Enclosure 2, Attachment 1, Quad Cities Replacement Steam Dryer Instrumentation Acceptance Criteria, GE-NE-0000-0032-1827, Revision 0, Non-Proprietary, Dated April 2005ML051360093 |
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Quad Cities |
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Mackiewicz J, Schrag M, Wu R General Electric Co |
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Document Control Desk, Office of Nuclear Reactor Regulation |
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DRF 0000-0036-2077, Class I, GE-NE-0000-0032-1827, Rev 0 |
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Category:Report
MONTHYEARRS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel SVP-21-041, Regulatory Commitment Change Summary Report2021-07-15015 July 2021 Regulatory Commitment Change Summary Report RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting SVP-20-074, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report2020-10-0808 October 2020 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report RS-20-086, Renewed Facility Operating License Nos. DPR-29 and DPR-302020-09-24024 September 2020 Renewed Facility Operating License Nos. DPR-29 and DPR-30 ML19168A1962019-08-29029 August 2019 Staff Assessment of Flood Hazard Integrated Assessment RS-19-049, Submittal of 10 CFR 50.46 Annual Report2019-05-0202 May 2019 Submittal of 10 CFR 50.46 Annual Report ML19064B3702019-03-0505 March 2019 Enclosure a - QDC-7500-M-2341, Revision 0, Quad Cities Units 1 & 2 Secondary Containment Drawdown Analysis. ML19064B3712019-03-0505 March 2019 Enclosure B - QDC-0000-N-1481, Revision 3, Quad Cities Units 1 & 2 Post-LOCA Eab, LPZ, and CR Dose - AST Analysis. 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. 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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 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 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 2024-05-06
[Table view] Category:Technical
MONTHYEARRS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-22-090, Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-07-13013 July 2022 Response to Request for Additional Information Regarding Quad Cities New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-006, Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel2022-01-20020 January 2022 Request to Expand Applicability of Prime Methods to Evaluate Fuel Centerline Melt and Cladding Strain Compliance for Framatome Fuel RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping SVP-20-074, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report2020-10-0808 October 2020 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report RS-20-086, Renewed Facility Operating License Nos. DPR-29 and DPR-302020-09-24024 September 2020 Renewed Facility Operating License Nos. DPR-29 and DPR-30 RS-19-049, Submittal of 10 CFR 50.46 Annual Report2019-05-0202 May 2019 Submittal of 10 CFR 50.46 Annual Report ML19064B3702019-03-0505 March 2019 Enclosure a - QDC-7500-M-2341, Revision 0, Quad Cities Units 1 & 2 Secondary Containment Drawdown Analysis. ML19064B3712019-03-0505 March 2019 Enclosure B - QDC-0000-N-1481, Revision 3, Quad Cities Units 1 & 2 Post-LOCA Eab, LPZ, and CR Dose - AST Analysis. RS-18-089, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109)2018-08-14014 August 2018 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (EA-13-109) RS-18-087, Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2018-08-14014 August 2018 Report of Full Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML16271A3242016-10-31031 October 2016 Technical Review Documentation for Flooding Hazard Reevaluation of Quad Cities Nuclear Power Station, Units 1 and 2 ML15251A3842015-08-31031 August 2015 Attachment 9 - NP-3305NP, Revision 1, Mechanical Design Report for Quad Cities and Dresden Atrium 10XN Fuel Assemblies - Licensing Report. (Non-Proprietary) RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14101A2282014-04-0707 April 2014 Holtec International Report No. HI-2125245, Revision 5, Licensing Report for Quad Cities Criticality Analysis for Inserts. RS-13-288, Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report.2013-12-19019 December 2013 Request for License Amendment to Technical Specifications Section 5.6.5. Core Operating Limits Report. ML13317A9572013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Quad Cities Nuclear Power Station, TAC Nos.: MF1048 and MF1049 ML13199A0382013-07-16016 July 2013 Attachment 5 - Holtec International Report No. HI-2125245, Revision 2, Licensing Report for Quad Cities Criticality Analysis for Inserts - Non Proprietary Version ML12361A0932012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 10 of 15 ML12361A0862012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 4 of 15 ML12361A0872012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 5 of 15 ML12361A0892012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 6 of 15 ML12361A0902012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 7 of 15 ML12361A0912012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 8 of 15 ML12361A0922012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 9 of 15 ML12361A0952012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 12 of 15 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 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 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 ML12361A1092012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 9 of 10 ML12361A1082012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 8 of 10 ML12361A1072012-10-31031 October 2012 Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 7 of 10 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 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 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 ML12361A0962012-10-31031 October 2012 Report 12Q0108.40-R-002, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 2. Part 13 of 15 ML13199A0392009-07-30030 July 2009 Attachment 8 - Netco Report NET-259-03, Revision 5, Material Qualification of Alcan Composite for Spent Fuel Storage ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 RS-07-157, Request for Technical Specification Change for Minimum Power Ratio Safety Limit2007-11-20020 November 2007 Request for Technical Specification Change for Minimum Power Ratio Safety Limit SVP-07-027, 90-Day Post Outage ISI Letter, Dated July 14, 20062007-05-0505 May 2007 90-Day Post Outage ISI Letter, Dated July 14, 2006 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. 2024-05-06
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ENCLOSURE 2 GE Non-Proprietary Reports and Specifications
ENCLOSURE 2 ATTACHMENT 1 "Quad Cities Replacement Steam Dryer Instrumentation Acceptance Criteria," GE-NE-0000-0032-1827, Revision 0, Non-Proprietary, dated April 2005
GE Nuclear Energy General Electric Company 175 CurtnerAvenue, San Jose, CA 95125 GE-NE-0000-0032-1827 DRF Section 0000-0036-2077 Revision 0 Class I April 2005 Quad Cities Replacement Steam Dryer Instrumentation Acceptance Criteria Prepared by:
Richard Wu Jerzy Mackiewicz Manager:
Mike Schrag Structural Analysis &
Hardware Design
'f57
-, I 7
GE-NE-0000-0032- 1827 Non Proprietary Version Page 2 NON PROPRIETARY NOTICE This is a non proprietary version of the document GE-NE-0000-0032-1827P, which has the proprietary information removed. Portions of the document that have been removed are indicated by an open and closed bracket as shown here (( )).
IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please Read Carefully The only undertakings of the General Electric Company (GENE) with respect to the information in this document are contained in the contract between EXELON and GENE, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than EXELON or for any purpose other than that for which it is intended, is not authorized; and with respect to any unauthorized use, GENE makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not infringe upon privately owned rights.
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 3 Table of Contents
- 1. Scope ........................................ 4
- 2. Strain Gauge Acceptance Criteria Determination ........................................ 4
- 3. Accelerometer Acceptance Criteria Determination ........................................ 9
- 4. Pressure Gauge Acceptance Criteria Determination ....................................... 11
- 5. References ............................................... 13 List of Figure Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations .14 Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations (continued) .15 Figure I Replacement Steam Dryer Instrumentation Sensors and Locations (continued) .16 Figure I Replacement Steam Dryer Instrumentation Sensors and Locations (continued). 17 Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations (concluded). 18 Figure 2 Weld Fatigue Factor Flow Diagram .19 Figure 3 Sample Criteria Calculation for Outer Hood Strain Gauge S-3 .20 Figure 4 Sample Criteria Calculation for Skirt Strain Gauge S-8 .21 Quad Cities Replacement Steam Dryer - Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page4
- 1. Scope The Quad Cities replacement steam dryer is instrumented with 9 strain gages, 27 pressure sensors and 6 accelerometers. The locations of these instrumentation sensors are listed in Table I and depicted in Figure 1.
The purpose of the strain gages is to confirm the structural integrity of the replacement dryer for long-term operation at extended power uprate (EPU) conditions. This document specifies the vibration acceptance criteria based on strain gage data measured during the in-plant power operation condition. If the measured strain amplitude is within the acceptance criteria, the dryer maximum stress intensity will be within the fatigue limit and fatigue crack initiation due to flow induced vibration will not occur during the power operation of the plant.
The accelerometers are used to detect the overall (rigid body) motion of the dryer:
translation and rotation. The actual accelerometer measurement consists of both the rigid body motion and the flexural motion. The rigid body motion should be in a lower frequency range, and the flexural motion should be in a higher frequency range. Acceptance criteria are developed for the flexural component of the acceleration. These accelerometer acceptance criteria may be used to supplement the strain gage criteria if the need arises.
The primary purpose of the pressure sensors is to measure the pressure loading on the dryer at the reactor operating environment. Two sets of fluid dynamic load definition are used in the design of the replacement dryer: Scale Model Testing (STM) new dryer load (Reference
- 1) and full-scale vulnerability load (Reference 2).
Acceptance criteria are developed for six of the 27 pressure gages: P3, P12, P20, P21, P24, and P27. The 4 gages next to the steam line nozzles (P3, P12, P20, and P21) are the most important for determining the loads acting on the dryer outer hoods. P24 is for determining the loads acting on the skirt and P27 is for determining the loads acting on the inner hoods.
The dynamic characteristics (vibration frequencies, modal shapes and modal damping) of the replacement dryer have been obtained from an impact hammer test conducted outside the reactor in an ambient environment (Reference 3). These results from the impact hammer test have been used to confirm and/or refine the reliability of the final finite element model used in developing the acceptance criteria reported herein.
Detailed descriptions of the development of the acceptance criteria are given in the following.
- 2. Strain Gauge Acceptance Criteria Determination Two levels of strain measurement acceptance criteria will be developed for the Quad Cities replacement steam dryer in-plant power tests: Level A and B.
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 5
((
For the steam dryer, the structural responses are multi-dimensional (multi-axial), and the strain gages may not be located at the maximum stress location. The procedure and assumptions used to determine the strain measurement acceptance criteria are described in the following for strain gages located on components above the water line and on components below the water line, respectively.
(A) Strain gages located on components above the water line (SI, and S-3 through S-9)
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page6 The fluid dynamic loads on these components are primarily acoustic in nature with distinct frequency spectra. The structure will respond at these distinct forcing frequencies.
The basic steps to establish the acceptance criteria are as follows:
((
(B) Strain gage located on drain channel below the water line (S-2).
The finite element model of the dryer uses a super element to model the skirt below the water line. This super element is used to appropriately account for hydrodynamic effects of the water on the skirt. Due the used of this super element, the strain time histories at the Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page7 gauge locations below the water line are not explicitly available. Thus a different method is required to determine the strain criteria for the underwater gauges.
The basic steps to establish the acceptance criteria for underwater gauges are as follows:
((
Based on the procedure as described in the previous Section, the maximum allowable vibration strain levels for the nine strain gages are listed in Table 1 for Level A criteria and in Table 2 for Level B Criteria.
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page8 Table 1 Strain Gage Acceptance Criteria Level A Sensor Sensor Allowable Strain Allowable Strain Criteria Location ID microstrain microstrain Strain on Dryer (peak-to-peak) (peak-to-peak) microstrain SMT Loads In-Plant Loads (peak-to-peak)
Skirt S-1 Drain Channel S-2 Outer Hood S-3 Outer Hood S4 Closure Plate S-5 Tie Bar S-6 Vane Cap S-7 Curved Part Skirt S-8 Outer Hood S-9 These low values indicate that the strain gauges are not optimally located.
Thus, any noise contamination of the signal can give rise to inappropriate conclusions. These numbers should be used with caution.
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page9 Table 2 Strain Gage Acceptance Criteria Level B Sensor Location Sensor Allowable Strain Allowable Strain Criteria on Dryer ID microstrain microstrain Strain (peak-to-peak) (peak-to-peak) microstrain SMT Loads In-Plant Loads (peak-to-peak)
Skirt S-I Drain Channel S-2 Outer Hood S-3 Outer Hood S-4 Closure Plate S-5 Tie Bar S-6 Vane Cap S-7 Curved Part Skirt S-8 Outer Hood S-9 These low values indicate that the strain gauges are not optimally located.
Thus, any noise contamination of the signal can give rise to inappropriate conclusions. These numbers should be used with caution.
- 3. Accelerometer Acceptance Criteria Determination The procedure and assumptions used to determine the accelerometer acceptance criteria are almost identical to that for the strain gauge as described in the previous section except that for the accelerometer acceptance criteria, the acceleration information are processed.
For accelerometers located on components above the water line (A-1 through A4), the acceleration time history at the accelerometer location is processed to find the maximum acceleration value. Then, the same stress normalization factor as defined previously for the Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032- 1827 Non Proprietary Version Page lo strain criteria is applied to the maximum acceleration to arrive at the accelerometer acceptance criteria.
For accelerometers located on components below the water line (A-5 through A-6), the modal accelerations are calculated at each of the accelerometer locations. Then, the same stress normalization factor as defined previously for the strain criteria is applied to the modal acceleration to arrive at the accelerometer acceptance criteria.
The actual accelerometer measurement consists of both the rigid body component (lower frequency) and the flexural component (higher frequency). These accelerometer acceptance criteria are determined only from the flexural component of the acceleration. These accelerometer acceptance criteria may be used as a conservative supplement the strain gage criteria if the need arises, and meeting these criteria may be overly conservative.
Table 3 Accelerometer Acceptance Criteria Level A Sensor Location Sensor Acceleration Acceleration Criteria on Dryer ID G (peak-to-peak) G (peak-to-peak) Acceleration
_ SMT Loads In-Plant Loads G (peak-to-peak)
Tie Bar 5 End at A-1 Hood Bank A Top Corner Tie Bar 5 End at A-2 Hood Bank F Top Corner Tie Bar I End at A-3 Hood Bank F Top Corner Tie Bar I End at A-4 Hood Bank A Top Corner Skirt Bottom at A-5 90 deg Skirt Bottom at A-6 270 deg I Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page 11 Table 4 Accelerometer Acceptance Criteria Level B Sensor Location Sensor Acceleration Acceleration Criteria on Dryer ID G (peak-to-peak) G (peak-to-peak) Acceleration SMT Loads In-Plant Loads G (peak-to-peak)
Tie Bar 5 End at A-1 Hood Bank A Top Corncr Tie Bar 5 End at A-2 Hood Bank F Top Comer Tie Bar I End at A-3 Hood Bank F Top Comer Tie Bar I End at A4 Hood Bank A Top Corner .
Skirt Bottom at A-5 90 deg Skirt Bottom at A-6 270 deg _
- 4. Pressure Gauge Acceptance Criteria Determination The primary purpose of the pressure sensors is to measure the pressure loading on the dryer at the reactor operating environment.
During the design stage of the replacement dryer, two sets of fluid dynamic load definition are used: Scale Model Testing (STM) new dryer load (Reference 1) and full-scale vulnerability load (Reference 2).
The pressure gauge acceptance criteria will be used to compare the two design loads against the actual plant measure pressure data. Acceptance criteria are developed for six pressure Quad Cities Replacement Steam Dryer- InstrumentationAcceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page 12 gages: P3, P12, P20, P21, P24, and P27. The four gages next to the steam line nozzles (P3, P12, P20, and P21) are the most important for determining the loads acting on the dryer outer hoods. P24 is for determining the loads acting on the skirt and P27 is for determining the loads acting on the inner hoods. The pre-test predicted SMT and in-pant pressure loads (design loads) are given in Reference 9.
The acceptance criteria for the pressure sensor. data are:
((
))
Quad Cities Replacement Steam Dryer- InstrumentationAcceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page 13
- 5. References
- 1. Continuum Dynamics, Inc. 2005. Quad Cities 2 New Dryer SMT Loads. C.D.I.
Technical Note No. 05-04
- 2. Continuum Dynamics, Inc. 2005. Quad Cities 2 New Dryer Vulnerability Loads.
C.D.I. Technical Note No. 05-03.
- 3. "Test and Analysis Report Quad Cities New Design Steam Dryer #1 Experimental Modal analysis and Correlation with Finite Element Results" LMS, April22, 2005.
- 4. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, Appendix I, Fig. 1-9.2.2 and Table 1-9.2.2, 1995 Edition.
- 5. "Fatigue Stress Threshold Criteria for use in the Exelon Replacement Steam Dryer",
GENE 0000-0034-8374, October 2004.
- 6. " Mechanical Engineering Design". J. E. Shigley and L. D. Mitchell, McGraw Hill, Inc. 1983, page 431.
- 7. "Recommended Weld Quality and Stress Concentration Factors for use in the Structural Analysis of the Exelon Replacement Steam Dryer", GENE 0000-0034-6079, February 2005.
- 8. "Quad Cities Units 1 and 2 Replacement Steam Dryer Analysis Stress, Dynamic, and Fatigue Analyses for EPU Conditions" GENE 0000-0034-3781, April 2005.
- 9. Continuum Dynamics, Inc. April 2005. "Pretest Predictions for New Dryer Loads for Quad Cities". C.D.I. Technical Memorandum No. 05-17.
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 14 Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page 15 Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations (continued)
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 16 Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations (continued)
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 17 1]
Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations (continued)
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032- 1827 Non Proprietary Version Page 18 Figure 1 Replacement Steam Dryer Instrumentation Sensors and Locations (concluded)
Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 19 Nomenclature: t,, =Nominal plate thickness t = Throat width at a single Fillet (see Figure 2)
= Sun of two throat widths at a double fillet Figure 2 Weld Fatigue Factor Flow Diagram Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria
GE-NE-0000-0032-1827 Non Proprietary Version Page 20 Figure 3 Sample Criteria Calculation for Outer Hood Strain Gauge S-3 Quad Cities Replacement Steam Dryer - Instrumentation Acceptance Criteria
GE-NE-0000-0032-1 827 Non Proprietary Version Page 21 Figure 4 Sample Criteria Calculation for Skirt Strain Gauge S-8 Quad Cities Replacement Steam Dryer- Instrumentation Acceptance Criteria