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Category:Letter type:RS
MONTHYEARRS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS RS-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request – Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request – Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell RS-23-058, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges2023-04-24024 April 2023 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-11 Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell Flanges RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-007, Application to Adopt TSTF-564, Safety Limit MCPR2023-03-0303 March 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-032, Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location2023-02-0303 February 2023 Application to Move SR 3.5.1.2 Note to LCO 3.5.1 in Accordance with TSTF-416, LPCI Valve Alignment Verification Note Location RS-23-034, Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program2023-02-0202 February 2023 Notification of Extension to the Fifth Ten-Year Interval of the Inservice Testing Program RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-033, Request for Exemption from 10 CFR 2.109(b)2023-01-27027 January 2023 Request for Exemption from 10 CFR 2.109(b) RS-23-005, Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves2023-01-17017 January 2023 Response to Request for Additional Information for Quad Cities Relief Request RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves RS-22-127, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair2022-12-14014 December 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-10 Reactor Pressure Vessel Penetration N-11B Repair RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-119, Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval2022-10-31031 October 2022 Withdrawal of Relief Request RV-11 Associated with the Sixth Inservice Testing Interval RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-108, Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage2022-10-0505 October 2022 Response to Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-102, Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times2022-08-18018 August 2022 Supplement to Request to Revise Technical Specification 3.1.4, Control Rod Scam Times RS-22-095, Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel2022-08-10010 August 2022 Response to Request for Additional Information Regarding Request to Expand Applicability of GNF Thermal Mechanical Analysis Methods to Framatome Fuel RS-22-096, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-098, Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-282022-08-0101 August 2022 Response to Request for Additional Information for Quad Cities Relief Request RV-11, Code Case OMN-28 RS-22-094, Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements2022-07-25025 July 2022 Submittal of Sixth Inservice Inspection Interval Relief Request I6R-09 to Permit Continued Application of Certain ASME Section XI 2013 Edition Non-Destructive Examination Requirements 2024-08-20
[Table view] 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. 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 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:Miscellaneous
MONTHYEARSVP-21-041, Regulatory Commitment Change Summary Report2021-07-15015 July 2021 Regulatory Commitment Change Summary Report ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML19168A1962019-08-29029 August 2019 Staff Assessment of Flood Hazard Integrated Assessment 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-18-048, 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 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 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) 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 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.. 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 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 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 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 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 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 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 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 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 ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. SVP-12-062, Post Outage Inservice Inspection (ISI) Summary Report2012-07-13013 July 2012 Post Outage Inservice Inspection (ISI) Summary Report ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants SVP-11-050, Regulatory Commitment Change Summary Report2011-06-11011 June 2011 Regulatory Commitment Change Summary Report ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML0802800922008-01-15015 January 2008 U.S. Dept of Homeland Security/Quad Cities Nuclear Power Station Medical Services (MS-1) Drill Report/Report ML0731000992007-11-0606 November 2007 Federal Emergency Management Agency, Final Report for September 28, 2007 Medical Service Drill of the Offsite Radiological Emergency Response Plans Site-Specific to the Quad Cities Nuclear Power Station ML0711004532007-04-0404 April 2007 Westinghouse Application for Withholding, Affidavit, and Non-Proprietary Version of Attachment 2 (Attachment 3) SVP-06-081, Extension of the Provisional Variance of National Pollutant Discharge Elimination System Permit No. IL00050372006-08-10010 August 2006 Extension of the Provisional Variance of National Pollutant Discharge Elimination System Permit No. IL0005037 RS-06-113, Startup and Power Ascension Testing Following Installation of Acoustic Side Branch Modifications2006-08-0202 August 2006 Startup and Power Ascension Testing Following Installation of Acoustic Side Branch Modifications ML0600301402005-11-30030 November 2005 Enclosure 6 - Non-Proprietary GE Report GE-NE-0000-0048-1485-01-NP, Damping Value for Steam Dryer Hood Focused on a Single Frequency Regime. SVP-05-058, Regulatory Commitment Change Summary Report2005-07-28028 July 2005 Regulatory Commitment Change Summary Report SVP-05-043, Core Operating Limits Report for Plant Cycle 19, Rev 12005-05-31031 May 2005 Core Operating Limits Report for Plant Cycle 19, Rev 1 ML0611504632005-04-30030 April 2005 C.D.I. Technical Note No. 05-04, Quad Cities 2 New Dryer Smt Loads, Revision 5, Dated April 2005, Non-Proprietary SVP-05-031, Occupational Radiation Exposure Report for January Through December 20042005-04-22022 April 2005 Occupational Radiation Exposure Report for January Through December 2004 RS-05-040, Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-04-0101 April 2005 Technical Documentation Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations ML0611504572005-01-31031 January 2005 C.D.I. Report No. 04-09P, Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes, Revision 5, Dated January 2005, Non-Proprietary ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement SVP-05-001, Summary Report of Changes, Tests, and Experiments Completed2005-01-0303 January 2005 Summary Report of Changes, Tests, and Experiments Completed SVP-04-067, Regulatory Commitment Change Summary Report2004-08-13013 August 2004 Regulatory Commitment Change Summary Report ML0309006662003-03-19019 March 2003 Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Exelon Generation Company, LLC SVP-03-034, Day Post Outage ISI Letter2003-02-24024 February 2003 Day Post Outage ISI Letter SVP-03-002, 10 CFR 50.59 Summary Report2003-01-0303 January 2003 10 CFR 50.59 Summary Report ML0326713602002-08-22022 August 2002 Calculation QDC-0000-N-1117, Site Boundary and Control Doses Following a Loss of Coolant Accident Using Alternative Source Terms, Revision 0 2021-07-15
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Exelon.
Exelon Generation www.exelonCOTPCOM NucleaT 4300 Winfield Road Warrenville, IL60555 RS-06-113 August 2, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating Ucense Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Quad Cities Unit 1 Startup and Power Ascension Testing Following Installation of Acoustic Side Branch Modifications
Reference:
Letter from Keith R. Jury (Exelon Generation Company, LLC) to U. S. NRC, "Quad Cities Nuclear Power Station Operational Plan Commitments," dated April 14, 2006 Following completion of a maintenance outage in May 2006 for Quad Cities Nuclear Power Station (QCNPS) Unit 1, the unit was returned to service and implemented the start-up test program described during the March 16, 2006, meeting between Exelon Generation Company, LLC (EGC) and the NRC. The start-up test program included collecting data during operation at extended power uprate (EPU) power levels. EGC has reviewed the collected data and compiled results from this review. As described in the reference, EGC is providing the startup and power ascension test data and associated analysis to the NRC in the attachment to this letter.
There are no regulatory commitments contained in this letter. If you have any questions conceming this letter, please contact Mr. David Gullott at (630) 657-2819.
Respectfully, Kenneth M. Nicely Manager - Licensing o\0
August 2, 2006 U. S. Nuclear Regulatory Commission Page 2
Attachment:
Exelon Report AM-2006-003, "Quad Cities Unit 1 Main Steam Line Acoustic Source Identification and Load Reduction,* Revision 0 cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station
ATTACHMENT Exelon Report AM-2006-003, "Quad Cities Unit I Main Steam Line Acoustic Source Identification and Load Reduction,"
Revision 0
Quad Cities Unit I Main Steam Line Acoustic Source Identification and Load Reduction Document Number AM-2006-003 Revision 0 Nuclear Engineering Department Exelon Nuclear Generating Co.
Preardyy:44 Guy DcBoo Date: G_____,__
Reviewed by.IL A$- 4e.Z? KCeiI RarnsJdt Approved by. omn= Cksior R~L Date:
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 Abstract This report documents the results of extensive data collection on the Quad Cities Unit 1 Main Steam Lines after the installation of the acoustic side branch (ASB) modifications to the pressure relief branch line lines. The modifications were installed on the Electromatic Relief Valve (ERV) and Main Steam Safety Valve (MSSV) branch lines. The subsequent post-modification testing confirmed the effectiveness of the modifications. Review of the data confirmed that vortex shedding coupled column resonance in the relief and safety valve standpipes was significantly reduced at the power levels tested.
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Quad Cities Unit I MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 A bstract .................................................................................................... .. . . 2
- 1. Introduction ........................................................................................... . . 4
- 2. Main Steam System Acoustic Load Reduction ........................................ 5
- 3. Main Steam System Instrumentation ...................................................... 6
- 4. Start-Up Test for ASB Installation ............................................................. 7
- 5. Main Steam System Performance with ASBs Installed ............................ 9 5.1 Steam Line Strain Gage Measurements ................................................. 9 5.2 Steam Line Acceleration Measurements ............................................... 12
- 6. Conclusions and Recommendations ....................................................... 13
- 7. References ............................................................................................. 14 Attachm ent A ........................................................................ 15-20 Attachm ent B ........................................................................ 21-29 3of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0
- 1. Introduction The Quad Cities Units 1 and 2 have experienced significant steam system component fatigue, fretting, and wear failures that have been attributed to the increased steam flow velocities. A 17 % extended power uprate, (EPU) increased the steam line flow velocities and caused a significant increase in acoustically generated pressure oscillations. As a result of the increased pressure oscillations, the steam dryer experienced the most significant fatigue failures while the actuators for the Electromatic Relief Valves (ERVs) have experienced the most fretting and wear. The sources of these pressure oscillations were identified in Reference I as being the ERVs and main steam safety valve (MSSV) standpipes. Cyclic loads caused by differential pressure oscillations initiated the fatigue cracks that lead to the steam dryer failures. Quad Cities Unit 2 in-vessel pressure measurements on the steam dryer surface and main steam line acceleration measurements taken at the ERV inlet flanges have been used to confirm the sources of the pressure oscillations causing this degradation.
Analysis of the collected Quad Cities Unit 2 power ascension test data concluded very strong acoustic sources in the 140-160 Hz range accounted for the oscillating pressure loading on the dryer and the remainder of the steam path.
Subscale testing performed by Continuum Dynamics, Inc. identified the likely acoustic sources as being the ERV and main steam safety valve (MSSV) standpipes. Steam line strain and accelerometer measurements confirmed the ERV and MSSV standpipes as the sources. The standpipe column resonance frequency is excited by the vortex shedding frequency at EPU steam flow rates producing the oscillating pressures that caused the fatigue damage to the steam dryer and steam line components. Prior main steam line vibration measurements as documented in References 2 and 3 have demonstrated these same sources were active in Quad Cities Unit 1.
An acoustic side branch (ASB) was designed to decouple the standpipe column resonance frequency from the vortex shedding frequency. The ASB was also designed with acoustic damping to further suppress potential acoustic response at non-EPU flow rates. The effectiveness of the ASB modification in reducing the acoustic loads in the main steam system was demonstrated during the Quad Cities Unit 2 power ascension testing performed in the spring of 2006 and documented in Reference 1. The ASB modifications proved to be highly effective in reducing the acoustic loads. Identical ASB modifications were installed in the Quad Cities Unit I main steam standpipes in QIM19, May 2006.
This report provides a summary of the subsequent start-up testing results and confirms the effectiveness of the ASB modification on Quad Cities Unit 1.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0
- 2. Main Steam System Acoustic Load Reduction The Quad Cities Unit I ASB designs and locations were similar to those installed in the Quad Cities Unit 2 steam system. The 24" long ASBs were installed in the MSSV standpipes for the B, C and D steam lines. For the A steam line, the lengths of the ASBs installed in the 4A and the 4E MSSV standpipes were reduced by 6" and 12" to reduce the potential for these standpipes to acoustically couple with the Target Rock valve standpipe. The 34" long ASBs were installed in all the ERV standpipes. Similar to Unit 2, the Target Rock valve standpipe was not modified.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0
- 3. Main Steam System Instrumentation The main steam lines and valves were instrumented with the same instruments and locations as were used for the Quad Cities Unit 2 ASB start-up testing. The unsteady steam line pressures were obtained by measuring the piping hoop strains using 8 strain gages at two locations on each line. The ERV valves were instrumented with multiple sets of accelerometers. Two sets of accelerometers measuring the three orthogonal directions were installed on the inlet flanges to the ERVs. Accelerometer sets measuring three orthogonal directions were also installed on the ERV pilot valves and actuators. An accelerometer set was also installed at the end of an MSSV standpipe ASB on each steam line. Additional accelerometer sets were installed on other steam components to provide specific component responses.
During the start-up test two strain gages were non-functional and were disconnected from the half-bridge for the pair. The remaining functional strain gage in the pair was reconfigured into a typical 1/4 bridge configuration and the measurements were averaged with the remaining pairs. The S2A strain gage at the A main steam line upper location and the S28B strain gage at the B main steam line lower location were not functioning.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0
- 4. Start-Up Test for ASB Installation After installing the ASBs in the MSSV and ERV standpipes, steam line pressure and acceleration measurements were taken during the Quad Cities Unit I start-up test, Reference 6. This start-up test collected steam line oscillating pressures and vibration measurements at several different power levels during the unit power ascension to demonstrate the reduction of the steam line acoustic loads.
Table 1 provides a listing of the test conditions and the power levels at which steam line measurements were taken for this startup test.
Acceptance criteria were established for the test based on long-term acceptance, as Level 2 criteria, and short term acceptance (for the duration of the power ascension test) as Level 1 criteria. The acceptance criteria for the strain gage measurements were defined as the envelope of the strain gage measurements obtained from both Quad Cities Units I and 2 prior to installing the ASBs. With Level 1 being the envelope of the EPU measurements and Level 2 being the envelope of the original licensed thermal power data (OLTP) measurements.
The ERV inlet flange acceleration measurements used similar criteria, enveloping prior measurements from both units. The acceptance criteria for the ERV pilot valve and the ASB measurements were based on vibration tests that determined the long and short-term limits. For this assessment of the main steam acoustic and vibration performance, a comparison is made to the Unit 1 strain gage and ERV acceleration measurements at EPU and OLTP power levels prior to the installation of the ASBs. Using just these measurements, instead of the enveloped measures, demonstrates the actual reduction in oscillating steam line pressures and vibration levels for Unit 1.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 Table 1. Test Condition Summary Generator
(~)(~hPower Core Thermal Power Test Condition (MWe) (Wth) 2 114 515 3 242 892 4 307 1072 5 503 1659 6 545 1785 7 587 1934 8 651 2115 9 702 2250 10 751 2394 11 798 2519 11-2' 795 2504 12 822 2607 13 855 2700 14 880 2764 15 904 2840 16 913 2868 17 921 2895 18 927 2912 Note: 1. Test Condition 11 was retaken.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0
- 5. Main Steam System Performance with ASBs Installed 5.1 Steam Line Strain Gage Measurements FFTs of the steam line strain measurements obtained during the start-up test are presented in Attachment A and were compared to the steam line measurements taken at the same steam line location prior to the installation of the ASBs. The steam line data for the comparison were obtained during the unit restart after installing the replacement steam dryer in May 2005. The May 2005 startup test data are provided in Reference 4. The current steam line data presented were obtained at TC18, with the unit operating at 2912 MWt. These measurements were compared to the pre-ASB EPU data, obtained during TC1 5 with the unit operating at 2887 MWt and the OLTP obtained during TC1 1 with the unit operating at 2642 MWt. All data sets were identically processed to develop these spectra. Details of the data processing for these comparisons are provided in Reference 5.
Subsequent to the completion of the start-up test, the steam lines continued to be monitored and additional strain gage measurements were obtained. The charts provided in Attachment A include an additional data set that was obtained on July 13, 2006 when the unit was operating at 2907 MWt.
Reviewing the steam line strain gage FFTs presented in Attachment A, the results of the strain measurement comparisons are very similar to the results seen from the Unit 2 comparisons in Reference 1. The only substantial change in strain magnitudes occurs from approximately 140 to 160 Hz. The reduction in strain magnitudes between 140 and 160 Hz is readily seen to be below the pre-ASB EPU levels by an order of magnitude. In fact, at almost all steam line locations, the magnitude in this frequency range is reduced to measurement threshold levels and is well below the OLTP values. At the MSL A upper location, the TC18 measurements showed increased frequency content at 36 Hz, although the measured amplitude was still small compared to the pre-ASB magnitudes at 140 to 160 Hz. However, this 36 Hz increase is not seen in the subsequent strain gage measurements as demonstrated by the July 13, 2006 measurements, and it is not measured at the MSL A lower strain gage. This would suggest that this is not a propagating pressure response. It should also be noted that the first acoustic mode of the standpipe with ASB is above 100 Hz at all locations, and therefore the modification could not yield an increase in 37 Hz acoustic response. These facts indicate this frequency is not caused the piping breathing mode and is the result of a higher order shell mode response. This frequency content along with other lower frequency increases in the MSL B upper, MSL C lower and MSL D upper locations are determined to be insignificant when compared to the more significant reduction in almost all the other frequencies, but most importantly in the 140 to 160 Hz range.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 The result of this comparison is that the acoustic resonance at EPU power levels is reduced to measurement threshold levels and oscillating pressures are now less than at the pre-ASB OLTP levels.
Further confirmation of the steam line oscillating pressure reduction relative to prior steam line operating conditions can be seen in Table 2. The main steam line strain gage rms and maximum-minimum measurements for each test condition are summarized in Table 2. The maximum value for any test condition is compared to the pre-ASB OLTP value and in all cases is now less than the OLTP values. This comparison provides additional confirmation that the current steam line strain measurements and therefore the oscillating pressure rms and maximum-minimum values are less than the OLTP values.
Charts trending the strain gage maximum-minimum values are presented in Attachment B. On these charts the Quad Cities Unit 2 trend data are also plotted for comparison to the Unit 1 data. The Unit 1 data trends are very similar to those seen from Unit 2. These trends demonstrate the oscillating pressures are generally increasing with the square of the thermal power. This indicates the acoustic resonance has been eliminated, and the steam system unsteady pressure functional dependence is now related to the steam flow dynamic pressure only. At some intermediate power levels there are small oscillations in the maximum-minimum strain values that are attributed to the altered branch line acoustic sources. As the steam line flow velocities increase with thermal power these sources are excited, but with the ASBs the acoustic resonance is damped and the magnitude of the pressure waves remain below the prior OLTP levels.
Based on these trends and the significant reduction of the acoustic resonance pressure oscillations, it is concluded that the full thermal power (i.e. 2957 MWt) pressure loads will not exceed prior OLTP levels.
Based on these results, the Unit 1 dryer pressure loads that caused the prior dryer failures have been eliminated for EPU power levels.
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Quad Cities Unit I MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 Table 2: Summary of Main Steam Line Strain Measurements from 01M19 Startun Test RMS Values (microstrain) I
% of Description EPU OLTP TC2 TC3 TC4 TC5 TC6 TC7 TC8 TC9 TC10 TCII-2 TC12 TC13 TC14 TC15 TC16 TC17 TC18MaxTCOLTP MSL A Upper 0.46 0.37 0.05 0.05 0.06 0.06 0.09 0.10 0.10 0.11 0.14 0.23 0.16 0.17 0.16 0.16 0.16 0.16 0.17 0.23 0.63 MSL A Lower 0.28 0.23 0.01 0.03 0.03 0.03 0.06 0.06 0.07 0.08 0.09 0.10 0.10 0.11 0.11 0.11 0.11 0.12 0.12 0.12 0.50 MSL B Upper 0.22 0.31 0.04 0.05 0.05 0.05 0.09 0.10 0.11 0.15 0.15 0.20 0.17 0.18 0.17 0.18 0.18 0.19 0.19 0.20 0.64 MSL B Lower 0.35 0.26 0.02 0.02 0.03 0.03 0.05 0.06 0.07 0.08 0.09 0.11 0.11 0.12 0.11 0.12 0.12 0.12 0.12 0.12 0.46 MSL C Upper 1.11 0.84 0.03 0.04 0.04 0.06 0.06 0.07 0.08 0.09 0.15 0.11 0.12 0.13 0.12 0.12 0.13 0.13 0.13 0.15 0.18 MSL C Lower 0.22 0.18 0.03 0.05 0.05 0.07 0.08 0.08 0.09 0.10 0.11 0.16 0.16 0.16 0.13 0.15 0.15 0.14 0.14 0.16 0.89 MSL D Upper 0.24 0.25 0.02 0.04 0.04 0.06 0.06 0.07 0.08 0.09 0.10 0.12 0.17 0.19 0.12 0.12 0.12 0.13 0.13 0.19 0.75 MSL D Lower 0.32 0.33 0.01 0.02 0.03 0.05 0.05 0.06 0.07 0.07 0.09 0.15 0.15 0.16 0.11 0.10 0.11 0.11 0.11 0.16 0.48 Max-Min Values (microstrain)I
% of Description EPU OLTP TC2 TC3 TC4 TC5 TC6 TC7 TC8 TC9 TCI0 TCII-2 TC12 TC13 TC14 TC15 TC16 TC17 TC18MaxTCOLTP MSL A Upper 4.27 3.31 0.44 0.45 0.54 0.54 0.75 0.83 0.95 0.94 1.21 1.56 1.40 1.45 1.44 1.38 1.42 1.58 1.52 1.58 0.48 MSL A Lower 2.36 1.99 0.15 0.23 0.27 0.27 0.51 0.52 0.64 0.68 0.76 0.91 0.92 0.94 0.91 0.96 1.02 0.97 1.10 1.10 0.55 MSL B Upper 1.85 2.22 0.34 0.46 0.43 0.43 0.78 0.86 0.98 1.26 1.40 1.59 1.46 1.63 1.44 1.65 1.63 1.61 1.64 1.65 0.74 MSL B Lower 3.14 2.25 0.15 0.21 0.31 0.31 0.47 0.54 0.60 0.64 0.76 0.88 0.93 1.03 0.93 1.06 1.06 1.15 1.04 1.15 0.51 MSL C Upper 9.62 6.82 0.23 0.31 0.32 0.51 0.59 0.66 0.68 0.85 1.18 0.96 1.12 1.17 1.08 1.11 1.19 1.20 1.15 1.20 0.18 MSL C Lower 1.66 1.53 0.23 0.36 0.40 0.64 0.67 0.74 0.83 0.82 1.03 1.31 1.29 1.25 1.11 1.35 1.34 1.16 1.38 1.38 0.90 MSL D Upper 2.17 2.03 0.20 0.30 0.32 0.46 0.56 0.65 0.74 0.78 0.90 0.98 1.25 1.31 1.14 1.04 1.09 1.22 1.11 1.31 0.65 MSL D Lower 2.53 2.44 0.13 0.19 0.26 0.46 0.46 0.57 0.61 0.64 0.74 1.11 1.10 1.16 0.93 0.88 0.96 0.93 0.94 1.16 0.47 11 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 5.2 Steam Line Acceleration Measurements FFT spectral comparisons for the ERV inlet flange vertical acceleration measurements at TC18, 2912 MWt, are also presented in Attachment A. These comparisons to the prior EPU and OLTP measurements were chosen because they best represent the accelerations that lead to the prior ERV actuator degradation. The current acceleration measurements show very similar frequency response as seen from the strain gage measurements. The acoustic resonance behavior seen in the prior EPU and OLTP data is no longer evident.
In the acoustic frequency range from 140 to 160 Hz, very little acceleration response can be seen and it is well below the significant acoustic peaks seen in the prior OLTP data. In the low frequency range, 0 to 40 Hz, the acceleration response continues to be insignificant.
Charts trending the acceleration grms with respect to thermal power for the ERV inlet flanges are also provided in Attachment B. These trend plots clearly show the significant reduction of the acceleration levels in the steam lines. For most locations, the maximum gris is less than 50% of the prior OLTP measurement.
For the few locations where the current acceleration is approaching the OLTP limit, the actual magnitude of the acceleration is very small and has an insignificant impact on the steam line and its components. This demonstrates the magnitude of the acoustic resonance of this branch line is very small and has an insignificant impact on the overall gns value.
The current acceleration levels for the ERV pilot valves and the ASBs are compared to the acceptance criteria determined by component vibration tests.
From these comparison plots, it is clear that the current EPU vibration levels, as well as vibration levels extrapolated to full thermal power (i.e.2957 MWt) would remain well below the long-term endurance limits.
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Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0
- 6. Conclusions and Recommendations Based on the plant measurement data presented, the following conclusions can be drawn:
- 1) The acoustic resonant behavior of the main steam line safety and relief valve branches has been essentially eliminated at EPU power levels based on strain gage comparisons. The EPU unsteady pressure loads have been reduced to levels that are less than the prior loads at OLTP power levels. The maximum and minimum pressures are less than the prior OLTP maximum and minimum measurements. The EPU unsteady pressures and accelerations are below those at the OLTP levels, where the plant operated at for more than 25 years. The replacement steam dryer stress levels are effectively reduced to less than OLTP levels.
- 2) The steam line vibration gnus measurements have been reduced to approximately 50% of the prior OLTP measurements without the ASBs. The acceleration (g) levels in the 140 to 160 Hz frequency range have been reduced to background levels.
- 3) The acoustic pressure oscillations from Target Rock safety relief valve are seen at lower thermal power levels as expected and have been reduced compared to measurements obtained prior to installation of the ASBs.
- 4) Extrapolation of the these measurements from 2912 MWt to full thermal power of 2957 MWt show that the acceleration levels will remain below the prior OLTP levels and the unsteady pressures in the steam lines will be at or below the prior OLTP levels.
Based on these conclusions, the unrestricted operation of the QC1 steam system at flows up to the full licensed thermal power of 2957 MWt is acceptable.
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- 7. References
- 1. Exelon Report AM-2006-002, "Quad Cities Unit 2 Main Steam Line Acoustic Source Identification and Load Reduction," May 3, 2006.
- 2. SIA Calculation, QC-1 IQ-302, "Quad Cities Unit I Main Steam Line Component Vibration Assessment," Revision 0, January 7, 2004.
- 3. SIA Report No. SIR-06-005, "Quad Cities ERV Accelerometer Data Reduction New Dryer Design," February 2006.
- 4. SIA Report, SIR-05-208, "Quad Cities Unit I Main Steam Line Strain Gage Reductions," Revision 2.
- 5. SIA Calculation, QC-39Q-303, UQCIM19 Main Steam Line Strain Gage Data Reduction," Revision 0, June 14, 2006.
- 6. Exelon Procedure, TIC-1468, "Quad Cities Unit I Power Ascension Test Procedure for the Acoustic Side Branch (ASB) Installation," Revision 0.
14 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 Attachment A QC1 ASB Modification Startup Test Results for TC18, 2912 MWt 15 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 A Steam Line Strain Gage Spectra Comparisons:
QCI - MSL A Upper 0.20 -MSL A Upper TC18 at 2912 MWt
-OCl pre-ASB EPU 0.18 -QC1 pre-ASB OLTP
- MSL Upper 7/13/06 at 2907 MWt 0.16 0.14 0.12 0.10 0'
I-0.08 U.U0 AI 0.04 0.02 0.00 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
QCI - MSL A Lower 0.14 -MSL A Lower TC18 at 2912 MWt
-QC1 pre-ASB EPU
- QCl pre-ASB OLTP 0.12
- MSL A Lower 7/13/06 at 2907 MWt 0.10 0.08 I--
0.06 0.04 0.02 0.00 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
16 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 B Steam Line Strain Gage Spectra Comparisons:
QCl - MSL B Upper 0.25 -K6L B Upper TcM8 at 2912 MWt
- QC1 pre-ASB ERJ
- QC1 pre-ASB OLTP 0.20 MSL B Upper 7/13/06 at 2907 MWVt 0.15 C',
1--
Co 0.10 0.05 0.00 0
A~j~
20 40 60 80 OR da. -M 100 120 140 160 180 Frequency [Hz]
QCI - MSL B Lower 0.18 - SL B Lower TC18 at 2912 NW
- Q1 pre-ASB P 0.16 . O1 pre-ASB OLT
- NL B Low er 7/13/06 a t 2907 NW 0.14 0.12 .
0.10 .
0.08 0.06 0.04 0.02 0.00, 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
17 of 29
Quad Cities Unit I MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 C Steam Line Strain Gage Spectra Comparisons:
QCI - MSL C Upper 0.70 -MSL C Upper TC18 at 2912 VMt
-QC1 pre-ASB ERJ 0.60 QCl pre-ASB OLTP
- MSL C Upper 7/13/06 at 2907 vMt 0.50 0.40 I,-
0.30 0.20 0.10 0.00 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
QCI - MSL C Lower 0.16 MSL C Low erTC18 at 291 I
- QCl pre-ASB EPU 0.14- 0C1 pre-ASB OLTP
-- SL C Low er 7/13/06 at 22907 MWt 0.12 0.10 S0.08 0.06 0.04 l 0.02 0.00 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
18 of 29 Cii3
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 D Steam Line Strain Gage Spectra Comparisons:
QCI - MSL D Upper 0.16 -MSL D Upper Tc18 at 2912 MWt
-QC1 pre-ASB EPU
-QC1 pre-ASB OLTP 0.14
-MSL D Upper 7/13/06 at 2907 MWt 0.12 0.10 0,,
I--
&0.08 0.06 0.04 0.02 Y
0.00 w-0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
OC1 - MSL D Lower 0.20 WSL D Lower TC18 at 2912 Wt
- QC1 pre-ASB EPU 0.18 QC1 pre-ASB OLTP 0.16 MSL D Lower 7/13/06 at 2907 I WMt 0.14 Co 0.12 0.10 I.-
0.08 0.06 0.04 0.02 0.00 0 20 40 60 80 100 120 140 160 180 Frequency [Hz]
19 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 ERV Inlet Flange Vertical Acceleration Spectra at 2912 MWt:
QCl 3B ERV Inlet Flange Y Direction Vibration Spectra 0.30 0.25 0.20 JA 0.15 S
S 0.10 0.05 0.00 0 20 40 60 80 100 120 140 160 180 200 Frequency, Hz QC1 3C ERV Inlet Flange Y Direction Vibration Spectra 0.70 1 -- TC18 at 2912 MWt, Y1
- TC18 at 2912 MWt, Y2
- pre-ASB at 2901 MWt, Y1 0.60 .t- pre-ASB at 2901 MWt, Y2 0.50 I7,
. 0.40 I
.2 0.30 0.20 0.10 -
0 20 40 60 80 100 120 140 160 180 200 Frequency, Hz 20 of 29 0, - 01ý
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 Attachment B Q2R18 Steam Line Strain Gage and Accelerometer Measurement Trends with Thermal Power 21 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 MSL A Strain Gage Measurements Maximum-Minimum Trends:
Quad Cities Routine Monitoring - Strain Gage Max - Min MSL A Upper Level 5
4.5 4
-- UnitI Strain Gage Peak to Peak
-Level 2 Acceptance Criteria (previous EPUmeasurements)
Level 2 Acceptance Criteria (previous OLTP measurements)
-- Unit2 Strain Gage Peak to Peak S2 0
1.5 1.5 0
0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt Quad Cities Routine Monitoring - Strain Gage Max - Min MSL A Lower Level 4
3.5
- Unit I Strain Gage Peak to Peak 3 -Level 1 Acceptance Criteria (previous EPUmeasurements)
Level 2 Acceptance Criteria (previous OLTP measurements)
.-U--Unit 2 Strain Gage Peak to Peak 25 j 2 0.
0
. 1.5 0.5 0
0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt 22 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 MSL B Strain Gage Measurements Maximum-Minimum Trends:
Quad Cities Routine Monitoring - Strain Gage Max - Min MSL B Upper Level 3
2.5
- unit I Strain Gage Peak to Peak S2 [LevelI Acceptance Criteria (previous EPUmeasurements)
Level2 Acceptance Criteria (previous OLTPmeasurements)
- -4--Unit 2 Strain Gage Peak to Peak 1.5 0.5 0
0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt Quad Cities Routine Monitoring - Strain Gage Max - Min MSL B Lower Level 3.5 3 - Unit 1 StrainGagePeakto Peak
-Level 1 Acceptance Criteria(preniss EPUmeasurements)
Level2 Acceptance Criteria(previous OLTPmeasurements)
-- Unit 2 StrainGagePeakto Peak 2.5 0.
0 0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt 23 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 MSL C Strain Gage Measurements Maximum-Minimum Trends:
Quad Cities Routine Monitoring - Strain Gage Max - Min MSL C Upper Level 9Unit 1 Strain Gage Peak to Peak
-Level 1 Acceptance Criteria (previous EPU measurements)
Level2 Acceptance Criteria (previous OLTPmeasurements) 8 -- W--Unit 2 Strain Gage Peak to Peak 7
6 E
-5 9.
04 3
2 0
0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt Quad Cities Routine Monitoring - Strain Gage Max - Min MSL C Lower Level 2.5
-- Unit 1Strain Gage Peak to Peak Level1 Acceptance Criteria (previous EPUmeasurements)
Lovel2 Acceptance Criteria(previousOLTPmeasurements) 2 -- Unit2 Strain Gage Peak to Peak 1.5 U
a.
0 0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt 24 of 29
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 MSL D Strain Gage Measurements Maximum-Minimum Trends:
Quad Cities Routine Monitoring - Strain Gage Max - Mi MSL 0 Upper Level 3.5
-0k. Unit 1 Strain Gage Peak to Peak 2.5 Level 2 Acceptance Criteria (previous OLTP measurerents)
-U--Unit 2 Strain Gage Peak to Peak 0.5! '
5100105 0200 0,
0I L 50W0010 20 5030 Core Thermal Power, MWit Quad Cities Routine Monitoring - Strain Gage Max - Min MSL D Lower Level 3
2.'5
--- Unit2 Strain Gage Peak to Peak
_Level 1 Acceptance Criteria (previous EPU measurements)
Level 2 Acceptance Criteria (previous OLTP measurements)
.S 2'- Unit 2 Strain Gage Peak to Peak 0
1.5 05 I0.1 0.5 0
0 500 1000 1500 2000 2500 3000 Core Thermal Power, MWt 25 of 29 C.'tq
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 3B ERV Inlet Flange Acceleration Trend:
Q0M19 Accelerorneter Trends 38 ERVInlet Flange - X
,,,,-3BEVIrlet FaNgeX1 015 iýtor~l (pmS)EUVlue Co i
Hin10liCal (pý-ASB)CL-P 3IE RVInltFage2 0 00 1000 0000 000 2005m0 ca 1-l Pee., IWI QIMI9 A-esleronoeter Trends 3B ERV Inlet Flange - Y 04-n-O 3ERV I-F4.Flege Y1 l-H1iwtli(poe-ASS) EPUValue 00 lstodCal(o-*ASS ) CLIPValue 03-35 HV InletFlangeY2 050 1000 1500 20M0 2500 3Wm0 CO* l*.IPee,hnft Q1M1I Accelaeronete, Trends 3B FRVInlet Flange -Z
ý 38ERVInlelFlare Zl 0 1ral Hemi30 (pwe-ASS)EPUVaue Hiawoý~(prnASB)OLTPV.ý~
.3 O IRV fidelFlage Z2 0'.3 0 W0 10w0 1ism 20.0 250m00 26 of 29
!t7
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 3C ERV Inlet Flange Acceleration Trend:
Q11M19Accelerometer Trends 3C ERV Inlet Flange -X V lnlet X1 FFange S- ERVI9Fb ERV 33 ange F-3C X2 00 istor.caI(pre-ASB)EPUValue 0025 0.
Coe ThermalPoe-r AWI f005 -o3EVOeFegY Q1MI 9 Aeoleaometer Trends 3C ERV Inlet Flange - Y e*
I C ERIV.. 1eFlangeY1 0 500 000 Ism0 2000 200 3000 gramHistorcal(p-eASS)EPU Val-e Historical(pre-ASB) OLTPValue
-3CERVInetFeangeY2 0 50 1000 1500 200D 2500 30OO Co. Thiemal P-e, M QI M19 A-clerometer Trends 3C ERV Inlet Flange - Z 3X0!ERVInletFlang'eZ1
-Historical (pr*ASBJEPUValue 02Historical (pm-ASB) OLTP Value
--- 3CERVInletFlange Z2 005 o
000 1(m0 1500] 2. 2.0 30 Cýr Thmeal Powm. MWt 27 of 29 c-/f
I Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 3D ERV Inlet Flange Acceleration Trend:
0116111Accelerom~eterTrends 3D ERVInlet Flange -X 1,6 IA 12 08 04 02 Soo lowo IM 20W 2500 3000 C.t. T.,,,. P-.,, MMn QIM19 Acce.lometer Trends 3D ERV Inlet Flange -Y 01' E TRnIne P""ng.MZt C-Q1IM19Aoonler-nte Trend.
3D ERV Inlet Flange - Z I,
50.4 O2 ao 2000 2500 3000 Coe. Thýoal Power,MWt 28 of 29 c4--ý
Quad Cities Unit 1 MS Line Acoustic Source Identification and Load Reduction Report AM-2006-003 Revision 0 3E ERV Inlet Flange Acceleration Trend:
01 M19Accelerometer Trends 3E ERV Inlet Flange - X 025 025 02 015 01 0.00 500 1000 15000 2000 2500 3000 Cor TheneelP-w.,. MWI QIMI9 Acceleromneter Trends 3EERV Inlet Flange- Y 09 0.7 0,6 02 01 2000 2000 3000 CoIe ThAeroePerTr MWd Q111l11Aooelero~neter Treed.
3EERVInlet Flenge- Z 0.3 0.25
=0.15-0 010.
500 1000 1500 200 2500 3000 Co-e Therlee P.e-, MWt 29 of 29
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