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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 4 "Quad Cities Strain Gage Uncertainty Evaluation," SIA File No.: EXLN-17Q-302, Revision 0, dated April 25, 2005
Structural Integrity CALCULATION File No.: EXLN-17Q-302 Associates, Inc. PACKAGE Project No.: EXLN-17Q PROJECT NAME: Strain Gage Uncertainty for Steam Dryer Load Definition CLIENT: Exelon Generation Co., LLC Contract / P.O. No.: 00083767 PLANT: Quad Cities Unit 2 CALCULATION TITLE: Quad Cities Strain Gage Uncertainty Evaluation Project Mgr. Preparer(s) &
Document Affected Approval Checker(s)
Revision Pages Revision Description Signature & Signatures &
Date Date 0 1-9 Initial Issue K. K. Fujikawa L. S. Dorfman App A 4/25/05 4/25/05 K. K. Fujikawa 4/25/05 Page 1 of 9 SIFonn F2001R2
Table of Contents 1 INTRODUCTION ............................................... 3 2 QUAD CITIES STRAIN GAGE DATA ACQUISITION .............................................. 3 2.1 Full Scale Range, Resolution Calculation and Scaling Factor ............................................... 3 2.2 Uncertainty Analysis ................. 4 4;
3 REFERENCES .......... 9 APPENDIX A UNCERTAINTY ANALYSIS SPREADSHEET........................................................... Al List of Figures Figure 1: Wheatstone Bridge.7 Figure 2: Electrical Schematic for Quad Cities Unit 2 .8 StructuralIntegritync.FileNo.: EXLN-17Q-302 Revision: 0 Revison 0 (Associates, Inc. Page 2 of 9
1 INTRODUCTION This calculation determines the dynamic pressure resolution and uncertainty for the strain gage measurements that will be taken at Quad Cities Unit 2 (QC2) during the upcoming 2005 outage.
2 QUAD CITIES STRAIN GAGE DATA ACQUISITION Strain measurements will be made at Quad Cities Unit 2 (QC2). The data acquisition system including signal conditioning and DAS is entirely different than that used at Dresden; although the strain gages are the same. For Dresden the strain gages and completion resistors were assembled as a completed bridge, for QC2 the completion resistors will be installed near the DAS in the signal conditioner.
This document reviews the calculations to determine the pressure from the strain measurements and provides the dynamic pressure resolution and uncertainty.
Figure I is a diagram of the Wheatstone Bridge. The weldable strain gages provided by Hitech Products, Inc. (HPI) for this task were installed in the circumferential direction and connected to the opposite arms of the Wheatstone bridge with completion resistors inserted in the other two arms.
Figure 2 provides a schematic for the QC2 DAS. The strain gages are spliced to shielded pair electrical cable, fed through the primary containment penetration to a strain gage cabinet that includes the strain gage signal conditioner and amplifier (Kyowa DPM-71A). The signal conditioner provides bridge balance and amplification. The DPM-71A will be shunt calibrated to provide a system sensitivity of IOOPC/V.
The amplified signal is then fed into a LMS SCADAS data acquisition system with a PQFA voltage amplifier. The amplifier provides amplification (+/-0.0625 -. 10 V input range), anti-alias filtering, A/D conversion (24 bit) and storage to disk.
2.1 Full Scale Range, Resolution Calculation and Scaling Factor In this configuration the bridge will add the two arms according to the following equation.
pi= ( AR, _AR2 +AR1 _ A-R4 (A)
XI=4 RI J?2 1?I R4 where VO = output voltage of the bridge Vi= bridge excitation voltage R is the change in gage resistance, AR, divided by the gage resistance, R, due to an applied strain, c, for each arm of the bridge.
Structural Integrity File No.: EXLN-17Q-302 Revision: 0 Associates, Inc. . Page 3 of 9
For this case, R2 and R4 are completion resistors thus AR2 = AR4 = 0 (no resistance change due to strain) and AR - R 3 ~- for strain in the same plane along the pipe. Equation A is reduced to RI R3 R 4 (AR, + AR3 2 AR AR (B) or R-(---r 2-=) ) (B) 4 RI ~4~ R 2R The applied strain, c, changes the gage resistance according to the formula AR
-= GFe (C)
R where GF is the dimensionless gage factor provided by the gage manufacturer that relates the strain to the change in resistance.
Equation C then becomes V/= 2 GFe or £= -F (D)
YVI 2GF The DPM-7]Aprovides full scaleinputranges of d100 to I0,OOOpcproviding+/-1V out forthe full scale input.
Assuming that the input range of the LMS PFQA amplifier is set to +/-lV (+/-100iic), the A/D resolution can be calculated as follows:
The AID, converter is 24 bits or 224 bits for the full input range of 2V (200pc), providing an A/D resolution of (200/224 ) = 0.000012p£.
Assuming the same relationship between the pipe's internal pressure to the hoop strain is the same as Dresden [1], 0.251 pc/psi will be used to determine the Full Scale range and A/D resolution in pressure Full Scale Range = 1 00pz /0.251 pc/psi =+/- 398psi and the A/D Resolution = 0.000012pe /0.251pc/psi = 0.000048psi.
2.2 Uncertainty Analysis The uncertainty analysis combines the uncertainty of the strain-to-pressure calculation and the measurement system. The strain as measured in the circumferential direction is the superposition of the strain in the circumferential and that due to the Poisson effect of the axial strain due to the internal pipe pressure.
StructuralIntegrity FileNo.: EXLN-l7Q-302 Revision: 0 Associates, Inc. Page4 of 9
The hoop and axial stress are calculated from the equations 2p 2 2
2PdH_d (E) and a Pd (F)
The hoop strain is the strain in the circumferential direction minus v times the axial strain as shown in the following equation aH - V6L,(G O
ell E (G)
Substituting Equations E and F into Equation G yields Pd (2-v)
H E(d2_d2) (H) where the strain per unit pressure is
___ d?(2 - v) p E(d2-d2) or p( Cd(-v) where CFH= Hoop stress due to internal pressure, psi GL= Axial stress due to internal pressure, psi E,,= Hoop strain, pin/in p = unit applied internal pressure, psi di= pipe inside diameter, in do- pipe outside diameter, in E = Young's Modulus, psi v= Poisson's ratio.
Equation (J) relates the internal pipe pressure to the measured strain.
The overall uncertainty is determined by a SRSS method used for random errors. The nominal (no error) pressure is calculated first. Then the pressure is calculated again by changing each variable in the equation by the amount of the potential error, one variable at a time. The new pressure calculated for each variable with the error is then subtracted from the nominal pressure and squared. This is done for each case where there is an uncertainty in the parameter of the pressure equation. Each case's squared difference from the nominal is summed and the square root taken of the result.
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The nominal values are as follows:
di=17.93 in d=20 in E= 27.9xlo6 psi v=0.3 GF = 2.0 E= I 001t, the full scale range.
The accuracy values are as follows:
di= 2.8% (ASME Code worst case) do= 0.625% (ASME Code worst case)
E = 5% (SI metallurgist, common practice) v 0 (SI, common practice)
GF = 2% per gage, for 2 gages (SRSS) =2.8% (HP], Reference 2)
The uncertainty for c, Absolute Strain Error (ASE) is found in Reference 2 for a quarter bridge as ASE = (GF2 + OEE 2)0 5 or for a half bridge as (2(GF2 ) + OEE2 )0 5 where OEE = overall electronics error, 1.1% (Reference 2)
GF = Gage Factor of 2.0 (HPI).
The uncertainty for c is calculated as ASE = 3.03%.
For QC2 the error will be minimized by making actual pipe thickness (ultrasonic) and outer diameter measurements. Assuming that do can be measured with an error of 10 mils and the thickness can be measured (ultrasonic) within 20 mils the error becomes do =0.05%
di = 0.22%.
The overall uncertainty on the measurement and conversion to pressure is 6.3% (see Attachment A).
Integrity FStructural le No.: EXLN-17Q-302 Revision: 0 Associates, Inc. Page6 of 9
Vi g -strain gage, 350ohm l l cr - completion resistor, 350 ohm Figure 1: Wheatstone Bridge StructuralIntegrity File No.: EXLN-1 7Q-302 Revision: 0 Associates, Inc. Page 7 of 9
Kyowa DPM-71A Signal Conditioner 350 Ohm 100microstrainNolt GF: 2.0 L DAS Figure 2: Electrical Schematic for Quad Cities Unit 2 Structural Integrity File No.: EXLN-1 7Q-302 Revision: 0 Associates, Inc. Page 8 of 9
3 REFERENCES
- 1. E-mail from Guy DeBoo (Exelon) to K. Fujikawa (SI) and L. Dorfman (SI), dated 2/1/05, "Dresden MS Line Strain Gage Information," SI File No. EXLN-1 7Q-201.
- 2. Y. Dayal, "Exelon Corporation Quad Cities Unit 2 Nuclear Power Plant Dryer Instrumentation Uncertainty", GE-NE-0000-0037-1951-01 Rev 0, February 2005, SI File No. EXLN-1 7Q-202.
tutrlnertlFile t
Structural Integrity Associates, Inc.
No.: EXL-N-17Q-302 Q j 0 lRevision:Pg~f Revision:
Page of .
APPENDIX A UNCERTAINTY ANALYSIS SPREADSHEET Structural Integrity File No.: EXLN-17Q-302 Revision: 0 4 Associates, Inc. PageAl of A2
Quad Cities 2 Accuracy with improved diameter measurements Accuracy Nominal Nominal Values Plus di 17.93 0.22% 17.969446 do 20 0.05% 20.01 E 2.79E+07 5% 29295000 v 0.3 0 0.3 GF 2 2.8% 2.056 E 0.0001 3.03% 1 0.000103 I Nominal + di I + do I +E I t SRSS I Pressure 400.818621 391.86341 1 402.86113 1 420.85955 1412.96343 Theta 4070.5524 4085.0112 -400.81862 400.81862 Uncert*Theta . I 8.9552154 12.0425056 -20.040931 I 12.144804 169484 Pressure = 400.81862 psi + 25.169484 psi
% Error 6.3%
Structural Integrity File No.: EXLN-17Q-302 Revision: 0 Associates, Inc. . Page A2 of A2