1.125 6.044 0.280 0.257 8.949 P25 -1.342 -1.260 6.508 1.348 1.258 7.154 0.328 0.295 11.186 P26 -0.294 -0.238 23.529 0.280 0.245 14.286 0.077 0.064 20.313 P27 -0.335 -0.242 38.430 0.285 0.231 23.377 0.074 0.059 25.424 Average -1.218 -1.147 6.168 1.189 1.159 2.646 0.332 0.334 -0.450 OKIr1 pressures ror assessment e4'f0 ..e 11Outer Hood pressures for assessment Table 1: Pressure Comparisons for TC1 5a and TC1 5a_3 Load Cases 6 of 14
AM-2005-007 Revision 0 The table contains the percent difference of the TC15a load case to the TC15a_3 load case. Positive percentages indicate that TC15a pressures are greater than the TC1 5a 3 pressures for the RMS and maximum pressures. A positive percentage also indicates that TC1 5a minimum pressures are smaller than the TC15a_3 minimum pressures. Positive percent changes indicate that TC15a bounds the TC1 5a_3 load case for the pressure being evaluated.
The percent changes at the skirt locations, P22, P24, and P25, meet the assessment criteria provided in Section 2. The minimum pressures for the TC1 5a load case are smaller than the minimum pressures for the TC1 5a_3 load case by approximately 2% to 10%. The maximum pressures for TC1 5a are larger than the maximum pressures for the TC1 5a_3 load case by approximately 6% to 13%. The RMS pressures for TC1 5a are generally larger than the maximum pressures for the TC1 5a_3 load case by approximately 8%to 11%,
however one location is less by 2.2%.
Reviewing the frequency content of the skirt pressures at the P22, P24 and P25 locations in Figures 1 through 3 below, the TC15a load case clearly envelops all frequencies at these three locations with one minor exception at approximately 180 Hz.
0.1 0.01
.N C.
0.001
._ 0.0001 IO'5 10-6 0 50 100 150 200 Frequency (Hz)
Figure 1: P22 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 C(2-7 of 14
AM-2005-007 Revision 0 0.1 . ... .... I I ...
1- 0.01 N
I:l 0.001
'-0~ ,
.0001
.. 100 1:0 10 0 50 loo t5o 200 Frequency (Hz)
Figure 2: P24 PSD - Black Curve is TCI5a & Blue Curve is TCI5a- 3 0.01 N 0.001 VI
~n 0.0001 c.
0~
10'6
-- 0 50 100 150 200 Frequency (Hz)
Figure 3: P25 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 8 of 14
AM-2005-007 Revision 0 For the outer hood pressure comparisons, the assessment is not as conclusive as it was for the skirt comparisons. The TC15a maximum and minimum pressures for the P3, P12, and P21 locations are clearly bounding the pressures from the TC15a_3 load case. The TC15a maximum, minimum and RMS pressures for the P20 location are less than the TC15a_3 by approximately 5%
for each. The P3-P13 differential pressure satisfies the assessment criteria and is bounding for the minimum and RMS pressures. The TC15a maximum, minimum and RMS pressures for the P20-P14 differential pressure are less than the TCI5a_3 pressures by approximately 5%for each. With the exception of the TC15a_3 pressures at the P20 nozzle, the TC15a pressures at the other nozzles and generally for the rest of the dryer locations bound the TC15a93 pressures.
The frequency comparisons for the outer hood locations opposite the main steam nozzles are presented in Figures 4 through 7 below. Reviewing these figures the following conclusions are drawn.
- 1. P3 - TC 5a bounds the TC1 5a_3 pressures at all frequencies except a minor difference at approximately 180 Hz. This has not been a frequency of concern for the design of the dryer and magnitudes are greater at other frequencies that are more significant to the dryer.
- 2. P12 - TC15a bounds the TC15a_3 pressures at all frequencies except minor differences at approximately 150 Hz and 180 Hz. These have not been frequencies of concern for the design of the dryer and magnitudes are greater at other frequencies that are more significant to the dryer.
- 3. P20 - TC15a bounds the TC15a_3 pressures at all frequencies except minor differences at approximately 15 Hz and 50 Hz. These have not been frequencies of concern for the design of the dryer and magnitudes are greater at other frequencies that are more significant to the dryer.
- 4. P21 - TC15a bounds the TC15a-3 pressures at all frequencies.
The frequency content comparisons for the P3-P13 and P20-P14 differential pressures are presented in Figures 8 and 9 below. Reviewing these figures the following conclusions can be drawn:
- 1. P3-P 13 - TC 5a bounds the TC1 5a_3 pressures at all frequencies except minor differences at approximately 80 Hz and 180 Hz. The 180 Hz has not been a frequency of concern for the design of the dryer and magnitudes at other more significant frequencies to dryer are greater. The 80 Hz difference is very minor and would be enveloped by a much larger pressure at approximately 78 Hz.
- 2. P20-P14 - TC15a bounds the TC15a_3 pressures at all frequencies except a minor difference at approximately 10 Hz to 15 Hz. This has not been a frequency range of concern for the design of the dryer and magnitudes are greater at other frequencies that are more significant to the dryer.
9 of 14
AM-2005-007 Revision 0 0.1 I I I I I I I r - -r -
ON 0.01 ki_ 0.001 -------------------- i----------------------
I "Ze C) 0.0001
-- - - - I- - - -
10-5 ----------
6 I I 1A _
I I I 0 50 100 150 200 Frequency (Hz)
Figure 4: P3 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 1 ' ' ' --------------------
0.0 1 ----------------------- .....
V I
0 50 100 150 200 Frequency (Hz)
Figure 5: P12 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 10 of 14
AM-2005-007 Revision 0 1
0.1 - - - - - - - - - - - - - - - - -
-N 0.01 --------------------- ---------------------- r ------------- ------------
0.00 1 ---------- ------------- -------
4:-
Cn 0.000 ----- -------
CL4 10o5 -----------------------------------------------------
6 n1V 0 50 100 150 200 Frequency (Hz)
Figure 6: P20 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 0.1 = I I I I I I I I I =
0.01 2- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -!
-o 0.001 5---------------------- ---------------------- ---- -- - - - - - - - - - - - -- !
4_
rn:
rA 0.0001 - ------------
a Cn 107' ---- ---------------------- -------------------- -
1IO 0 50 . 10. . . . . 150
.- 0 50 100 150 200 Frequency (Hz)
Figure 7: P21 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 C05 11 of 14
AM-2005-007 Revision 0 0.1 0.01 E ' ' ' I I ' I I f a' 0.01l --------------------- ---------------------- ------------------A-- -t -------------
a °°t.0001 MC-@ -----
10 X, y*,-
10 , , j, , jj.
0 50 100 150 200 Frequency (Hz)
Figure 8: P3-P13 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 1 T! a i a ra ~ ----- rT t a---.r 30.01 r--- --- *-- *-----
0.001 10 -6~~ r 0 50 100 150 200 Frequency (Hz)
Figure 9: P20-P14 PSD - Black Curve is TC15a & Blue Curve is TC15a_3 coc9 12 of 14
AM-2005-007 Revision 0
- 4. Conclusions and Recommendations Based on the results of this assessment, the following conclusions are drawn.
- 1. The TC15a load case is bounding for the loading on the skirt when compared to the TC15a_3 load case. The pressures are bounding and the frequency content envelops that of TC15a_3 frequency content.
- 2. The TC1 5a load case is representative but not necessarily bounding for the loading on the outer hoods when compared to the TC1 5a_3 load case. The pressures generally bounding those from the TC15a_3 load case and the frequency content generally envelops that of TC15a_3 frequency content.
Based on these conclusions, it is recommended to qualify the skirt using the QC1 B FEA results. All other dryer components should be qualified using the QC1 D FEA results since that acoustic circuit model load case was developed using a validated acoustic circuit model, Reference 2 and Reference 3, with main steam line pressure inputs equivalent to those used in the TC15a_3 load case and satisfied the recommendations specified in Reference 4.
An additional recommendation is to perform a finite element analysis using the TC15a_3 load case. This load case is based on a validated acoustic circuit model using the best representation of main steam line pressure data as input, Reference 4; and it is less conservative than the load case used in the QC1 D FEA.
13 of 14
AM-2005-007 Revision 0
- 5. References
- 1. "Test Condition TC1 5a Load Comparison for Quad Cities Unit 1,"
Continuum Dynamics, Inc. Technical Note No. 05-34, Revision 0, dated August 1, 2005.
- 2. "Evaluation of Continuum Dynamics, Inc. Steam Dryer Load Methodology Against Quad Cities Unit 2 In-Plant Data," Continuum Dynamics, Inc.
Report No. 05-10, Revision 0, July 2005.
- 3. "Acoustic Circuit Benchmark Quad Cities Unit 2 Instrumented Steam Path Final Model Revision 930 MWe Power Level," Exelon Nuclear Asset Management Report AM-2005-004, Revision 0, July 2005.
- 4. "Comparison of Quad Cities Unitl and Quad Cities Unit 2 Main Steam Line Strain gage Data," SIA Letter Report KKF-05-037, SIR-05-223 Revision 1, July18, 2005.
14 of 14