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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:Miscellaneous
MONTHYEARML22047A1322022-02-15015 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 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 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 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 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 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 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 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 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 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 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 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 2022-02-15
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~-* Exelon Generation Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450 February 12, 2017 SVPLTR: #18-0006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Facility Operating License No. DPR-19 NRC Docket No. 50-237
Subject:
Owner's Activity Report Submittal; Fifth 10-Year Interval 2017 Refueling Outage Activities This letter submits the Owner's Activity Report (i.e., Form OAR-1) and In-vessel Visual Inspection (IVVI) Report for the Dresden Nuclear Power Station (DNPS) Unit 2 refueling outage (D2R25) which began on October 30, 2017, and was completed on November 18, 2017. This is the first refueling outage conducted in the second inspection period of the fifth 10-year inservice inspection interval for DNPS Unit 2. A copy of the Owner's Activity Report and IVVI Report are provided as attachments to this letter.
This Owner's Activity Report is submitted in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission," and USN RC Safety Evaluation In Support of Request for Relief Associated With the Fifth 10-Year lnservice Inspection Interval Program dated September 30, 2013. Code Case N-532-4 requires an Owner's Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. In accordance with the conditions of Code Case N-532-4, this OAR-1 form is being submitted within ninety days of the completion of the refueling outage.
The IVVI results are provided to report vessel internal inspections and to support B-N-1 and B-N-2 relief request exam completion.
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Peter J. Karaba Site Vice President Dresden Nuclear Power Station Enclosures
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Refueling* Outage D2R25 OAR-1 Plant Dresden Nuclear Power Station, 6500 N. Dresden Road, Morris, IL 60450 Unit No. 2 Commercial Service Date 6/9/70 Refueling Outage Number _ __cD;;._;2c;;.;R...;;2c;;.;5'-----
--(i-fa-p-pl-lc-ab-le_)__
Current Inspection Interval 5th Inspection Interval (1, 2nd, 3rd, 4t11, other)
Current Inspection Period 2nd Inspection Period (l't, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the Inspection Plans 2007 Edition with 2008 Addenda Date/ Revision of Inspection Plans _ _ _ _ _ _ _ _ _ _ _ _ _ _. .; 1. .; 0'-'/3:;.;1; .,/. ; ;1,; ,6/'-'R. ;.;e:;.;v. ;.;is; .; io:;.;n.;, .; ;.3_ _ _ _ _ _ _ _ _ _ _ _ __
Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans NA Code Cases used: N-649 N-653-1 N-586-1 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the Inspection Plan as required by the ASME Code, Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of D2R25 conform to the ef.re~rts of Secti°,_? ~I Signed / ;...JG_J\{. 1{~1 Coordinator (Owner or Owner's designee. Title)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois The Hartford Steam Boiler of Hartford , Connecticut and employed by Inspection and Insurance Company have inspected the items described in this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI By signing this certificate neither the Inspector nor his employer makes any warranty expressed or implied concerning the repair/
replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable, in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection Commissions IL 1546; NB10972 A, N, I (Inspector's Signature) National Board, State, Province, and Endorsements Date D2R25 OAR-1 Page 1 of 4
TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Unacceptable Flaw Indication Found in Upper Shell to Flange B-A/B1.30 Circumferential Weld /2/1/RPV Shell/2-SC4-FLG SIA File No. 1400733.301 D2R25 OAR-1 Page 2 of 4
TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/
Class Description Of Work Completed Replacement Plan Number 2/3 2A LPCI Heat Exchanger Support Repairs Removed Indications and Re-Welded Support 11/3/17 RRP 2-17-038 2/3 2B LPCI Heat Exchanqer Suooort Repairs Removed Indications and Re-Welded Suooort 11/8/17 RRP 2-17-039 1 Unit 2 Upper Reactor Head Flange Indications Removed Indications 11/6/17 RRP 2-17-074 1 Unit 2 LPCI Support M-1164D-296 Indications Removed Indications 11/6/17 RRP 2-17-075 2 Leak on Unit 3 SBLC Line Replaced Leakinq Fittinq 9/23/17 RRP 3-17-012 1 Indications on Unit 2 N20A-6 Weld Overlaid Weld 11/11/17 RRP 2-17-082 D2R25 OAR-1 Page 3 of 4
Dresden Unit 2 Reactor Internals Inspection Report Refueling Outage D2R25 The ASME Section XI inspections credited during D2R25 includes the once-per-period B-N-1 inspection of the reactor vessel interior and B-N-2 inspections of reactor vessel interior attachments. Credit is being taken for the Boiling Water Reactor Vessel and Internals Project (BWRVIP) examinations in place of the B-N-1 and B-N-2 examinations as allowed in Dresden Station Relief Request I5R-07, "Request for Relief for the Use of BWRVIP Guidelines in lieu of Specific ASME Code Requirements on Reactor Vessel Internals and Component Inspection In Accordance with 10CFR50.55a(a)(3)(i) Alternative Provides Acceptable Level of Quality and Safety".
To implement the requirements of the BWRVIP, General Electric - Hitachi (GEH) was contacted to perform the inspection activities. The following components and assemblies were examined as directed by BWRVIP documents:
- Fourteen shroud and shroud support vertical welds in accordance with BWRVIP-76 Revision 1-A, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines".
- One shroud support horizontal weld in accordance with BWRVIP-38, "BWR Shroud Support Inspection and Flaw Evaluation Guidelines".
- Attachment welds for two core spray piping brackets and all four steam dryer support lugs in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".
- Steam dryer previous indications and ten additional inspections in accordance with BWRVIP-139-A, "Steam Dryer Inspection and Flaw Evaluation Guidelines".
- Previous indications on the top guide rim weld and one aligner pin/block assembly in accordance with BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines".
The above BWRVIP examinations resulted in no indications identified in the reactor interior surface as defined by B-N-1 or the reactor interior attachments as defined by B-N-2.
D2R25 OAR-1 Page 4 of 4
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 1 Repair/ Work Request Code EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Class Reportable I Dbase Record 2-13-026 01623423-01 1 2-220-62A Replace feedwater check valve disc/seat No assembly with a refurbished spare as required based on inspection.
2-13-030 01623421-01 1 2-220-58A Contingency to replace existing disc/seat No assembly with refurbished spare modified to add groove for o-ring or new disc/seat assembly.
2-13-049 97032518-01 1 FD WTR CHK ASMB Refurb spare feedwater checkvalve No assembly SI 570A23/Catid 7860.
2-13-065 01624416-01 1 2-203-2C Replace/upgrade Unit 2 MSIV 2C internals. No 2-14-006 01606525-01 1 SPARE FDWTR CHK Refurbish spare feedwater checkvalve seat No assembly that was removed under WO 1509923-01 .
2-14-013 01608012-01 3 2-1501-2D Replace bonnet bolting on 2-1501-2D valve No if required.
2-15-029 01096660-01 2 2-1302 Contingency replacement bolting on the No West Channel Cover. Bolting may be replaced if lost, damaged during disassembly or to facilitate installation.
2-15-035 01096660-08 2 2-1302 Re-install diaphragm seal weld on Unit 2 No Isolation Condenser West End.
2-15-036 01096660-11 2 2-1302 Install welded tube plugs on west side of No Unit 2 Isolation Condenser based on results of Eddy-Current testing.
2-15-037 01096660-12 2 2-1302 Re-install heat shield stud welds to facilitate No Eddy-Current testing on Unit 2 Isolation Condenser west end tube bundle.
2-15-049 01786762-01 1 SPARE FDWTR CHK Refurbish spare feedwater check valve No assembly SI 570A23. Removed under WO 1510033.
2-15-053 01681225-01 1 2-3204-A-502&03 Install new test tap valves 2-3204-A-502 and No 503 downstream of feedwater check valve 58A.
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 2 Repair/ Work Request Code EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Class Reportable I Dbase Record 2-15-054 01681225-02 1 2-3204-A-504 Install new test tap valve 2-3204-A-504. No 2-16-012 01827586-01 1 SPARE FDWTR CHK Refurb spare feedwater 18 bolt to 20 bolt No check valve assembly. Includes basemetal repairs.
2-16-015 01917418-01 2 2-1105-A Rebuild the spare SBLC Relief Valve that No was removed from the Unit 2, 2A SBLC Train under WO 01553451-01.
2-16-017 01778031-01 3 2/3-9400-1 02 Replace CREVS heat exchanger flange No studs and nuts 2-16-023 PO 568405-01 1 TRG RCKMN 223 Per form repairs to Target Rock Main S/N No 223 inlet flange per NWS Traveler 16-32.
2-16-024 01960327-01 1 SPARE MSIV DISC Perform NDE on MSIV disc machined per No EC 399980.
2-16-025 01960327-02 1 SPARE MSIV DISC Perform NDE on MSIV disc machined per No EC 399980.
2-16-026 01828211-01 MC 2-1605-18"-LX Install new hardened vent piping per EC No 400930.
2-16-027 01817918-01 3 2-3930-501 Replace check valve and bolting if required. No Also includes task 2 where flange bolting of heat exchanger may be required. (2-6699A/B) 2-17-001 04590454-01 2/3 2-1503-B Replace 28 LPCI heat exchanger cover No bolting if lost or damaged during inspection or cleaning.
2-17-002 01706139-01 2 2-1105-B Replace Unit 2 SBLC relief valve. No 2-17-003 01506113-01 1 2-0203-4D Replace 4D SRV, perform flange repairs No and replace inlet bolting if required.
2-17-004 01516255-01 1 2-0203-4G Replace SRV 4G and replace inlet bolting No and repair inlet flange if required.
2-17-005 01704062-01 2 2-2301-53 Replace relief valve and bolting if required. No 2-17-006 01708617-01 2/3 2-1503-B Replace LPCI heat exchanger cover bolting No and tubing if required.
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 3 Repair/ Work Request Code EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Class Reportable I Dbase Record 2-17-007 01708617-03 2/3 2-1503-B Repair area's of upper and lower LPCI heat No exchanger head channel if required.
2-17-008 01710614-01 1 2-0203-3D Replace ERV 30. Replace inlet bolting and No repair inlet flange if required in task 7 and 9.
2-17-009 01711170-01 1 2-0203-3B Replace Unit 2 ERV 38. Replace inlet No bolting. Repair inlet flange if required.
2-17-010 01901895-01 1 2-0203-3A Replace Unit 2 Target Rock valve. Replace No bolting and repair inlet flange if required.
2-17-011 01309348-01 2 2-1402-28B Replace relief valve and bolting if required. No 2-17-012 04616404-03 2 2-2301-3 Replace valve disc. No 2-17-016 01692876-01 2 2-1105-B Rebuild spare SBLC relief valve No 2-17-017 01883544-01 2 2-1402-28A Rebuild Core Spray relief valve that was No removed under WO 1095133-01.
2-17-018 01126869-01 2 2-2301-71 Replace valve disc if required. No 2-17-019 01901902-01 2 2-2301-45 Replace Unit 2 HPCI 45 valve and bolting if No required.
2-17-020 01883829-01 2 2-1501-12 Replace snubber 2-1501-12. No 2-17-021 01883829-02 2 2-1501-10 Replace snubber 2-1501-10. No 2-17-022 01883829-05 2 2-1501-15 Replace snubber 2-1501-15. No 2-17-023 01883829-07 2 2-1501-19 Replace snubber 2-1501-19. No 2-17-024 01883829-09 1 2B-202-09 Replace snubber 2B-202-09. No 2-17-025 01883829-12 2 2-2305-01 Replace snubber 2-2305-01. No 2-17-026 01883829-24 3 2-3019C-55 Replace snubber 2-3019C-55. No
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 4 Repair/ Work Request Code EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Class Reportable I Dbase Record 2-17-027 01883829-26 1 2-1001A-38 Replace snubber 2-1001 A-38. No 2-17-028 01883829-06 2 2-1501-04 Replace snubber 2-1501-04. No 2-17-029 01490368-01 2 2-1599-130 Replace LPCI relief valve. No 2-17-030 01712778-01 MC 2-8526 Replace relief valve. No 2-17-031 01507055-01 2 2-1599-13C Replace relief valve. No 2-17-032 01848791-01 3 2-1512-24" Replace degraded Unit 2 CCSW pipe in No Cribhouse.
2-17-033 01848791-07 3 2-1512-24" Repair degraded inner wall of Unit 2 CCSW No piping found during non-ISi inspection.
2-17-034 01848791-23 3 2-1501-36C Replace bonnet bolting on valve if required. No 2-17-035 01903432-05 1 CRDM'S This is not a Section XI flaw.This is a routine No refuel outage replacement of existing control rod assemblies based on performance trending results. Existing capscrews are being replaced with each CRD assembly instead of cleaning and re-installing for ease of installation.
2-17-037 01848788-01 3 2-1514-16" Replace Unit 2 CCSW pipe 2-1514-16" in No Unit 2 Torus basement.
2-17-038 01882842-02 2 2-1503A Repair area's identified in NOE report Yes performed in Task 1. Also repair up to an additional 20" per side of existing weld based on NOE report results.
2-17-039 01882847-02 2 2-15036 Repair area's identified in NOE report Yes performed in Task 1. Also repair up to an additional 20" per side of existing weld based on NOE report results.
2-17-041 01440976-05 2 2-1402-86 Perform weld build-up on valve disc guides. No
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 5 Repair/ Work Request EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Code Class Reportable I Dbase Record 2-17-042 01883837-01 MC 2-2001-106 Perform PM's on valve. No 2-17-043 01901892-01 MC 2-2001-6 Replace diaphragm and perform PM's. No 2-17-044 01901899--1 MC 2-2001-5 Replace valve diaphragm and perform PM's. No 2-17-045 01901904-01 MC 2-2001-105 Replace valve diaphragm and perform PM's. No 2-17-048 01891399-04 1 U2 WST BNK HCUS Perform PM's on Unit 2 west bank HCU's. No Includes tasks 4, 28 and 29. Involves 138 valve work and accumulator replacement.
Done during D2R25.
2-17-049 01891399-05 1 EST BNK HCU'S Perform PM's on Unit 2 east bank HCU's No Includes tasks 5,6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21, 22, 23, 24, 25, 26, 27, 30 and 31. Involves 138 valve work and accumulator replacement. Perform during D2R25.
2-17-050 01828210-97 MC M-1158D-153 Remove MC support M-1158D-153 and add No shims to support M-1158D-161.
2-17-051 04608838-1 2 SPARE 2301-45 Rebuild spare 2301-45 check valve. No Removed from Unit 3 under WO 1838183-01.
2-17-052 PO 591089-L1 1 BK 7160 Perform repairs to Main Steam Safety Valve No BK 7160 per CEAR 17-215.
2-17-053 PO 591089-L1 1 BK6260 Perform repairs to Main Steam Safety Valve No BK 6260 per CEAR 17-217.
2-17-057 01942644-01 1 2-202-A Replace seal flange on 2A Re-Circ pump. No 2-17-058 04606234-01 2 2-1101-22 Perform overhaul on SBLC 2-1101-22 valve. No 2-17-060 1770616-01 1 2-203-1A Replace valve disc and bonnet bolting if No required.
2-17-061 01508125-01 2 2-1105-B Rebuild the spare SBLC Relief Valve. No
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 6 Repair/ Work Request Code EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Class Reportable I Dbase Record 2-17-062 568497-N/A 1 SPARE MSIV Replace main disc and machine the nozzle No seat step to re-establish design nozzle seat step.
2-17-065 04675213-04 1 2-0220-112D Cut out and remove valves 2-0220-112D & No 113D/2-0220-112C & 113C, then weld a pipe cap on the exposed sensing line.
2-17-066 01608012-04 3 2-1502-2D Repair disc guide rails if required. No 2-17-068 04668162-01 1 2-203-2D Overhaul Unit 2 2D MSIV as required. No 2-17-069 04668162-12 1 2-203-2D Perform in-body machining on MSIV valve to No install new liner assembly.
2-17-071 01883829-11 1 2-3001A-49 Replace Lisega Snubber with a new Lisega No snubber 2-17-072 01704664-01 1 2-0203-4E Install valve rotate out of stock No 2-17-073 01706140-01 1 2-0203-4F Change SRV No 2-17-074 01899866-17 1 2-0201 Repair indications in vessel head to flange Yes weld 2-17-075 0189987 4-20 1 M-1164D-296 Remove indications on attachment welds on Yes support M-1164D-296 (IWA).
2-17-076 04708193-01 3 M-564E-7 Perform repairs to support as identified in IR No 4071021.
2-17-077 04708202-01 3 M-564E--15 Perform repairs to support as identified in IR No 4071014.
2-17-078 01901291-01 1 2-0304-2-1/2" Replace flange bolting No 2-17-079 04709815-01 1 HCU 38-35 Replace stem/plug on 126 valve.HCU 38-35 No 2-17-080 04709814-01 1 HCU 46-47 Replace stem/plug on HCU 46-47 126 valve. No 2-17-081 04709813-01 1 HCU 14-27 Replace HCU 126 valve stem/plug. No
OAR-1 Summary Date Submitted: I 2/16/2018 Page: 7 Repair/ Work Request Code EPN Number Description of Repair/Replacement OAR-1 Replacement Plan No.
Number Class Reportable I Dbase Record 2-17-082 04709411-01 1 JP N20A-6 Perform weld overlay on jet pump nozzle No weld N20A-6. VT-2 not required per company position paper. Revision 1 added for Discontinuity Removal Method.
2-17-083 04710868-01 1 2-305-54-39-127 Replace stem\disc if required No 2-17-085 1883829-28 2 2-1522-24 Replace snubber 2-1522-24. No 3-14-028 01674590-01 3 3-5700-300 Replace standpipes on CCSW Room Cooler No 3-5700-30D. Replace flange bolting if required.
3-15-014 01674590-19 3 3C CCSW PM CLR Install TMOD per EC 398257 on 3C CCSW No pump vault cooler.
3-16-025 95046273-24 1 SPARE MSIV DISC Perform NOE on MSIV disc modified per EC No 399980.
3-16-063 00690402-02 3 3-3903 Replace Unit 3 DGCW pump and motor if No required.
3-17-002 01828114-01 3 2/3-3930-501 Replace check valve and bolting if required. No 3-17-003 01828114-09 3 2/3-6669A/B. Replace or repair diesel generator cooling No water piping as required.
3-17-011 04657318-01 3 3-1503B Replace LPCI heat exchanger cover bolting No if lost or damaged during inspection and cleaning.
3-17-012 04683812-01 2 Replace 1 1/2" pipe tee on SBLC line 3- No 1102A-1 1/2"-A. Pipe tee between squib valve and 3-1101-2A.