|
---|
Category:Letter type:RS
MONTHYEARRS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 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-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary 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-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 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-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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-23-080, 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-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-23-042, 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-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H 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-23-003, 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-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request 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-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-101, 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-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement 2024-07-31
[Table view] Category:Report
MONTHYEARSVPLTR 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 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 Owner'S 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 ML13126A1792013-03-28028 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 1 of 13 ML13126A1802013-03-28028 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 13 of 13 ML13126A1812013-03-28028 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 2 of 13 ML13126A1832013-03-28028 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 3 of 13 ML13126A1842013-03-28028 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 4 of 13 ML13126A1852013-03-28028 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 5 of 13 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 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 2024-03-07
[Table view] Category:Miscellaneous
MONTHYEARSVPLTR 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 Owner'S 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 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 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 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 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 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 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 ML12348A2692012-11-15015 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 4 of 7 ML12348A2702012-11-15015 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 5 of 7 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 2024-03-15
[Table view] |
Text
Nuclear Exelon Generation Company, LLCwww.exeloncorp.com 4300 Winfield Road Warrenville, IL 60555 RS-11-171 October 28, 2011 10 CFR 50.46(a)(3)(ii)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50
-237 and 50-249
Subject:
Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Exelon Generation Company, LLC (EGC) is submitting this letter and its attachments to meet the annual reporting requirements of the Emergency Core Cooling System (ECCS) Evaluation Model changes and errors for Dresden Nuclear Power Station (DNPS), Units 2 and 3.
EGC received notification from Westinghouse which identified that incorrect R-factors have been used in the DNPS, Units 2 and 3 LOCA reload analyses. The impact due to this error was determined to be 18
°F in the worst case and is applied conservatively to all of the Westinghouse fuel.The error resulted in an increase to the existing licensing peak cladding temperature (PCT) of 2164
°F for DNPS, Units 2 and 3. The updated DNPS, Units 2 and 3 licensing basis PCT is 2182
°F as shown in Attachments 2 and 3 for Westinghouse fuel. This value is within the 2200°F acceptance criterion of 10 CFR 50.46.
The attachments to this letter provide updated information regarding the PCT value for Westinghouse fuel in DNPS, Units 2 and 3. Note 12 of Attachment 4 provides details related to the error discussed above.
U. S. Nuclear Regulatory Commission October 28, 2011 Page 2 There are no regulatory commitments contained in this letter. If there are any questions concerning this letter, please contact Mr. Joseph A Bauer at (630) 657-2804.
Respectfully, David M. Gullott Manager - Licensing and Regulatory Affairs Attachments:
1.Dresden Nuclear Power Station Unit 2 -10 CFR 50.46 Report (GE Fuel) 2.Dresden Nuclear Power Station Unit 2 - 10 CFR 50.46 Report (Westinghouse Fuel) 3.Dresden Nuclear Power Station Unit 3 - 10 CFR 50.46 Report (Westinghouse Fuel) 4.Dresden Nuclear Power Station Units 2 and 3 - 10 CFR 50.46 Report Assessment Notes Dresden Nuclear Power Station Unit 2 10 CFR 50.46 Report (GE Fuel)
Fuel: Limiting Fuel Type:
Limiting Single Failure:
Limiting Break Size and Location:
Reference Peak Cladding Temperature (PCT)
Dresden Nuclear Power Station, Unit 2 SAFER/GESTR-LOCA 10/28/2011 22 The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, SAFER/GESTR Application Methodology, NEDE-23785-1-PA, General Electric Company, Revision 1, October 1984."SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Dresden Nuclear Station 2 and 3 and Quad Cities Nuclear Station Units 1 and 2," NEDC-32990P, Revision 2, GE Nuclear Energy, September 2003.
9x9-2, ATRIUM-9B and GE14 GE14 Diesel Generator 1.0 Double-Ended Guillotine in a Recirculation Suction Pipe 2110°F PLANT NAME:
ECCS EVALUATION MODEL:
REPORT REVISION DATE:
CURRENT OPERATING CYCLE:
ANALYSIS OF RECORD Evaluation Model:
Calculations:
Page 1 of 2 Dresden Nuclear Power Station Unit 2 10 CFR 50.46 Report (GE Fuel)
MARGIN ALLOCATION A.PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated December 6, 2001 (See Note 1)
APCT = 0°F 10 CFR 50.46 report dated November 25, 2002 (See Note 2)
APCT = 0°F 10 CFR 50.46 report dated November 25, 2003 (See Note 3)
APCT = 0°F 10 CFR 50.46 report dated November 24, 2004 (See Note 4)
LPCT = 0°F 10 CFR 50.46 report dated November 16, 2005 (See Note 5)
OPCT = 0°F 10 CFR 50.46 report dated November 9, 2006 (See Note 6)
OPCT = 0°F 10 CFR 50.46 report dated October 31, 2007 (See Note 7)
APCT = 0°F 10 CFR 50.46 report dated October 31, 2008 (See Note 8)
OPCT = 0°F 10 CFR 50.46 report dated October 30, 2009 (See Note 9)
APCT = 0°F 10 CFR 50.46 report dated October 29, 2010 (See Note 10)
APCT = 0°F 10 CFR 50.46 report dated July 28, 2011 (See Note 11)
APCT = 85°F Net PCT 2195°F B.CURRENT LOCA MODEL ASSESSMENTS None APCT = 0°F Total PCT change from current assessments EAPCT = 0°F Cumulative PCT change from current assessments E I APCT I= 0°F Net PCT 2195°F Page 2 of 2 Dresden Nuclear Power Station Unit 2 10 CFR 50.46 Report (Westinghouse Fuel)
PLANT NAME:
ECCS EVALUATION MODEL:
REPORT REVISION DATE:
CURRENT OPERATING CYCLE:
ANALYSIS OF RECORD Evaluation Model:
Calculations:
Fuel Analyzed in Calculation:
Limiting Fuel Type:
Limiting Single Failure:
Limiting Break Size and Location:
Reference Peak Cladding Temperature (PCT)
Dresden Nuclear Power Station, Unit 2 USA5 10/28/2011 22"Westinghouse BWR ECCS Evaluation Model:
Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-16078-P-A, November 2004."Dresden 2 & 3 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TRO21 DR-LOCA, Revision 5, Westinghouse Electric Company LLC, October 2009.
SVEA-96 Optima2 SVEA-96 Optima2 LPCI injection valve 1.0 Double-Ended Guillotine Break in the Recirculation Pump Suction Line 2150°F Page 1 of 2 Dresden Nuclear Power Station Unit 2 10 CFR 50.46 Report (Westinghouse Fuel)
MARGIN ALLOCATION A.PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 30, 2009 (See Note 9)
APCT = 2°F 10 CFR 50.46 report dated October 29, 2010 (See Note 10)
APCT = 12°F Net PCT 2164°F B.CURRENT LOCA MODEL ASSESSMENTS R-factor error (see Note 12)
APCT = 18°F Total PCT change from current assessments EOPCT =18°F Cumulative PCT change from current assessments E I OPCT I= 18-F Net PCT 2182°F Page 2 of 2 Dresden Nuclear Power Station Unit 3 10 CFR 50.46 Report (Westinghouse Fuel)
Fuel Analyzed in Calculation:
Limiting Fuel Type:
Limiting Single Failure:
Limiting Break Size and Location:
Reference Peak Cladding Temperature (PCT)
Dresden Nuclear Power Station, Unit 3 USA5 10/28/2011 22"Westinghouse BWR ECCS Evaluation Model:
Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel," WCAP-16078-P-A, November 2004."Dresden 2 & 3 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TRO21 DR-LOCA, Revision 5, Westinghouse Electric Company LLC, October 2009.
SVEA-96 Optima2 SVEA-96 Optima2 LPCI injection valve 1.0 Double-Ended Guillotine Break in the Recirculation Pump Suction Line 2150°F PLANT NAME:
ECCS EVALUATION MODEL:
REPORT REVISION DATE:
CURRENT OPERATING CYCLE:
ANALYSIS OF RECORD Evaluation Model:
Calculations:
Page 1 of 2 Dresden Nuclear Power Station Unit 3 10 CFR 50.46 Report (Westinghouse Fuel)
MARGIN ALLOCATION A.PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 report dated October 30, 2009 (See Note 9)
LPCT = 2°F 10 CFR 50.46 report dated October 29, 2010 (See Note 10) zPCT = 12°F Net PCT 2164°F B.CURRENT LOCA MODEL ASSESSMENTS R-factor error (see Note 12)
OPCT = 18°F Total PCT change from current assessments EAPCT =18°F Cumulative PCT change from current assessments E I APCT I= 18-F Net PCT 2182°F Page 2 of 2 Dresden Nuclear Power Station Units 2 and 3 10 CFR 50.46 Report Assessment Notes 1.Prior LOCA Model Assessment The 10 CFR 50.46 letter dated December 6, 2001, reported a new LOCA analysis to support extended power uprate (EPU) and transition to GE14 fuel for Dresden Unit 2 Cycle 18. The same report assessed impact of errors in Framatome ANP LOCA analysis model for Dresden Unit 3 Cycle 17 at pre-EPU power level.
[
Reference:
Letter from Preston Swafford (PSLTR: #01-0122) (Exelon) to USNRC,"Plant Specific ECCS Evaluation Changes
-10 CFR 50.46 Report," December 6, 2001.]
2.Prior LOCA Model Assessment Unit 3 implemented GE LOCA analysis and GE14 fuel with Dresden Unit 3 Cycle 18 startup on October 25, 2002. Therefore, both Dresden Units 2 and 3 are being maintained under the same LOCA analysis. In the referenced letter, the impact of GE LOCA error in the WEVOL code was reported for Dresden Units 2 and 3 and determined to be negligible.
[
Reference:
Letter from Robert J. Hovey (RHLTR: #02-0083) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 25, 2002.]
3.Prior LOCA Model Assessment The annual 10 CFR 50.46 report provided information on the LOCA model assessments for SAFER LevelNolume table error and Steam Separator pressure drop error. In the referenced letter, the impact of these two GE LOCA errors was reported to be negligible.
[
Reference:
Letter from Robert J. Hovey (RHLTR: #03-0077) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 25, 2003.]
4.Prior LOCA Model AssessmentThe referenced annual 10 CFR 50.46 report provided information on reload of GE14 fuel for Dresden Unit 2 Cycle 19 and impact of postulated hydrogen-oxygen recombination on PCT. GE determined that there is no PCT impacts due to the new reload of GE14 fuel or from the effect of the postulated hydrogen -oxygen recombination.
[
Reference:
Letter from Danny Bost (SVPLTR: #04-0075) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes -10 CFR 50.46 Report," November 24, 2004.]
Page 1 of 4 Dresden Nuclear Power Station Units 2 and 3 10 CFR 50.46 Report Assessment Notes 5.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter reported the PCT impact of reload of GE14 fuel for D3C19 starting on December 8, 2004. Also, the letter reported the GE LOCA evaluation for Unit 3, which implemented the lower sectional replacement and T-box clamp repairs. GE determined that there is no PCT impacts because of the change due to the new reload of GE14 fuel and the lower sectional replacement and T-box clamp repairs.
[
Reference:
Letter from Danny Bost (SVPLTR:#05-0044) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 16, 2005.]
6.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter reported the PCT impact of the reload of GE14 fuel for D2C20. The letter also reported an evaluation of increased leakage of less than 5 gpm at runout condition in core spray line flow due to crack growth identified during D2R19 outage. Additionally, a GE evaluation of the small break for impact due to top-peak axial power shape was reported in this letter.
The impact due to these changes on the licensing basis PCT was reported as zero.
[
Reference:
Letter from Danny Bost (SVPLTR: #
06-0054) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," November 9, 2006.]
7.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter reported D3C20 startup with the first reload of Westinghouse Optima2 fuel and implementation of the Westinghouse LOCA analysis. No error was reported for GE LOCA applicable to operation of GE14 fuel in the Unit 2 core and Unit 3 core.
[
Reference:
Letter from Danny Bost (SVPLTR: #07-0049) (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," October 31, 2007.]
8.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. No error was reported for GE LOCA applicable to operation of GE14 fuel in the Unit 2 core and Unit 3 core.
[
Reference:
Letter from David Wozniak (SVPLTR: #
08-0059 (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," October 31, 2008.]
Page 2 of 4 Dresden Nuclear Power Station Units 2 and 3 10 CFR 50.46 Report Assessment Notes 9.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3. The letter updated the vessel leakage between the lower shroud and the downcomer.
Westinghouse evaluated this change and demonstrated that all 10 CFR 50.46 criteria were satisfied. This evaluation resulted in maximum PCT impact due to the change in vessel leakage of 2°F for Optima2 fuel with the licensing basis PCT of 2152°F. The vessel leakage identified by GE to have an insignificant impact on the PCT transientportion of the LOCA event. Therefore, a PCT impact of 0°F is reported for GE14 fuel with the licensing basis PCT remaining at 2110°F. Note: The new analysis is documented in Revision 5 of the Dresden LOCA Report and contains the same information as stated above and transmitted to the NRC in the Reference.
[
Reference:
Letter from Timothy Hanley (SVPLTR:#09-0052 (Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes -
10 CFR 50.46 Report," October 30, 2009.]
10.Prior LOCA Model Assessment The referenced letter provided the annual 10 CFR 50.46 report for Units 2 and 3.
The letter reported the replacement of core spray lower sectional piping in Dresden Unit 2 during D2R21. Both GEH and Westinghouse evaluated the core spray leakage due to this modification and concluded that the PCT impact was 0°F. The letter also identified a change in input for modeling bypass hole flow coefficient in the Westinghouse LOCA analysis. The impact on PCT due to this change was determined by Westinghouse to be 12°F. For D2C22 and D3C22, Westinghouse established a MAPLHGR limit for the fresh bundles to accommodate the change. For 10 CFR 50.46 reporting purposes, the PCT impact is conservatively applied to all bundle types including the fresh bundles.
This PCT update will remain in effect only until the MAPLHGR limits for all bundles in future Dresden Unit 2 and Unit 3 cores are evaluated for the change in bypass hole flow coefficient. The latter issue pertains only to Westinghouse SVEA-96 Optima2 fuel.
[
Reference:
Letter from Jeffrey Hansen (RS-10-191, Exelon) to USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 Report," October 29, 2010.]
Page 3 of 4 Dresden Nuclear Power Station Units 2 and 3 10 CFR 50.46 Report Assessment Notes 11.Prior LOCA Model Assessment The referenced letter provided the 30-day 10 CFR 50.46 report for Dresden Unit 2 for fuel type GE14. The 30-day 10 CFR 50.46 report was submitted for Dresden unit 2 due to errors reported by GEH in the LOCA methodology associated with the GE14 fuel inDresden Unit 2.
Dresden Unit 3 is not affected because it does not have GNF fuel loaded in the core. GEH identified two errors. One error involves the way input coefficients are used to direct the deposition of gamma radiation energy produced by the fuel.Correcting this error results in a PCT increase of 75°F. The other error involves the contribution of heat from gamma ray absorption by the channel. The gamma ray absorption by the channel was found to have been minimized. Correcting this error results in a PCT increase of 10°F. The total impact of both errors is conservatively taken to be 85°F. The Dresden Unit 2 core has one batch of GNF fuel remaining in the core and is not the limiting fuel type. This fuel is scheduled to be discharged in the autumn of 2011 refueling outage (D2R22). These errors apply only to the GE14 fuel in the Dresden Unit 2 core. The LOCA analysis for the Westinghouse fuel in the Dresden Unit 2 core is not affected by the errors discussed in this note.
[
Reference:
Letter from Jeffrey Hansen (RS-1 1-124, Exelon) to the USNRC, "Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14," July 28, 2011.]
12.Current LOCA Model Assessment Westinghouse reported errors in the current Dresden LOCA analysis associated with the use of incorrect R-factors [Reference]. The impact due to this change was determined to be 18°F in PCT update. For 10 CFR 50.46 reporting purposes, the PCT update is conservatively applied to all bundle types including the fresh bundles. This PCT update will remain in effect only until the MAPLHGR limits for all bundles in future Dresden Unit 2 and Unit 3 cores are evaluated with the correct R-factors.
[
Reference:
Westinghouse letter LTR-LAM-1 1-63, Revision 0, "Dresden Units 2 & 3 and Quad Cities Units 1 & 2, 10 CFR 50.46 Notification and Report for R-Factor Error Evaluation," September 14, 2011.]
Page 4 of 4