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Category:Letter type:SVP
MONTHYEARSVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 SVP-24-023, Ile Outline Submittal Letter2024-03-29029 March 2024 Ile Outline Submittal Letter SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 SVP-23-016, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2023-04-20020 April 2023 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVP-23-015, Annual Dose Report for 20222023-04-18018 April 2023 Annual Dose Report for 2022 SVP-23-011, Notification of Readiness for NRC 95001 Inspection (EA-22-062)2023-03-28028 March 2023 Notification of Readiness for NRC 95001 Inspection (EA-22-062) SVP-22-072, Manual Scram Due to Feedwater Regulator Valve Failure Increasing Reactor Water Level2022-12-30030 December 2022 Manual Scram Due to Feedwater Regulator Valve Failure Increasing Reactor Water Level SVP-22-061, Registration of Use of Casks to Store Spent Fuel2022-10-0404 October 2022 Registration of Use of Casks to Store Spent Fuel SVP-22-057, Response to Apparent Violation EA-22-062 and Preliminary White Finding Regarding the Failure of One Electromatic Relief Valve2022-09-15015 September 2022 Response to Apparent Violation EA-22-062 and Preliminary White Finding Regarding the Failure of One Electromatic Relief Valve SVP-22-056, Registration of Use of Casks to Store Spent Fuel2022-09-13013 September 2022 Registration of Use of Casks to Store Spent Fuel SVP-22-050, Response to NRC Inspection Report and Preliminary White Finding2022-08-18018 August 2022 Response to NRC Inspection Report and Preliminary White Finding SVP-22-046, Registration of Use of Casks to Store Spent Fuel2022-08-17017 August 2022 Registration of Use of Casks to Store Spent Fuel SVP-22-042, Owner'S Activity Report Submittal Fifth 10-Year Interval 2020 Refueling Outage Activities2022-07-22022 July 2022 Owner'S Activity Report Submittal Fifth 10-Year Interval 2020 Refueling Outage Activities SVP-22-041, Registration of Use of Casks to Store Spent Fuel2022-07-13013 July 2022 Registration of Use of Casks to Store Spent Fuel SVP-22-036, Offsite Dose Calculation Manual (ODCM) Section 12.2.2, Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor2022-06-10010 June 2022 Offsite Dose Calculation Manual (ODCM) Section 12.2.2, Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor SVP-22-029, Annual Radiological Environmental Operating Report for 20212022-05-13013 May 2022 Annual Radiological Environmental Operating Report for 2021 SVP-22-026, Radioactive Effluent Release Report for 20212022-04-29029 April 2022 Radioactive Effluent Release Report for 2021 SVP-22-024, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2022-04-21021 April 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVP-22-021, Annual Dose Report for 20212022-04-14014 April 2022 Annual Dose Report for 2021 SVP-22-018, Core Operating Limits Report for Quad Cities Unit 2 Cycle 272022-04-0808 April 2022 Core Operating Limits Report for Quad Cities Unit 2 Cycle 27 SVP-21-041, Regulatory Commitment Change Summary Report2021-07-15015 July 2021 Regulatory Commitment Change Summary Report SVP-21-040, Owner'S Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities2021-06-29029 June 2021 Owner'S Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities SVP-21-028, Annual Radiological Environmental Operating Report2021-05-13013 May 2021 Annual Radiological Environmental Operating Report SVP-21-024, Annual Dose Report for 20202021-04-22022 April 2021 Annual Dose Report for 2020 SVP-21-001, 10 CFR 50.59 /10 CFR 72.48 Summary Report2021-01-0404 January 2021 10 CFR 50.59 /10 CFR 72.48 Summary Report 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 SVP-20-069, Registration of Use of Casks to Store Spent Fuel2020-10-0101 October 2020 Registration of Use of Casks to Store Spent Fuel SVP-20-064, Registration of Use of Casks to Store Spent Fuel2020-09-0808 September 2020 Registration of Use of Casks to Store Spent Fuel SVP-20-056, Registration of Use of Casks to Store Spent Fuel for Quad Cities Nuclear Power Station, Units 1 and 22020-08-13013 August 2020 Registration of Use of Casks to Store Spent Fuel for Quad Cities Nuclear Power Station, Units 1 and 2 SVP-20-049, Regulatory Commitment Change Summary Report2020-07-14014 July 2020 Regulatory Commitment Change Summary Report SVP-20-053, Owner'S Activity Report Submittal: Fifth 10-Year Interval 2020 Refueling Outage Activities2020-07-14014 July 2020 Owner'S Activity Report Submittal: Fifth 10-Year Interval 2020 Refueling Outage Activities SVP-20-046, Registration of Use of Casks to Store Spent Fuel2020-06-30030 June 2020 Registration of Use of Casks to Store Spent Fuel SVP-20-035, Annual Radiological Environmental Operating Report2020-05-14014 May 2020 Annual Radiological Environmental Operating Report SVP-20-030, Radioactive Effluent Release Report for 20192020-04-30030 April 2020 Radioactive Effluent Release Report for 2019 SVP-20-026, Annual Dose Report for 20192020-04-30030 April 2020 Annual Dose Report for 2019 SVP-20-028, Core Operating Limits Report for Quad Cities Unit 2 Cycle 26 - Revised2020-04-21021 April 2020 Core Operating Limits Report for Quad Cities Unit 2 Cycle 26 - Revised SVP-19-091, National Pollutant Discharge Elimination System (NPDES) Permit No. IL0005037 Application to Renew2019-12-20020 December 2019 National Pollutant Discharge Elimination System (NPDES) Permit No. IL0005037 Application to Renew SVP-19-053, Regulatory Commitment Change Summary Report2019-07-11011 July 2019 Regulatory Commitment Change Summary Report SVP-19-051, Owner'S Activity Report Submittal Fifth 10-Year Interval 2019 Refueling Outage Activities2019-07-0303 July 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2019 Refueling Outage Activities 2024-08-07
[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 Generation 10 CFR 50.59 10 CFR 72.48 SVP-13-001 January 4, 2013 U. S. Nuclear Regulatory Commisslon ATTN: Document Control Desk Washington, D.C. 20555 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254,60-265, and 72-53
Reference:
Letter from W. R. Gideon (Exelon Generation Company, LLC) to U. S. NRC, "10 CFR 50.59 /10 CFR 72.48 Summary Report," dated January 5, 2011
Subject:
10 CFR 50.59 / 10 CFR 72.48 Summary Report In accordance with 10 CFR 60.59, subpart (d)(2), and 10 CFR 72.48 subpart (d)(2),
"Changes, tests, and experiments," Exelon Generation Company, LLC is submitting a summary of completed changes, tests, and experiments for Quad Cities Nuclear Power Station (QCNPS). This summary Is provided as an attachment to this letter, which describes the 10 CFR 50.59 evaluations that were completed for QCNPS between January 1, 2011 and December 31, 2012. The referenced letter provided the previous summary report. Note that there were no 10 CFR 72.48 evaluations completed for QCNPS during this time period.
Should you have any questions concerning this letter, please contact Mr. W. J. Beck at (309) 227-2800.
Tm H.tey Site V President Quad Cities Nuclear Power Station
Attachment:
Summary Report of Completed Changes, Tests, and Experiments.
cc: Regional Administrator - NRC Region III NRC Senior Resident Inspector - Quad Cities Nuclear Power Station ý1 "r~~5 I*,l, ogA e
ATTACHMENT Summary Report of Completed Changes, Tests, and Experiments 1- Tracking Number: QC-E-2011-001 Unit: Unit 1 / Unit 2 Activity Description The activity is a temporary change involving the installation and removal of four temporary jumpers in the Oscillation Power Range Monitor (OPRM) subsystem. This activity will bypass the Reactor Protection System (RPS) automatic suppression function for one RPS division, with the other RPS division in a tripped condition (i.e., half SCRAM). This configuration will exist while the RPS motor generator (MG) set is restored as the normal RPS power supply. This change is in response to an event at another station where a full RPS trip occurred during restoration of an RPS MG set when an OPRM RPS trip signal was received on the opposite trip system. This action is being taken as a compensatory action to prevent spurious/inadvertent RPS trips during RPS MG set removal/restoration/transfer operations.
Impact of Activity The installation of the jumpers requires use of the alternate method strategy for detection of thermal hydraulic instabilities. This method is described in the station updated Final Safety Analysis Report and Limiting Condition of Operation (LCO) action for Technical Specification LCO 3.3.1.3. The alternate method relies on operator action to prevent operation within the exclusion zone (greater than 25% reactor thermal power and core flow less than 60% of rated core flow), to detect oscillations and if necessary, to insert a reactor scram. Operator action is controlled by station operating procedures for power to flow map reactor operation. Design limits, accident frequencies, malfunctions, and consequences are unaffected by this change.
Basis for Not Requiring NRC Prior Approval A full 50.59 evaluation against the eight criteria of 10 CFR 50.59 was completed which concluded that prior NRC approval is not required. The proposed activity does not modify the NRC approved strategy for mitigating potential thermal hydraulic instabilities. By station procedures, and during this activity, operation of the plant is normally controlled outside of the exclusion zone where thermal hydraulic instability would be expected to occur. Alternate means of monitoring for this condition are invoked as prescribed in the licensing basis documents (including Technical Specifications) during the time the temporary jumpers are installed. In addition, although the jumpers are installed preventing the trip function for one RPS trip function, the OPRM System is still available to provide alarms to the operator if the onset of oscillations were to occur.
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ATTACHMENT Summary Report of Completed Changes, Tests, and Experiments 2 Tracking Number: QC-E-2011-002 Unit: Unit 1 / Unit 2 Activity Description This activity reviews the Control Room Habitability Analysis of Offsite Hazardous Chemicals (Calculation QDC-5700-M-1 767, Rev. 0). The purpose of this calculation is to document the triennial offsite survey of chemicals near Quad Cities and to evaluate the identified offsite toxic chemical hazards for control habitability. This calculation identified a new bounding scenario for control room habitability. The UFSAR currently states that a postulated failure of three large refrigerated atmospheric ammonia tanks located at an industrial site north of the nuclear plant is the basis for determining that adequate protection is provided for ammonia gas. As a result of the triennial offsite survey documented in the calculation, and resultant analysis for control room habitability, the new bounding scenario is a barge accident near the site carrying anhydrous ammonia or fertilizer. The bounding toxicity concentration limit for ammonia in the control room as stated in the UFSAR is being changed from 100 ppm to 300 ppm. This higher industry-accepted limit was used as the acceptance criteria for all the analyzed ammonia spills/accidents. This UFSAR update is required to reflect the more up-to-date identified release scenario and toxicity limit for ammonia.
Impact of Activity Currently, the UFSAR identifies the limiting scenario for control room habitability as an ammonia tank failure at an industrial site north of the plant. Based on the new toxic gas survey, the limiting scenario has become a barge accident near the plant. Based on this new scenario, no procedures or plant equipment is affected. The change of the ammonia control room toxicity limit stated in UFSAR section 6.4.4.2.3 from 100 ppm to 300 ppm has been endorsed through the NRC based on more recent studies, including Regulatory Guide 1.78 and NUREG/CR-6624. The higher main control room ammonia toxicity limit was used in the analysis for all postulated ammonia spills fixed and mobile off site and onsite that could adversely affect control room habitability.
Basis for Not Requiring NRC Prior Approval The 50.59 review concluded that the UFSAR change can be made without prior NRC approval.
The associated change in the allowable toxic gas concentration for ammonia (for control room habitability) increases from 100 ppm to 300 ppm. The increase in the allowable toxic gas concentration from 100 ppm to 300 ppm has been reviewed and accepted by the NRC. The new toxic gas release point increases the concentration of ammonia that the control room operators potentially can be exposed to; however, the analysis results of the spill concluded the exposure to control room personnel is within the acceptance criteria with use of the toxic gas analyzer system and isolation/recirculation function of the HVAC in its current configuration. The new limiting ammonia release source and higher concentration acceptance limit does not increase the likelihood of a failure of the toxic gas analyzers because the toxic gas analyzer is capable of monitoring and responding to the higher analyzed concentration in its current configuration with no decrease in reliability. It was concluded that the new limiting release source of the ammonia spill will not increase the frequency of the accident because the frequency of barge accidents based on published data was determined to be extremely low. The consequences of failure of the toxic gas monitoring system and HVAC isolation/recirculation functions is not increased, and a failure with a different result is not created because of the redundancy in the design of the toxic gas monitoring system and fail safe design of the HVAC isolation dampers. An accident of a different Page 2 of 5
ATTACHMENT Summary Report of Completed Changes, Tests, and Experiments type is not created because even though a new limiting source for the ammonia spill source has been determined, the accident remains the same: a chemical spill of ammonia within 5 miles of the plant. A toxic gas spill of ammonia will not adversely affect any physical plant fission product barriers. Therefore the design basis limits for a fission product barrier are not exceeded or altered. The methodology used in the evaluation has not changed from the method described in the UFSAR.
3] Tracking Number: QC-E-2012-001 Unit: Unit 2 Activity Description The proposed activity supports the placement of eight Westinghouse OPTIMA2 Low Tin ZIRLO Lead Test Assemblies (LTAs) in the core. Low Tin ZIRLO channels are dimensionally the same as the presently used channels. The difference is that the chemical composition of the material has slightly lower permissible concentrations of Tin, Iron, and Oxygen while having higher concentration of Niobium, and contains no Chromium or Nickel second phase precipitates, to improve channel bow performance relative to the licensed Zircaloy 2 channel material. The LTAs will be placed in the core such that the maximum thermal limits in the LTAs remain less than the maximum thermal limits observed over the entire duration of the cycle (i.e., non-limiting core regions). Low Tin ZIRLO offers an opportunity for improved fuel channel dimensional stability.
Impact of Activity The analysis of the LTAs concluded that NRC accepted design bases are met. The proposed activity does not physically alter any other equipment, system performance, or operator actions that could affect any of the accidents in UFSAR Section 15.0, "Accident Analyses". The proposed activity does not affect overall performance of any system that could more than minimally increase the frequency of occurrence of any accident. The proposed activity does not cause any SSC to be operated outside its design or testing limit, or change any SSC design function.
Basis for Not Requiring NRC Prior Approval The methodology for adopting an LTA program is described in CENPD-287-P-A. LTAs are permitted in Technical Specification 4.2.1, Fuel Assemblies, which states "Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions." The proposed LTAs do not change the frequency of occurrence of an accident or malfunction evaluated in the UFSAR. The consequences of accidents evaluated in the UFSAR are not affected. No new accident or malfunction is created.
The LTAs were analyzed with applicable NRC approved codes and methods and have been shown to comply with the safety design bases. The LTAs will be placed in non-limiting core locations. Therefore, the proposed activities may be implemented without prior NRC approval.
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A1TACH MENT Summary Report of Completed Changes, Tests, and Experiments W4] Tracking Number: QC-E-2012-002 Unit: Unit 1 Activity Description This temporary change reroutes the Unit 1 Reactor Core Isolation Cooling (RCIC) steam supply condensate drain from its normal configuration (i.e., a common header with HPCI to the Main Condenser). A temporary hose for the RCIC Steam Line Condensate Drain will be routed to the Unit 1 Reactor Floor Drain Sump and discharge under the water level of the sump. The hose will be rated for at least 250 psig and 450 deg. F. The RCIC Steam Trap Bypass Valve (AO 1-1301-
- 32) will be maintained in the closed position for the duration of the hose installation. The high level drain pot alarm will not be defeated. The RCIC drain valve to the condenser (AO 1-1301-35) will also be maintained in the closed position during the duration of the installation to isolate the drain piping to the condenser. The RCIC Steam Header Inboard Drain Valve (AO 1-1301-34) will still automatically isolate the steam supply drain line to the condenser upon initiation of the RCIC system. This activity is being performed to allow the Unit I RCIC system to remain operable during repair of the High Pressure Coolant Injection (HPCI) drain valve AO 1-2301-30. The RCIC and HPCI Turbine Steam Supply Condensate Drain Lines tie together into a common header back to the Main Condenser.
Impact of Activity This temporary design change has a minimal impact on plant operations and the design bases of the system. The safety analyses described in the UFSAR are not affected. The rating of temporary components will exceed all maximum operating conditions for the temporary reroute of the condensate drain. UFSAR Section 5.4.6 states that the steam line drain bypass valves opens on high level in the drain pot. However, the RCIC Steam Trap Bypass Valve AO 1-1301-32 will be maintained in the closed position to ensure that the condensate will flow through the drain pot and steam trap during the time that this temporary change will be in place. This ensures that the condensate routed through the hose will not exceed the pressure-temperature rating of the hose and also ensures that excessive liquid does not enter the reactor building floor drain sump. The sump high level alarm function will not be defeated, so that the operators can take appropriate action if excessive condensate occurs.
Basis for Not Requiring NRC Prior Approval The evaluation concluded the temporary change does not adversely affect the reliability of the RCIC system or other mitigating systems available for use and that the fission product barriers would not be affected. There is no interaction with any initiators of an accident. The evaluation concluded that there was not more than a minimal increase in the frequency of an accident, in the likelihood of occurrence of a malfunction of an SSC, in the consequences of an accident, or the consequences of a malfunction of an SSC. The temporary change will not create the possibility of an accident of a different type or the possibility of a malfunction of an SSC with a different result.
The temporary change will not alter or change a design basis limit for a fission product barrier or result in a departure from the method of evaluation used in the safety analyses.
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ATTACHMENT Summary Report of Completed Changes, Tests, and Experiments 5] Tracking Number: QC-E-2012-003 Unit: Unit 1 Activity Description The proposed activity will add a new protective relaying scheme to isolate the Reserve Auxiliary Transformer 12 (RAT 12) upon detection of an open or loss of phase upstream of RAT 12. The new protective relaying scheme augments the existing protective devices which isolate RAT 12.
The new relay scheme monitors phase current input from existing Current Transformers on the high-voltage side of RAT 12 to detect an open or loss of phase condition, and on a detected open or loss of phase will initiate a transformer lockout. The open phase relay is provided with a short time delay allowing the detection scheme to differentiate between an open phase condition and a fault condition. This activity addresses a vulnerability identified during an event at Byron Station where a mechanical failure on the "C" phase to the Station Auxiliary Transformer (SAT) created a single phase voltage condition that propagated to the buses fed from the SAT.
Impact of Activity This activity will install a new relaying scheme to: (1) detect an open or loss of phase upstream of RAT 12, and (2) actuate the existing transformer lockout relays to isolate the transformer upon detection of an open or loss of phase condition. When RAT 12 is isolated, the feed to the associated 4kV buses will automatically be transferred to the Unit Auxiliary Transformer, if available. The actuation of the new scheme will produce the same results as the actuation of existing RAT 12 protection devices. The activity will protect the Class IE electrical system from an open or loss of phase condition. This protective scheme is a new; the initial installation of this activity will only alarm (the tripping action will not be armed). This approach allows an assessment of the functioning and response of the protective relaying scheme. After an appropriate time for assessment, the tripping function will be activated.
Basis for Not Requiring NRC Prior Approval The proposed activity does not adversely affect RAT 12 capacity or the existing automatic and manual switching capabilities involving the normal, reserve, or emergency feeds to the Station 4kV buses. The proposed activity does not adversely affect existing equipment protection, including protection from overcurrent, undervoltage, or degraded voltage conditions. There is no adverse impact on UFSAR-described design functions and the proposed activity will not adversely affect how the UFSAR functions are performed or controlled. However, the new trip system could result in a loss of offsite power to the 4kV buses on an open or loss of phase condition. The 50.59 review determined that due to the balancing of the positive effects (isolating a degraded power source) and the negligible negative effect (inappropriate isolation of a functioning power source), the proposed activity does not result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. The activity does not involve an adverse change to an element of a UFSAR-described evaluation methodology, or use of an alternative methodology, that is used in establishing the design bases or used in the safety analyses. The proposed activity involves the installation of an additional feature that will disconnect an unreliable power supply to the 4kV buses. Therefore, the proposed activity does not involve a test or experiment not described in the UFSAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design.
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