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Category:Letter
MONTHYEARIR 05000237/20230042024-02-0202 February 2024 Integrated Inspection Report 05000237/2023004 and 05000249/2023004 IR 05000010/20230012024-01-17017 January 2024 NRC Inspection Report 05000010/2023001 (Drss) ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program SVPLTR 23-0037, Core Operating Limits Report for Cycle 292023-11-29029 November 2023 Core Operating Limits Report for Cycle 29 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 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums 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 ML23285A2342023-10-13013 October 2023 Confirmation of Initial License Examination 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 ML23279A0712023-10-0606 October 2023 Response to NRC Dresden Nuclear Power Station, Units 2 and 3 - Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 ML23269A0662023-09-28028 September 2023 Proposed Alternative Request RV-23H Associated with the Sixth 10-Year Inservice Testing Interval ML23265A1322023-09-27027 September 2023 Proposed Alternative Request RV-03 Associated with the Sixth 10-Year Inservice Testing Interval ML23205A1362023-09-20020 September 2023 Proposed Alternative Request RV-02D Associated with the Sixth IST Interval IR 05000237/20230112023-09-0606 September 2023 Comprehensive Engineering Team Inspection Report 05000237/2023011 and 05000249/2023011 RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-080, 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 IR 05000237/20234022023-08-29029 August 2023 Security Baseline Inspection Report 05000237/2023402 and 05000249/2023402 IR 05000237/20230022023-08-0808 August 2023 Integrated Inspection Report 05000237/2023002 and 05000249/2023002 ML23212A9892023-08-0303 August 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23174A1502023-08-0303 August 2023 Issuance of Amendment Nos. 282 and 275 Control Rod Scram Times ML23193A0052023-07-28028 July 2023 Subsequent License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23192A6292023-07-11011 July 2023 Correction Letter - Issuance of Amendment Nos. 281 and 274 Regarding Transition to GNF3 Fuel (EPID L-2022-LLA-0121) (Non-Proprietary) ML23144A3142023-07-0606 July 2023 Issuance of Amendment Nos. 281 and 274 Transition to GNF3 Fuel (EPID L-2022-LLA-0121) - Nonproprietary ML23187A0462023-07-0606 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000237/2023004 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 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 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 IR 05000237/20233012023-05-30030 May 2023 NRC Initial License Examination Report 05000237/2023301; 05000249/2023301 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 ML23132A0932023-05-17017 May 2023 Information Meeting (Public Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Dresden Power Station, Units 2 and 3 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 SVPLTR 23-0018, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report IR 05000237/20230012023-05-0404 May 2023 Integrated Inspection Report 05000237/2023001 and 05000249/2023001 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) ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI IR 05000237/20234012023-04-26026 April 2023 Cyber Security Inspection Report 05000237/2023401 and 05000249/2023401 ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration IR 05000237/20235012023-04-21021 April 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000237/2023501 and 05000249/2023501 ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 SVPLTR 23-0014, Annual Dose Report for 20222023-04-15015 April 2023 Annual Dose Report for 2022 ML23088A2242023-04-0505 April 2023 Regulatory Audit Report Regarding License Amendment Request to Transition to GNF3 Fuel ML23087A0482023-03-28028 March 2023 Operator Licensing Examination Approval - Dresden Nuclear Power Station, April 2023 2024-02-02
[Table view] Category:Report
MONTHYEARNMP1L3469, 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 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 ML13126A1902013-03-28028 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 10 of 13 2022-06-30
[Table view] Category:Technical
MONTHYEARNMP1L3469, 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 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 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 RS-18-077, Defueled Safety Analysis Report Update, Revision 92018-06-20020 June 2018 Defueled Safety Analysis Report Update, Revision 9 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 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 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 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-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 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 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 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 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 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 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 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 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 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 ML13126A1902013-03-28028 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 10 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 ML12306A3932012-11-0101 November 2012 Request for a Written Response to NRC Observations and Concerns Regarding Dresden Station Response Plan for External Flooding Events RS-09-165, Request for Approval of Updated Pipe Flaw Evaluation Report2009-12-0707 December 2009 Request for Approval of Updated Pipe Flaw Evaluation Report ML0908404302009-03-0505 March 2009 Medical Services (MS-1) Drill Report ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 RS-07-097, Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit2007-07-10010 July 2007 Request for Technical Specifications Change for Minimum Critical Power Ratio Safety Limit ML0715705102007-04-0505 April 2007 CC-AA-309-1001, Rev 3, Attachment 1, Design Analysis Major Revision Cover Sheet, 9389-46-19-3, Rev 004, Diesel Generator 2/3 Loading Under Design Bases Accident Condition. ML0715705012007-04-0505 April 2007 CC-AA-309-1001, Rev 3, Attachment 1, Design Analysis Major Revision Cover Sheet, 9389-46-19-1, Rev 003 Diesel Generator 3 Loading Under Design Bases Accident Condition ML0715705052007-04-0404 April 2007 CC-AA-309-1001, Rev 1, Attachment 1, Design Analysis Major Revision Cover Sheet, 989-46-19-2, Rev 003, Calculation for Diesel Generator 2 Loading Under Design Bases Accident Condition ML0634601312006-12-0707 December 2006 Attachment 11, Exelon/Amergen Response to the Request for Additional Information, EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative Loss of the RCS Barrier ML0621300322006-05-31031 May 2006 GE-NE-0000-0053-8435-R1-NP, Rev 1, Dresden 2 & 3 and Quad Cities 1 & 2, Safety Valve Setpoint Tolerance Relaxation, May 2006 ML0606203682006-01-26026 January 2006 Attachment 3 (Technical Specifications) and 4 (Affidavit and Non-Proprietary Version of Attachment 2 to Exelon Letter Dated January 26, 2006) ML1024201462005-12-0707 December 2005 Groundwater Tritium Investigation Report, Dresden Generating Station, Project Number EXENW-18513-400 RS-05-064, Commitments and Plans Related to Extended Power Uprate Operation2005-05-13013 May 2005 Commitments and Plans Related to Extended Power Uprate Operation ML0514400842005-05-0505 May 2005 Enclosure 1, Attachment 2, 26A6266AB, Revision 4, Steam Dryer, GE Nuclear Energy, Design Specification Data Sheet, Dated May 5, 2005 ML0513601002005-04-30030 April 2005 Enclosure 2, Attachment 2, Replacement Steam Dryer Reactor Vessel Bracket Stress Report for Quad Cities 1, 2, and Dresden 2,3, GE-NE-0000-0034-4803-02, Non-Proprietary, Dated April 2005 ML0513300532005-04-25025 April 2005 Enclosure 3, Dresden Strain Gage Uncertainty Evaluation, SIA File No.: EXLN-17Q-301, Revision 0, Dated April 25,2005 ML0514400812005-04-24024 April 2005 Enclosure 1, Attachment 1, 26A6266, Rev 3, Steam Dryer, GE Nuclear Energy, Design Specification, April 24, 2005 RS-05-042, Additional Information Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations2005-04-0606 April 2005 Additional Information Related to Analysis and Design of New Quad Cities Steam Dryers, and Responses to Requests for Additional Information Related to EPU Operation at Dresden and Quad Cities Nuclear Power Stations ML0507303262005-03-31031 March 2005 Non-Proprietary Dresden and Quad Cities Neutron Flux Evaluation ML0510902702005-01-31031 January 2005 Attachment 2, CDI Report No. 05-01, Rev 0, Revised Hydrodynamic Loads on Quad Cities Unit 2 Steam Dryer to 200 Hz, with Comparison to Dresden Units 2 & 3 Loads. RS-05-005, Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews2005-01-0505 January 2005 Letter RS-05-005, Dated 1/05/05, Submittal of Information Regarding Extended Power Uprate Vulnerability Reviews 2022-06-30
[Table view] |
Text
Common*lth Edison
- One First Na~I Plaza, Chicago, Illinois Address Reply to: Post Office Box 767 Chicago, Illinois 60690
ill *-
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BBS Ltr. #"?f3"j-75 Dresden Nuclear Power Station-~-
- Mr. James G. Keppler, Regional Director fi:egulatory Docket flle
~ . -------*----:~~~~
Directorat~ of Regulatory Operations-Region III
- u. s. Nuclear Regulatory Comnission 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
roLLOW-UP REPORT TO ABNORMAL OCCURRENCE ENTITLED "CORRELATION OF FUEL FAILURES AT DRESDEN-3 IDENTIFIED BY WEI' SIPPlNG TESTS TO CALCULATED VIOLATIONS OF GE FCIOMRll .
Reference:
- NRC Exit Interview of May 20,.. 1975
.. *~
Please find attached the iaoove-mentioned report, provided per NRC request of May 20, 1975. .
.~ . '
L B.. B. Stephen
.'\~ Super;Lntendent BBS:smp . - ~ *-
File/NRC JUN
" T*frr-_: James G. Keppler TITLE 9
- June 20, 1975 Fuel Failures Identified at D3-EOC3 by Wet Sipping Tests and Com!n~Regarding the PCIOMR.
SUI'<WARY 724 assemblies were wet sipped out of core and total of 113 defective assemblies were identified. General Elec-tric a{:.rreed they were defective as indicated by the fuel contract and were d.ischarged. Twenty-seven high exposure assemblies were also discharged and a total of 140 new assemblies were inserted in the core for cycle 4. All the defective assemblies were 7X7 fuel enriched to 2.13 w/o U-235. The average fuel failure rate was 15.6%. The core was sipped at an average rate of 40 assemblies per day. Table 1 is a listing of the identified failures, their core locations and exposures.
DISCUSSION Figure 1 is a core map indicating the location of the leakers. Pigures 2 to 4 graph three power distributions (equilibrium xenon) typical of the preconditioned shape (2227-Figure 4 (a)) and the spape at 6:57 a.m. on 10-31-74 (1432-Figure 4 (b)). Xenon transients, depending on core location, will increase the bottom peaks by O to 25%.
Failures that don't appear to be related to 10-31-74 are reviewed as follows:
(a) None of the Cycle 2 edge assemblies, includi.~g those n10ved to the center for Cycl~ 3, failed - Figure 6. -
(b) There were three assemblies from cells that had 3 out of 4 failures at EOC-1 that were moved to uncontrolled locations on the edge for Cycles 2 and 3.
None of these three has failed yet.
(c) Four edge assemblies failed during Cycle 3. One,DD0209, was classified as a suspect leaker at EOC-2.
(d) Of 50 Oycle 3 assemblies that were reconstituted at EOC-1, six failed.
All but one may be attributed to 10-31-74.
No GEB (7X7) or DDB (8X8)assemblies were classified as leak.era. The average
- exposure of the GEB's was about 4000 MWD/T, and of the DDB's about 2000 MWD/T.
Initially, one GEB (058) and two DDB's (008 and 011) sipped as leakers. The three were resipped twice and found to be sound. To resolve any questions concerning these assemblies, five other assemblies, initially sipped at approx-imately the same time and classified as leakers, were resipped. Again all five
Mr. James G. Keppler June 20, 1975 e
were found to be defe,ctive. Of the 52 GEB' s in the core, 29 exceeded the PCIOMR. Seven .of these dfd so by more than 2 KW/ft, and were among the most severe variations. The differences from the original core 7X7's introduced in the GEB' s include: different fill gas, lower exposure, *tru:-cker cladding, smaller pellet diameter, and shorter pellets with chamfered edges.
Figure 1 indicates that about 80% of the assemblies on the periphery (one assembly removed) of cells that eA"}Jerienced major rod movements (D7, C6, CB and symmetric locations) failed. Figure 7 shows the local power distribution at about 15,000 MWD/T ,for a controlled and an uncontrolled D3 2.13 w/o assembly.
A 2.13 w/o Gd assembly is included to compare the local factors of pins A7 and Gl, which are about 25% higher £or the D3 assemblies.
An analysis was done with a FLARE-type code to determine the kW/ft of nodes that exceeded 8 kW/ft on a pin. The study was done at equilibrium xenon for 12-inch nodes (a correction factor was applied to account for transient xenon). The results are summarized in Figure 8. Only original core fuel is included, and power changes were assumed to be instantaneous. Some comments on the results follow:
(a) The failures do not appear to be related to previous cycle operation.
(b) 22 Failures of 433 assemblies (5%) were at less than 8 kW/ft on 10/31/74.
Thus, none of these was assumed to be related to the October 31, rod movements.
(c) 5 of 74 assemblies (-7%) failed when the envelope (or 8 kW/ft, which ever was greater) was violated by 1 kW/ft or less. The failure rate increased rapidly as the step change above the envelope increased.
(d) The effect on fuel failures of more gradual increases in power, soak periods, exposure, and length of time fuel remains "preconditioned" requires more data than is currently available.
CONCLUSIONS
- 1. The fuel rod failures related to rod movements on 10/31/74 were probably caused by a pellet-clad interaction mechanism involving highly localized strain leading to cracking of cladding having a low strain-to-fracture capability. Some cracking could also have been promoted by a stress corrosion phenomenon.
- 2. GE's PCIOMR, based on the assumption that a minimum tensile stress is required to cause such cracking, were in part substantiated: the evidence appears to support the 8 KW/ft threshold and allows some margin above a "preconditioned" shape.
- 3. Based on past sipping experience and en the observed care with which sipping operations were conducted, the sipping program for D-3 EOC-3 was judged to be very successful, with an estimated effectiveness of at least 90%.
--fAE::>LE I Defective Fuel Assemblies Identified at Dresden-3, End-of-Cycle 3
-~-
P.ssemb ly Core Exoosure Number location (M\IDL'.t)
DD 001 09-30 12,686 021 13-28 13,.018 025 13-38 13,420 036 13-34 13,008 037 31-48 13,576 053 47-34 12,990 064 51-30 12,814 073 09-34 12,891 079 . 45-32 13,015 081 53-20 12,88~
089 11-30 12,805 090 13-32 13,027 093 47-24 13,439 102 13-30 13,030 107 47-32 13, 01~4 111 09-38 12,580 120 39-20 13,321 121 49-26 13,100 127 09-28 12,906
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128 51-34 12,928 129 43-38 . . 13, 368
.132 09-32 12,, 790 134 47-20 13,298
Assembly Nur.1ber e
Core Location Exposure
( MWD /t) 331 51-38 12,536 332 25-38 12,287 343 31-20 12,978 350 43-30 12,317 351 43-26 9,465 364 09-42 12,385 378 11-40 12,741 401' 51-42 11,244 406 07-26 . 12, 958 424 27-32 11,941 425 19-06 11,774
. 431 51-36 10,501 433 09-44 .11,332 436 45-36 12,788 440 53-26 12,619 450 07-32 12,678 455 51-26 10,568 457 35-24 ;, 12, 303 460 43-34 12;679 465 11-1'6 " 12, 858 474 475 17-26 39-28 9,442
. *12, 550 480 15-50 . 12, 904 483 .13-44 10,353 487 . 35-32 12, l l~9
Core I..ocation 5 -
Exposure
( MHD /t)
~~
142 47-42 13,292 151 01-30 . 11,531 161 31-12 13,731 162 45-06 11,671 163 11-36 13,061 173 49-32 12,966 175 13-20 13,327 181 49-36 13,101 188 13-42 13,294 191 13-24 13,569 196 47-30 13,044 200 49-30 12,923 204 51-28 12,925 209 47-06 11,342 214 *21-20 13,327 229 29-42 *12, 822 233 47-38 13,437 270 47-28 ..13,114 286 09-36 l0,563 287 . 09-22 10,622 295 07-24 12,653 296 23-30 . 12, 633 300 17-56 11,936 301 '53-36 12,966 319 05-26 11,945
/
Core Loe at ion Exposure (MWDLt) 488 07-36 12,530 --~-
491 17-28 12,671 493 53-24 12,678 499 51-22 10,652 511 07~40 12,594 518 53-22 12,663 529 11-18 12,939*
531* 07-44 11,798 537 27-30 ll,944 542 lL-22 12,820 544 07-22 12,636 566 47-26 10,088 573 07-38 12,022 587 25-24. 12,309 613 07-30 12,863 617 11-44 12, 897 . "
618 09-40 10,593 623 53-38 i; 12,"667 624 45-26 12,789 633 49-44 ' 12, 949 .
639 13-26 .. 10, 075 646 13-36 10,060 652 13-40 . 10, 467 663 49-16 12,865 669. 33-30 11,945.
688 49-22 12,802
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P.ssembly Nuraber
Expos'.lre (MWD/t)
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693 13-22 10,502
. 698 47-22 10,503 699 49-40 12,791 700 15-36 12,764 705 05-34 12,099 706 09-26 l0,585 710 09-24 12, 519 .
714' 51-40 10,627 7i6 15-26 *12,778 721 17-14 10,356 730 51-20 10,653 745 47-40 10,492 750 53-40 12,648 752 51-24 12', 542 Average exposure of 113 defect:tve a3semblies - 12,29*4 M':tm/t.
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