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Category:Letter type:SVPLTR
MONTHYEARSVPLTR 24-0030, ISFSI Annual Effluent Release Report2024-09-20020 September 2024 ISFSI Annual Effluent Release Report SVPLTR 24-0020, Registration of Use of Casks to Store Spent Fuel2024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 SVPLTR 23-0021, Registration of Use of Casks to Store Spent Fuel2023-06-20020 June 2023 Registration of Use of Casks to Store Spent Fuel SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report SVPLTR 23-0019, ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1)2023-05-0101 May 2023 ILT 22-1 (2023-301) Svpltr 23-0019 Post-Exam Submittal Letter (1) SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 SVPLTR 23-0004, Owners Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities2023-02-10010 February 2023 Owners Activity Report Submittal Dresden Nuclear Power Station 6500 North Dresden Road Morris, Il 60450 Fifth 10-Year Interval 2022 Refueling Outage Activities SVPLTR 22-0037, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2022-09-0707 September 2022 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 22-0024, Registration of Use of Casks to Store Spent Fuel2022-06-16016 June 2022 Registration of Use of Casks to Store Spent Fuel SVPLTR 22-0016, Unit 3, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 2 and Unit 3 Shroud Vertical Welds2022-06-0808 June 2022 Unit 3, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 2 and Unit 3 Shroud Vertical Welds SVPLTR 22-0017, Registration of Use of Casks to Store Spent Fuel2022-05-25025 May 2022 Registration of Use of Casks to Store Spent Fuel SVPLTR 21-0061, Core Operating Limits Report for Dresden Unit 2 Cycle 282021-11-19019 November 2021 Core Operating Limits Report for Dresden Unit 2 Cycle 28 SVPLTR 21-0057, Submittal of 10 CFR 72.48 Evaluation Summary Report2021-10-15015 October 2021 Submittal of 10 CFR 72.48 Evaluation Summary Report SVPLTR 21-0030, Registration of Use of Casks to Store Spent Fuel2021-06-0202 June 2021 Registration of Use of Casks to Store Spent Fuel SVPLTR 21-0028, 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 2020 Annual Radiological Environmental Operating Report SVPLTR 21-0027, Radioactive Effluent Release Report and Offsite Dose Calculation Manual2021-04-22022 April 2021 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 21-0005, Submittal of Analytical Evaluation of Isolation Condenser Nozzle to Shell Weld Flaw Indications (ISI Weld 3/2/1302A-12/12-8)2021-01-29029 January 2021 Submittal of Analytical Evaluation of Isolation Condenser Nozzle to Shell Weld Flaw Indications (ISI Weld 3/2/1302A-12/12-8) SVPLTR 20-0053, Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 3 Top Guide Rim Weld2020-10-15015 October 2020 Deviation from BWR Vessel and Internals Project (BWRVIP) Guideline - Inspection of Unit 3 Top Guide Rim Weld SVPLTR 20-0045, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-09-0101 September 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 20-0037, Response to Apparent Violation in NRC Inspection Report 05000237/2020012 and 05000249/2020012; EA-20-0532020-07-0202 July 2020 Response to Apparent Violation in NRC Inspection Report 05000237/2020012 and 05000249/2020012; EA-20-053 SVPLTR 20-0027, Registration of Use of Casks to Store Spent Fuel2020-05-14014 May 2020 Registration of Use of Casks to Store Spent Fuel SVPLTR 20-0014, Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2020-04-21021 April 2020 Submittal of 2019 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 20-0010, Fifth 10-Year Interval 2019 Refueling Outage Activities2020-02-13013 February 2020 Fifth 10-Year Interval 2019 Refueling Outage Activities SVPLTR 19-0049, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-09-10010 September 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 19-0031, Registration of Use of Casks to Store Spent Fuel2019-06-14014 June 2019 Registration of Use of Casks to Store Spent Fuel SVPLTR 19-0020, Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2019-04-19019 April 2019 Submittal of 2018 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 19-0005, Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities2019-02-0808 February 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities SVPLTR 18-0025, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2018-08-15015 August 2018 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 18-0020, Corrected 2017 Radioactive Effluent Release Report2018-06-28028 June 2018 Corrected 2017 Radioactive Effluent Release Report SVPLTR 18-0018, Registration of Use of Casks to Store Spent Fuel2018-06-14014 June 2018 Registration of Use of Casks to Store Spent Fuel SVPLTR 18-0012, Submittal of 2017 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2018-04-24024 April 2018 Submittal of 2017 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 18-0007, Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revisions 17 and 182018-03-0101 March 2018 Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revisions 17 and 18 SVPLTR 17-0033, Submittal of Corrected 2016 Radioactive Effluent Release Report for January Through December2017-08-29029 August 2017 Submittal of Corrected 2016 Radioactive Effluent Release Report for January Through December SVPLTR 17-0026, Registration of Use of Casks to Store Spent Fuel2017-06-0606 June 2017 Registration of Use of Casks to Store Spent Fuel SVPLTR 17-0017, Submittal of 2016 Radioactive Effluent Release Report2017-04-26026 April 2017 Submittal of 2016 Radioactive Effluent Release Report SVPLTR 16-0027, 2016 Dresden Nuclear Station Initial License Examination Proposed Exam Files - Licensee Letter Transmitting the Proposed Examination/Test to the NRC2016-12-0101 December 2016 2016 Dresden Nuclear Station Initial License Examination Proposed Exam Files - Licensee Letter Transmitting the Proposed Examination/Test to the NRC SVPLTR 16-0061, Core Operating Limits Report for Unit 3 Cycle 252016-11-21021 November 2016 Core Operating Limits Report for Unit 3 Cycle 25 SVPLTR 16-0018, Transmittal of 2015 Radioactive Effluent Release Report and Offsite Dose Calculation Manual2016-04-25025 April 2016 Transmittal of 2015 Radioactive Effluent Release Report and Offsite Dose Calculation Manual SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation2016-04-0808 April 2016 Submittal of Post Accident Monitoring Report Instrumentation SVPLTR 16-0001, Cyber-Security Ms 1 Thru 7 Inspection 2014 405; Notification of Completion of Corrective Actions2016-01-21021 January 2016 Cyber-Security Ms 1 Thru 7 Inspection 2014 405; Notification of Completion of Corrective Actions SVPLTR 15-0070, Core Operating Limits Report for Cycle 24A2015-12-15015 December 2015 Core Operating Limits Report for Cycle 24A SVPLTR 15-0065, Core Operating Limits Report for Cycle 252015-11-16016 November 2015 Core Operating Limits Report for Cycle 25 SVPLTR 15-0059, Core Operating Limits Report, Cycle 242015-10-25025 October 2015 Core Operating Limits Report, Cycle 24 SVPLTR 15-0056, 1, 2 and 3 - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2015-09-0404 September 2015 1, 2 and 3 - Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report SVPLTR 15-0055, Notification of Readiness for NRC 95001 Inspection2015-08-25025 August 2015 Notification of Readiness for NRC 95001 Inspection SVPLTR 15-0052, Response to Preliminary White Finding2015-08-14014 August 2015 Response to Preliminary White Finding SVPLTR 15-0046, ISFSI - Registration of Use of Casks to Store Spent Fuel2015-07-17017 July 2015 ISFSI - Registration of Use of Casks to Store Spent Fuel 2024-09-20
[Table view] Category:Report
MONTHYEARRS-24-126, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4)2024-10-31031 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in Accordance with 10 CFR 2.390(b)(4) RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . ML24271A0292024-09-26026 September 2024 Enclosure - Dresden Nuclear Power Station, Unit 1 - Site Visit Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 ML24071A1232024-03-0707 March 2024 Staff’S Assessment of Hazards from a Hypothetical Rupture and Subsequent Release of Natural Gas of the Three Rivers Pipeline Lateral to the Dresden Power Station Units 2 and 3 ML23180A0402023-06-21021 June 2023 Technical Requirements Manual 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-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 ML22047A1322022-02-15015 February 2022 Owners Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities RS-21-086, Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2021-08-23023 August 2021 Supplement to Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E 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 ML20300A2352020-11-17017 November 2020 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting RS-20-070, Defueled Safety Analysis Report Update, Revision 102020-06-22022 June 2020 Defueled Safety Analysis Report Update, Revision 10 RS-19-093, Secondary Containment Drawdown Analysis2019-10-17017 October 2019 Secondary Containment Drawdown Analysis ML18138A3852019-03-0606 March 2019 Staff Assessment of Flood Hazard Integrated Assessment (CAC Nos. MG0221 and MG0222; EPID L-2017-JLD-0050) SVPLTR 19-0005, Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities2019-02-0808 February 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities RS-18-077, Defueled Safety Analysis Report Update, Revision 92018-06-20020 June 2018 Defueled Safety Analysis Report Update, Revision 9 ML18082A0812018-03-13013 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-conformances Identified in Response to Regulatory Issues Summary 2015-06, Tornado Missile... RS-18-003, 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 Conditions2018-01-12012 January 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 ML18052A4862017-02-12012 February 2017 Owner'S Activity Report Submittal; Fifth 10-Year Interval 2017 Refueling Outage Activities ML16291A0212016-11-0808 November 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 RS-16-124, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML16190A1162016-07-0606 July 2016 2015 Regulatory Commitment Change Summary Report RS-16-100, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation2016-04-0808 April 2016 Submittal of Post Accident Monitoring Report Instrumentation ML15307A0562015-11-0404 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanisms Reevaluation RS-15-265, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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) ML15215A3372015-07-30030 July 2015 Holtec International Report No. HI-2146153, Revision 2, Licensing Report for the Criticality Analysis of the Dresden Unit 2 and 3 SEP for Atrium 10XM Fuel Design ML15097A5192015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Relating to Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi ML15007A4912015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) SVPLTR 15-0014, Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities2015-02-11011 February 2015 Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities RS-14-310, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality2014-12-30030 December 2014 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Methodology and Proposed Change to Technical Specification 4.3.1, Criticality 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 RS-14-208, Third Six-Month Status Report in Response to 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)2014-08-28028 August 2014 Third Six-Month Status Report in Response to 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) 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 ML14115A2692014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident RS-14-122, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reevaluation Report - Redacted2014-05-19019 May 2014 Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reevaluation Report - Redacted ML14153A0062014-04-29029 April 2014 Revision 4 to Local Intense Precipitation Evaluation Report RS-14-067, 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..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.. SVPLTR 14-0013, Owner'S Activity Report Submittal Fifth 10-Year Interval 2013 Refueling Outage Activities2014-02-28028 February 2014 Owner'S Activity Report Submittal Fifth 10-Year Interval 2013 Refueling Outage Activities 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. ML13220A2382013-11-22022 November 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13317A8292013-11-20020 November 2013 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Dresden Nuclear Power Station Units 2 and 3, TAC Nos.: MF1046 and MF1047 ML13126A1862013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 6 of 13 RS-13-067, Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 11 of 132013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 11 of 13 ML13126A1872013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 7 of 13 ML13126A1882013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 8 of 13 ML13126A1892013-03-28028 March 2013 Seismic Walkdown Report in Response to 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for Dresden, Unit 3, Report No. RS-13-06, Part 9 of 13 2024-09-26
[Table view] Category:Miscellaneous
MONTHYEARML24271A0292024-09-26026 September 2024 Enclosure - Dresden Nuclear Power Station, Unit 1 - Site Visit Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations SVPLTR 24-0010, Owners Activity Report (OAR-1) for D2R282024-03-15015 March 2024 Owners Activity Report (OAR-1) for D2R28 ML22047A1322022-02-15015 February 2022 Owners Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18138A3852019-03-0606 March 2019 Staff Assessment of Flood Hazard Integrated Assessment (CAC Nos. MG0221 and MG0222; EPID L-2017-JLD-0050) SVPLTR 19-0005, Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities2019-02-0808 February 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2018 Refueling Outage Activities ML18082A0812018-03-13013 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-conformances Identified in Response to Regulatory Issues Summary 2015-06, Tornado Missile... ML18052A4862017-02-12012 February 2017 Owner'S Activity Report Submittal; Fifth 10-Year Interval 2017 Refueling Outage Activities ML16291A0212016-11-0808 November 2016 Staff Review of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2.1 RS-16-124, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML16190A1162016-07-0606 July 2016 2015 Regulatory Commitment Change Summary Report RS-16-100, Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal2016-06-30030 June 2016 Mitigating Strategies Flood Hazard Assessment (Msfha) Submittal SVPLTR 16-0017, Submittal of Post Accident Monitoring Report Instrumentation2016-04-0808 April 2016 Submittal of Post Accident Monitoring Report Instrumentation ML15307A0562015-11-0404 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood Causing Mechanisms Reevaluation RS-15-265, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15097A5192015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Relating to Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi ML15007A4912015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) SVPLTR 15-0014, Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities2015-02-11011 February 2015 Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities RS-14-208, Third Six-Month Status Report in Response to 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)2014-08-28028 August 2014 Third Six-Month Status Report in Response to 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-14-122, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reevaluation Report - Redacted2014-05-19019 May 2014 Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reevaluation Report - Redacted ML14153A0062014-04-29029 April 2014 Revision 4 to Local Intense Precipitation Evaluation Report RS-14-067, 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..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.. SVPLTR 14-0013, Owner'S Activity Report Submittal Fifth 10-Year Interval 2013 Refueling Outage Activities2014-02-28028 February 2014 Owner'S Activity Report Submittal Fifth 10-Year Interval 2013 Refueling Outage Activities 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 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 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 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 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 ML12348A2582012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 4 of 11 ML12348A2732012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 1 of 11 ML12348A2722012-11-15015 November 2012 12Q0108.30-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 2, Part 7 of 7 ML12348A2562012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 2 of 11 ML12348A2572012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 3 of 11 ML12348A2712012-11-15015 November 2012 12Q0108.30-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 2, Part 6 of 7 ML12348A2592012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 5 of 11 ML12348A2602012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 6 of 11 ML12348A2612012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 7 of 11 ML12348A2622012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 8 of 11 ML12348A2632012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 9 of 11 ML12348A2642012-11-15015 November 2012 12Q0106.30-R-002, Rev. 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 3, Part 10 of 11 ML12348A2662012-11-15015 November 2012 12Q0108.30-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 2, Part 1 of 7 ML12348A2672012-11-15015 November 2012 12Q0108.30-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 2, Part 2 of 7 ML12348A2682012-11-15015 November 2012 12Q0108.30-R-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Dresden Nuclear Power Station, Unit 2, Part 3 of 7 2024-09-26
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Dresden Generating Station
- ,
- 7
) !liV Exelon Generation 6500 North Dresden Road Morris. IL 60450 www,exeloncorp,com SVPLTR # 16-0017 April 8, 2016 ,
U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Post Accident Monitoring Report The attached report is submitted in accordance with Dresden Nuclear Power Station, Unit 3 Technical Specifications 3.3.3.1, "Post Accident Monitoring (PAM} Instrumentation," and 5.6.6, "Post Accident Monitoring Instrumentation Report." The report is required due to the ,
inoperability of one Main Steam Line Isolation Valve position indication for a period in excess of the 30 day restoration time. Accordingly, this report is due on April 13, 2016.
There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.
Respectfully,
~~-
Peter J Karaba Site Vice President Dresden Nuclear Power Station
Enclosure:
Dresden Unit 3 Post Accident Monitoring Report cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station
Dresden Unit 3 Post Accident Monitoring Report This Report is being submitted for Dresden Nuclear Power Station (DNPS), Unit 3 in accordance with Technical Specification (TS) 5.6.6, "Post Accident Monitoring Instrumentation Report." Additionally, TS 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," requires two channels of Penetration Flow Path Primary Containment Isolation Valve (PCIV) position indication to be Operable during plant operation in Modes 1 and 2. On February 29, 2016, the position indication for one main steam isolation valve (MSIV) was declared inoperable and TS 3.3.3.1, Condition A was entered. TS 3.3.3.1, Condition A requires channel restoration to Operable status in 30 days. If TS 3.3.3.1 Condition A is not satisfied in 30 days, then TS 3.3.3.1, Condition 8 is entered. Exelon Generation Company, LLC has determined that the position indication circuit cannot be restored within 30 days; therefore, TS 3.3.3.1, Condition 8 requires initiation of action in accordance with TS 5.6.6. This Administrative TS requires the submittal of a written report outlining the preplanned alternate method of monitoring, the cause
. of the inoperability, and the plans and schedule for restoring the instrument to Operable status within the following 14 days.
Description of Issue On February 29, 2016, while at full power, it was noted that the open indicating light for MSIV 3-0203-18 in the Main Control Room (MGR) was not lit. Alternate verification through the use of steam line flow and computer points monitoring valve position was utilized to verify that the valve was open; however, without the positive open indication in the MGR, the valve position was declared inoperable.
Further troubleshooting has determined that the source of the position indication issue is located insicfe DNPS, Unit 3 Drywell and cannot be accessed to affect repairs until the unit is shutdown.
Cause of the lnoperabilitv and Action Taken A circuit fault has rendered the MSIV 3-0203-18 valve position indication circuit unreliable. This fault is preventing positive verification of the valve position which is required by PAM PCIV position indications in accordance with TS 3.3.3.1. Troubleshooting under Work Order 01902902-01 has determined that the fault for the MSIV 3-0203-18 position indication circuit is located within the DNPS, Unit 3 Drywell.
Pre-planned Alternate Method of Monitoring With reliable closed valve indications, the two MSIV closed lights alone would provide the MGR with confirmation of isolation of an individual main steam line as required by TS 3.3.3.1.
The alternate method for monitoring isolation of the 38 main steam line as a penetration flow path is fulfilled by three indications.
Due to the unreliable closed indication for the 3-0203-1 8, indication of valve position may be determined from other system parameters including main steam line flow through the following indicators:
Fl 3-0640-23A 3A MN STM LINE FLOW Fl 3-0640-238 38 MN STM LINE FLOW Fl 3-0640-23C 3C MN STM LINE FLOW
Fl 3-0640-230 30 MN STM LINE FLOW In addition, the second MSIV in series, 3-0203-28, is fully operable, capable of isolating the line upon an isolation signal. Position indication for the 3-0203-28 MSIV.is available in the MCR, as required by TS 3.3.3.1, and can be used to show the 38 main steam line is isolated.
Combining the main steam line flow for the 38 main steam line, the closed indication of the outboard MSIV 3-0203-28, and the MSIV 3-0203-18 shown "not open" by computer point C176 provides the alternate method to assess isolation of the 38 Main Steam Line.
Plan and Schedule for Restoring the Instrumentation Channels The PAM instrumentation is planned to be restored during an outage of sufficient duration, either a forced outage or the upcoming 2016 ONPS, Unit 3 Refueling Outage 03R24.
Dresden Generating Station
- ,
- 7
) !liV Exelon Generation 6500 North Dresden Road Morris. IL 60450 www,exeloncorp,com SVPLTR # 16-0017 April 8, 2016 ,
U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Renewed Facility Operating License No. DPR-25 NRC Docket No. 50-249
Subject:
Post Accident Monitoring Report The attached report is submitted in accordance with Dresden Nuclear Power Station, Unit 3 Technical Specifications 3.3.3.1, "Post Accident Monitoring (PAM} Instrumentation," and 5.6.6, "Post Accident Monitoring Instrumentation Report." The report is required due to the ,
inoperability of one Main Steam Line Isolation Valve position indication for a period in excess of the 30 day restoration time. Accordingly, this report is due on April 13, 2016.
There are no regulatory commitments contained in this submittal. Should you have any questions concerning this letter, please contact Mr. Bruce Franzen at (815) 416-2800.
Respectfully,
~~-
Peter J Karaba Site Vice President Dresden Nuclear Power Station
Enclosure:
Dresden Unit 3 Post Accident Monitoring Report cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Dresden Nuclear Power Station
Dresden Unit 3 Post Accident Monitoring Report This Report is being submitted for Dresden Nuclear Power Station (DNPS), Unit 3 in accordance with Technical Specification (TS) 5.6.6, "Post Accident Monitoring Instrumentation Report." Additionally, TS 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," requires two channels of Penetration Flow Path Primary Containment Isolation Valve (PCIV) position indication to be Operable during plant operation in Modes 1 and 2. On February 29, 2016, the position indication for one main steam isolation valve (MSIV) was declared inoperable and TS 3.3.3.1, Condition A was entered. TS 3.3.3.1, Condition A requires channel restoration to Operable status in 30 days. If TS 3.3.3.1 Condition A is not satisfied in 30 days, then TS 3.3.3.1, Condition 8 is entered. Exelon Generation Company, LLC has determined that the position indication circuit cannot be restored within 30 days; therefore, TS 3.3.3.1, Condition 8 requires initiation of action in accordance with TS 5.6.6. This Administrative TS requires the submittal of a written report outlining the preplanned alternate method of monitoring, the cause
. of the inoperability, and the plans and schedule for restoring the instrument to Operable status within the following 14 days.
Description of Issue On February 29, 2016, while at full power, it was noted that the open indicating light for MSIV 3-0203-18 in the Main Control Room (MGR) was not lit. Alternate verification through the use of steam line flow and computer points monitoring valve position was utilized to verify that the valve was open; however, without the positive open indication in the MGR, the valve position was declared inoperable.
Further troubleshooting has determined that the source of the position indication issue is located insicfe DNPS, Unit 3 Drywell and cannot be accessed to affect repairs until the unit is shutdown.
Cause of the lnoperabilitv and Action Taken A circuit fault has rendered the MSIV 3-0203-18 valve position indication circuit unreliable. This fault is preventing positive verification of the valve position which is required by PAM PCIV position indications in accordance with TS 3.3.3.1. Troubleshooting under Work Order 01902902-01 has determined that the fault for the MSIV 3-0203-18 position indication circuit is located within the DNPS, Unit 3 Drywell.
Pre-planned Alternate Method of Monitoring With reliable closed valve indications, the two MSIV closed lights alone would provide the MGR with confirmation of isolation of an individual main steam line as required by TS 3.3.3.1.
The alternate method for monitoring isolation of the 38 main steam line as a penetration flow path is fulfilled by three indications.
Due to the unreliable closed indication for the 3-0203-1 8, indication of valve position may be determined from other system parameters including main steam line flow through the following indicators:
Fl 3-0640-23A 3A MN STM LINE FLOW Fl 3-0640-238 38 MN STM LINE FLOW Fl 3-0640-23C 3C MN STM LINE FLOW
Fl 3-0640-230 30 MN STM LINE FLOW In addition, the second MSIV in series, 3-0203-28, is fully operable, capable of isolating the line upon an isolation signal. Position indication for the 3-0203-28 MSIV.is available in the MCR, as required by TS 3.3.3.1, and can be used to show the 38 main steam line is isolated.
Combining the main steam line flow for the 38 main steam line, the closed indication of the outboard MSIV 3-0203-28, and the MSIV 3-0203-18 shown "not open" by computer point C176 provides the alternate method to assess isolation of the 38 Main Steam Line.
Plan and Schedule for Restoring the Instrumentation Channels The PAM instrumentation is planned to be restored during an outage of sufficient duration, either a forced outage or the upcoming 2016 ONPS, Unit 3 Refueling Outage 03R24.