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Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] Category:Report
MONTHYEARML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards ML22269A3882022-09-0707 September 2022 02-Gamma Spectroscopy of Concrete Pucks RA-20-0280, Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw2020-09-14014 September 2020 Submittal of IWB-3640 Analytical Evaluation Performed to Accept an ASME Section XI Code Rejected Sub-Surface Flaw ML19242C7282019-08-28028 August 2019 Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML17031A4312017-01-26026 January 2017 Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan ML16230A2822016-08-17017 August 2016 Duke Power Company Oconee Nuclear Station Unit 2 Integrated Leak Rate Test of the Reactor Containment Building ML16152A0522016-05-31031 May 2016 ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)2016-02-15015 February 2016 Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) ML16034A3252015-12-31031 December 2015 Revision 0 to Summary of Methodology Used for Seismic Capacity Evaluation of GMRS Mitigation Components ML15218A2972015-08-0606 August 2015 Historic Temperature Data Including Record Highs for the Seneca ML15201A0082015-07-22022 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15161A4202015-06-15015 June 2015 Review of the Spring 2014 Steam Generator Tube Inservice Inspection Report During Refueling Outage 27 ONS-2015-065, TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay2015-05-22022 May 2015 TIA 2014-04, Request for Technical Assistance Regarding the Adequacy of the Station Design and Licensing Bases for the Degraded Voltage Relay ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.2015-03-27027 March 2015 Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc. ML16272A2172015-03-0606 March 2015 Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Pp. 1-70, Dated March 6, 2015 (Redacted) ML16272A2182015-03-0606 March 2015 Revision 1 to Flood Hazard Reevaluation Report on Oconee Nuclear Station, Appendices, Dated March 6, 2015 (Redacted) ML15072A2172015-02-25025 February 2015 Form OAR-1 Owners Activity Report (CC N-532-4) for Oconee Unit 1, Refueling Outage EOC 28 ONS-2014-161, Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)2014-12-19019 December 2014 Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites) ML14218A8072014-08-27027 August 2014 NRC Staff Review of the Documentation Provided by Duke Energy for the Oconee Nuclear Station Concerning Resolution of GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat ONS-2014-074, Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System2014-08-15015 August 2014 Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System ML16272A2162014-04-30030 April 2014 Validation of Hrr Breach Hydrograph for Jocassee Dam, Dated April 30, 2014 (Redacted) ML15065A3372014-04-23023 April 2014 Response to NRC Request for Additional Information (RAI) Related to the MRP-227-A Applicant/Licensee Action Item #7 Analysis Supporting the Reactor Vessel Internals Inspection Plan Amendment Request (ANP-3267Q1NP (R1)) ML14076A0002014-04-0202 April 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 ONS-2014-040, 2013 Annual Commitment Change Report2014-03-31031 March 2014 2013 Annual Commitment Change Report ONS-2014-046, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3..2014-03-31031 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3.. ML14087A1752014-03-20020 March 2014 ANP-3267Q1NP, Rev. 0, Response to NRC Request for Additional Information (RAI) Related to the MRP-227-A Applicant/Licensee Action Item #7 Analysis Supporting the Reactor Vessel Internals Inspection Plan Amendment Request for Oconee, Units 1 ML13365A2582014-02-10010 February 2014 Interim Staff Evaluation Regarding Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14028A5122014-02-0404 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Oconee Nuclear Station, Units 1, 2, and 3, TAC Nos.: MF0782, MF0783, and MF0784 ONS-2014-002, Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-144472014-01-16016 January 2014 Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-14447 ML13339A3482013-11-30030 November 2013 ANP-3267NP, Revision 0,MRP-227-A Applicant/Licensee Action Item #7 Analysis for the Oconee Nuclear Station Units, Licensing Report ML13275A3002013-08-31031 August 2013 ANP-3208NP, Rev 1, Confirmation of Stress Relief for ONS-1, ONS-2, ONS-3, and CR-3 Core Support Shield Upper Flange Welds ML13275A2992013-08-31031 August 2013 ANP-3186NP, Rev 2, ONS License Renewal Scope and MRP-189, Rev. 1 Comparison ML13196A2482013-07-11011 July 2013 Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model ML13190A0152013-07-0101 July 2013 Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012 ML13192A1572013-05-15015 May 2013 Stone & Webster, Inc., Technical Report 1457690202-R-M-00005-0, NTTF 2.3 Seismic Peer Review Supplementary Report, Oconee Nuclear Station Unit 1. ML13119A0412013-03-31031 March 2013 Attachment 1, ANP-3186NP, Rev. 1, ONS License Renewal Scope and MRP-189, Rev. 1 Comparison. ML13119A0422013-03-31031 March 2013 Attachment 2, ANP-3208NP, Rev. 0, Confirmation and Stress Relief for ONS-1, ONS-2, ONS-3, and CR-3 Core Support Shield Upper Flange Welds. ML12347A2522012-11-27027 November 2012 Seismic Walkdown Information Request for Information Pursuant to Title 10 of Code of Federal Regulations Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident 3/12/12 ML16272A2202012-11-27027 November 2012 Enclosure 1: Flood Walkdown Report (NRC 50.54(f) NTTF Recommendation 2.3), Dated November 27, 2012 (Redacted) ML12347A2532012-11-16016 November 2012 Attachment 6: Nttp 2.3 Seismic Peer Review Report Oconee Nuclear Station Units 1,2 and 3 ML14058A0452012-09-20020 September 2012 History of Oconee Flood Concerns ML12251A0312012-09-10010 September 2012 Review of the Spring 2011 Steam Generator Tube Inservice Inspections During End of Cycle 26 Refueling Outage ML12251A0042012-09-0505 September 2012 Unit 3 Cycle 27 Startup Testing Report ML12187A2152012-03-31031 March 2012 Attachment 1, ANP-2951, Rev. 002, Inspection Plan for the Oconee Nuclear Station, Units 1, 2, and 3, Reactor Vessel Internals, Amp/Application to Implementation MRP-227-A ML11180A0112011-06-23023 June 2011 Closure of 60-Day Interim Report Notification: Dubose National Energy Services, Inc ML1108208652011-03-31031 March 2011 Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections ML1100404092010-12-23023 December 2010 Draft, Regarding Review of Root Cause Analysis and Actions Addressing the Underground Pipe Damage to the Condensate Storage Tank Return Line ML12053A3332010-10-27027 October 2010 Areva Document No. 47-9048125-002, Update of Irradiation Embrittlement in BAW-10008 Part 1 Rev 1, Non-Proprietary ML1029900642010-10-26026 October 2010 NRC Staff Assessment of Duke Energy Carolinas, Llc. Oconee External Flooding Issue 2023-09-26
[Table view] Category:Miscellaneous
MONTHYEARML23270B8362023-09-26026 September 2023 Code Case N-752 Audit September 26, 2023, E-mail Providing Additional Information Regarding the Use of Owner'S Requirements and Engineering Judgment in Lieu of Code and Standards ML19242C7282019-08-28028 August 2019 Attachments 5 - 12: Thermal-Hydraulic Models for High Energy Line Break Transient Analysis, Duke Energy/Framatome Affidavits, Regulatory Requirements, Definitions, Time Critical Operator Actions and Feasibility Assessment for New Proposed T RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML17031A4312017-01-26026 January 2017 Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and FLEX Final Integrated Plan ML16152A0522016-05-31031 May 2016 ANP-3477NP, Rev. O, MRP-227-A Applicant/Licensee Action Item 6 Analysis ONS-2016-017, Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2)2016-02-15015 February 2016 Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) ML15218A2972015-08-0606 August 2015 Historic Temperature Data Including Record Highs for the Seneca ML15201A0082015-07-22022 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML15161A4202015-06-15015 June 2015 Review of the Spring 2014 Steam Generator Tube Inservice Inspection Report During Refueling Outage 27 ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc.2015-03-27027 March 2015 Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc. ML15072A2172015-02-25025 February 2015 Form OAR-1 Owners Activity Report (CC N-532-4) for Oconee Unit 1, Refueling Outage EOC 28 ONS-2014-161, Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites)2014-12-19019 December 2014 Submittal of the Expedited Seismic Evaluation Process Report (CEUS Sites) ML14218A8072014-08-27027 August 2014 NRC Staff Review of the Documentation Provided by Duke Energy for the Oconee Nuclear Station Concerning Resolution of GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat ONS-2014-074, Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System2014-08-15015 August 2014 Special Report Per Selected Licensee Commitment 16.9.9 Auxiliary Service Water (Asw) System and Main Steam Atmospheric Dump Valves and Oconee Transition from the Station Asw System to the Protected Service Water System ML14076A0002014-04-0202 April 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 ONS-2014-040, 2013 Annual Commitment Change Report2014-03-31031 March 2014 2013 Annual Commitment Change Report ONS-2014-002, Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-144472014-01-16016 January 2014 Special Report Per Technical Specification 5.6.6, Problem Investigation Process No. O-13-14447 ML13196A2482013-07-11011 July 2013 Duke Energy Carolinas, LLC (Duke Energy): Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model ML13190A0152013-07-0101 July 2013 Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012 ML14058A0452012-09-20020 September 2012 History of Oconee Flood Concerns ML12251A0312012-09-10010 September 2012 Review of the Spring 2011 Steam Generator Tube Inservice Inspections During End of Cycle 26 Refueling Outage ML12187A2152012-03-31031 March 2012 Attachment 1, ANP-2951, Rev. 002, Inspection Plan for the Oconee Nuclear Station, Units 1, 2, and 3, Reactor Vessel Internals, Amp/Application to Implementation MRP-227-A ML11180A0112011-06-23023 June 2011 Closure of 60-Day Interim Report Notification: Dubose National Energy Services, Inc ML1108208652011-03-31031 March 2011 Evaluation of 2010 (Cycle 24) Steam Generator (SG) Tube Inspections ML1100404092010-12-23023 December 2010 Draft, Regarding Review of Root Cause Analysis and Actions Addressing the Underground Pipe Damage to the Condensate Storage Tank Return Line ML1029104802010-10-20020 October 2010 NRC Assessment of Oconee External Flooding Issue (October 18, 2010) ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1018201842010-07-0707 July 2010 Evaluation of 2009 (Cycle 24) Steam Generator Tube Inspections ML1013406842010-05-18018 May 2010 Audit Plan - Technical Adequacy of the Oconee Nuclear Plant'S License Amendment Request for the Transition to 10 CFR 50.48 (C) ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1019305452010-02-0808 February 2010 Preliminary Report Oconee Nuclear Station ML1020105402009-04-20020 April 2009 Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Appendix D Through Appendix E ML1020105382009-04-20020 April 2009 Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Cover Letter Through Appendix C ML1020105422009-04-20020 April 2009 Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Appendix E - Continued Through End ML1020105412009-04-20020 April 2009 Letter to Duke Energy from Cline, Site Characterization Report,Groundwater Protection Initiative, Oconee, Appendix E - Continued ML0834702462008-12-0909 December 2008 Submittal of Auxiliary Service Water System Outage Report ML0813502322008-05-12012 May 2008 Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Request 07-ON-004 ML0807101592008-02-29029 February 2008 GL-04-002 Supplemental Response on Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors ML0735322262007-12-13013 December 2007 Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004 ML0706504222007-02-27027 February 2007 Fitness-For-Duty Program Performance Data Reports for Period July 1, 2006 Through December 31, 2006 ML0705300702007-02-21021 February 2007 Emcb Review of the High Energy Line Break Mitigation Strategies for the Oconee Units as Proposed by Duke in a Letter Dated November 30, 2006 ML0702903282006-11-30030 November 2006 Tornado/Helb Mitigation Strategies and Regulatory Commitments ML0712902832006-11-13013 November 2006 DPO Panel Report-Memo to J. Dyer, NRR, from J. Grobe, Ades/Nrr, Subject: DPO Panel Response to DPO-2006-002 ML0712902512006-10-26026 October 2006 DPO Panel Report-Memo to J. Dyer, NRR, from J. Grobe, Ades/Nrr, Subject: DPO Panel Response to DPO-2006-003 ML0624904272006-08-28028 August 2006 Fitness-For Duty Program Performance Data Reports for Period Covering January 1, 2006 Through June 30, 2006 ML0711501942006-06-0202 June 2006 June 2006 Monthly Report for DPO-2006-002,-003 ML0612404452006-04-12012 April 2006 Future Oconee Tornado Mitigation Strategy ML0612404672006-03-0909 March 2006 Tornado and High Energy Line Break Events Outside Containment - Supplemental Information ML0606004492006-02-23023 February 2006 EOC22 Refueling Outage, October-November 2005 Steam Generator Inservice Inspection 3 Month Report 2023-09-26
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DUKE Scoff L.Batson ENERGY, Oconee NuclearStation Duke Energy ONO1VP I 7800 Rochester Hwy Seneca, SC 29672 10 CFR 54.37(b) o: 864.873.3274
- f. 864.873. 4208 Scoft.Batson@duke-energy.com July 1, 2013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, 50-270, 50-287 Aging Management Reviews for Newly Identified Systems, Structures and Components as of December 31, 2012 Pursuant to 10 CFR 54.37(b), attached are aging management reviews (AMR) for those Oconee Nuclear Station systems, structures and components (SSC) that have been newly identified as of December 31, 2012. These AMRs support changes to the aging management program summaries provided in the 2012 revision of the Updated Final Safety Analysis Report (UFSAR) for Oconee Nuclear Station that will be submitted under separate cover on or before July 1, 2013.
The following are the SSCs that have AMRs attached to this letter:
- 1) Standby Shutdown Facility - Auxiliary Service Water
- 2) Fan and Damper Housings
- 3) Keowee Turbine Guide Bearing Oil Coolers This submittal document contains no regulatory commitments.
If there are any questions, please contact Susan Perry at (864) 873-4370.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1st day of July, 2013.
Sincerely, Scott L. Batson Attachment www.duke-energy.com
U. S. Nuclear Regulatory Commission July 1, 2013 Page 2 xc:
Mr. Victor McCree Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John Boska Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852-2746 Mr. Ed Crowe Senior Resident Inspector Oconee Nuclear Station
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 1 Aging Management Reviews For Newly Identified Oconee Nuclear Station Systems, Structures and Components as of December 31, 2012
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 2 Introduction This summary report is in lieu of adding a level of detail to the Oconee Nuclear Station (ONS)
Updated Final Safety Analysis Report (UFSAR) that is greater than the remainder of the UFSAR, including the License Renewal Supplement. An entry on the NRC website, "Frequently Asked Questions (FAQs) About License Renewal Inspection Procedure (IP) 71003, 'Post-Approval Site Inspection for License Renewal,"' relates to the amount of detail required per 10CFR 54.37(b). It states, "The NRC staff will consider it acceptable if the summary information included in the FSAR update is consistent with the requirements of 10 CFR 54.21(d), and the guidance provided by Revision 1 of NUREG-1 800, 'Standard Review Plan for License Renewal Applications for Nuclear Power Plants' (SRP-LR), provided that the licensee has supplied the technical details (as described in RIS 2007-16) in another documented submittal to the NRC." The information in this report is consistent with the technical information previously submitted to the NRC with the License Renewal Application (LRA) and subsequent requests for additional information (RAIs).
In July 1998, ONS submitted a LRA to the NRC to renew the operating licenses for ONS Units 1, 2, and 3 for an additional 20 years beyond the original license expiration dates of February 6, 2013, October 6, 2013, and July 19, 2014, respectively. Within the LRA, system descriptions were provided to define the component types, intended functions, and the Aging Management Programs (AMPs) that applied. Lists of individual components within the scope of license renewal were not required to be provided. The renewed operating licenses were issued in May 2000 to extend the operating licenses for ONS Units 1, 2, and 3 for an additional 20 years.
For holders of a renewed operating license, 10 CFR 54.37(b) requires that newly-identified systems, structures, or components (SSCs) be included in the UFSAR update required by 10 CFR 50.71(e) describing how the effects of aging will be managed. Newly-identified SSCs are those SSCs that were installed in the plant at the time of the LRA submittal but were not evaluated as part of the LRA.
A review of engineering changes, newly generated License Renewal Boundary Drawings, and items identified using the Problem Investigation Program (PIP) were reviewed from January 1, 2012 through December 31, 2012. From this review, three Aging Management Reviews (AMRs) were performed for "newly identified" items. All newly identified components have been assigned to existing AMPs and appropriate actions to detect and manage aging effects throughout the period of extended operation (PEO) have been taken.
The components for which AMR results are already addressed within the LRA or are addressed by responses to NRC RAIs are not discussed here, since the results of the AMR have been previously submitted and found acceptable.
Summaries of the completed AMRs included in this report are:
1 - Standby Shutdown Facility - Auxiliary Service Water (SSF-ASW) System Changes 2 - Fan and Damper Housings 3 - Keowee Turbine Guide Bearing Oil Coolers
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 3 1.0 Standby Shutdown Facility - Auxiliary Service Water (SSF-ASW) System Changes During the LRA, the SSF-ASW piping was classified as having external environments of sheltered and yard pipe. Yard pipe was considered piping above ground piping. In addition, it was initially thought that the SSF-ASW had an internal environment of just service water.
ONS had a leak in a section of underground SSF-ASW piping. During the Failure Investigation Process (FIP), it was identified that the LRA did not appropriately represent the SSF-ASW piping. A portion of the SSF-ASW piping is buried piping (external environment -Underground).
It was also identified that certain sections of SSF-ASW piping are filled with demineralized (treated) water. An EC was performed to replace a portion of the underground portion of piping.
The existing material was carbon steel, and the new material used was stainless steel.
Impact on ONS UFSAR Chapter 18 No changes are required in Chapter 18 of the UFSAR for the Condenser Circulating Water Internal Coating Inspection Program or the Service Water Piping Corrosion Program.
Tables 1.1 and 1.2 contain the AMR review summary for internal and external environments.
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 4 Table 1.1 Aging Management Review Summary Table SSF-ASW System Internal Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Loss of Material Service Water Piping Pressure Carbon Steel Treated Water Galvanic GeraCoosn Corrosion Corrosion Program Pie Pressure General Corrosion Pipe Boundary Pitting Corrosion Stainless Steel Treated Water Loss of Material Service Water Piping Pitting Corrosion Corrosion Program Table 1.2 Aging Management Review Summary Table SSF-ASW System External Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Loss of Material Condenser Circulating Water Galvanic Corrosion Internal Coating Inspection Carbon Steel Underground General Corrosion Program Pressure Pitting Corrosion Pipe Boundary MIC Loss of Material Condenser Circulating Water Stainless Steel Underground Pitting Corrosion Internal Coating Inspection MIC Program
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 5 2.0 Fan and Damper Housings In accordance with RIS 2007-16, the NRC expects applicants to identify active mechanical component housings that require an AMR pursuant to 10 CFR 54.21. This determination considers whether failure of the housing would result in a failure of the associated active mechanical component to perform its intended function, and whether the housing meets the long-lived and passive criteria as defined in the Rule.
Specifically, housings for fans and dampers that perform a pressure retention and/or structural integrity function, which if not maintained, could prevent the associated active mechanical component from performing its intended function. Housings that perform these functions and meet the long-lived and passive criteria are subject to an AMR.
ONS considered the non-active part of a component that performs a function within the scope of Part 54 (e.g., Fan and Damper Housings). These reviews considered not just the active mechanical component, but also the intended function of its associated housing. The following Air Conditioning, Heating, Cooling and Ventilation Systems within the scope of License Renewal were evaluated as part of this process:
" Standby Shutdown Facility HVAC
- Reactor Building Cooling System
" Auxiliary Building Ventilation System
- Control Room Pressurization and Filtration System
- Penetration Room Ventilation System
" Reactor Building Purge System Although the Fan and Damper Housings were evaluated as an integral part of the "Ductwork" commodity in the original LRA since they also perform a pressure boundary component intended function, these components were not explicitly identified as a commodity group such as "Fan and Damper Housings" in the submittal.
Impact on ONS UFSAR Chapter 18 New UFSAR sections have been generated and incorporated into Chapter 18, Section 3.17, Preventative Maintenance Activities.
Tables 2.1 and 2.2 contain the AMR review summary for internal and external environments.
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 6 Table 2.1 Aging Management Review Summary Table Fan and Damper Housings Internal Environments Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring TypeFunction Management Program/Activity Aluminum Air None None Fan Pressure Galvanized Air Loss of Material - Preventative Maintenance Activities Reactor Housings Boundary Steel Stainless General Corrosion RatrSanesAir None None Building Steel Purge System Aluminum Air None None Damper Pressure Galvanized SteelAi Air Loss of Material -
GeeaCorso Preventative Maintenance Activities PrvnaieMntaceciiis Housings Boundary tlGeneral Corrosion Stainless Air None None Steel Aluminum Air None Loss of Material -. None PenetrationPntainGalvanized Room Fan Pressure Stee Air L orrion Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANne System Steel Air None None Aluminum Air None None Reactor Building Fan Pressure Sted Air Loss of Material - Preventative Maintenance Activities Cooling Housings Boundary StlGeneral Corrosion System Stainless Air None None
___________ ________ Steel __________________________________
Aluminum Air None None Building Fan Pressure Galvanized Air Loss of Material - Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANne System Steel Air None None
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 7 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Program/Activity Management Aluminum Air None None Building Damper Pressure Galvanized Air Loss of Material - Preventative Maintenance Activities Ventilation Housings Boundary Stainless ANne System Steel Air None None Aluminum Air None None Galvanized Loss of Material -
Fan Pressure Steel Air General Corrosion Preventative Maintenance Activities Control Room Housings Boundary Stainless Air None Pressurization Steel and Filtration Aluminum Air None None System Galvanized Loss of Material -
Damper Pressure Steel Air General Corrosion Preventative Maintenance Activities Housings Boundary Stainless Air None Steel Aluminum Air None None Galvanized Ar Loss of Material -
Fan Pressure Air Preventative Maintenance Activities Housings Boundary Steel General Corrosion Standby Stainless Air rNnoSte None None S h utd o w n Al menl mA Facility HVAC Aluminum Air None None Damper Pressure Galvanized Air Loss of Material - Preventative Maintenance Activities Housings Boundary Steel General Corrosion Stainless Air None None Steel
U. S, Nuclear Regulatory Commission July 1, 2013 Attachment Page 8 Table 2.2 Aging Management Review Summary Table Fan and Damper Housings External Environments Component ended Aging Effect Aging Management System Type Function Material Environment Requiring Type Function Management Program/Activity Reactor Loss of Material -
Boric Acid Corrosion Program Buildina Boric Acid Wastaae Aluminum I. - __________________________________
Loss of Material -
Sheltered Boric Acid Corrosion Program Boric Acid Wastage Loss of Material -
Reato Borc Ad Wasteiage - Boric Acid Corrosion Program Sheltered Loss of Material - Inspection Program for Civil General Corrosion Engineering Structures and Fan Pressure Boric Acid Wastage Housings Boundary GalvanizedComponents Steel Loss of Material -
Bori Wasage Aci Boric Acid Corrosion Program Sheltered Loso aeil- Inspection Program for Civil Reactor Lossra Cofratroian Engineering Structures and Building Geneal orroion Components Purge System Reactor Stainless None None Buildina Steel -, 4 Sheltered None None Loss of Material -
Aluminum Sheltered Boric Acid Corrosion Program Boric Acid Wastage Material -w Boric of Loss Ad Wasteiae - Boric Acid Corrosion Program Boric Acid Wastage Damper Pressure Galvanized Sheltered Inspection Program for Civil Housings Boundary Steel Loss of Material General Corrosion- Engineering Structures and GComponents Stainless Sheltered None None i h Steel I I i
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 9 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Program/Activity
________ __________ Management PormAtvt Aluminum Sheltered None None Penetration Inspection Program for Civil Room Fan Pressure Steel ofeMterian Engineering Structures and Ventilation Housings Boundary SteComponents SystemStils Stail Sheltered None None Aluminum Reactor Loss of Material -
Aluminum__ Building Boric Acid Wastage Boric Acid Corrosion Program ReactorLoss of Material -
Reactor Borc Ad Wasteiage - Boric Acid Corrosion Program Building Fan Pressure Galvanized Boric Acid Wastage Cooling Housings Boundary Steel Sheltered Loss of Material - Inspection Program for Civil System General Corrosion Engineering Structures and Components Stainless Sheltered None None Steel Loss of Material -
Aluminum Sheltered Boric Acid Wastage Boric Acid Corrosion Program Auxiliary Loss of Material - Boric Acid Corrosion Program Building Fan Pressure Galvanized Sheltered Loss of Mate Inspection Program for Civil Ventilation Housings Boundary Steel Loss of Materiala-GeeralCorrsion Engineering Structures and Systm System General Corrosion Components Stainless Sheltered None None Steel I
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 10 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring TypeFunction Management Program/Activity Aluminum Sheltered Loss Aluminum Shetere Boric of Material Acid -
Wastage Boric Acid Corrosion Program Auxiliary Loss of Material - Boric Acid Corrosion Program Building Damper Pressure Galvanized Sheltered Boric of Mate Inspection Program for Civil Ventilation Housings Boundary Steel Loss of Material - ineerin Progra nd System General Corrosion
___________Components Engineering Structures and Stainless Sheltered None None Steel Aluminum Sheltered None None Galvanized Loss of Material - Inspection Program for Civil Fan Pressure Steel Sheltered General Corrosion Engineering Structures and Housings Boundary Components Control Room Stainless Sheltered None None Pressurization Steel and Filtration Aluminum Sheltered None None System Galvanized Loss of Material - Inspection Program for Civil Damper Pressure Steel Sheltered General Corrosion Engineering Structures and Housings Boundary Components Stainless Sheltered None None Steel Aluminum Sheltered None None Standby Galvanized Loss of Material - Inspection Program for Civil Shutdown Fan Pressure Steel Sheltered General Corrosion Engineering Structures and Facility HVAC Housings Boundary Components Stainless Sheltered None None Steel
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 11 Component Intended Aging Effect Aging Management System Type Function Material Environment Requiring Type_____Function_______ Management Program/Activity Aluminum Sheltered None None Standby Galvanized Loss of Material - Inspection Program for Civil Shutdown Damper Pressure Steelvanid General Corrosion Engineering Structures and
..... . Housinas Boundarv ComDonents
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 12 3.0 Keowee Turbine Guide Bearing Oil Coolers The Turbine Guide Bearing Oil System includes the Turbine Guide Bearing Oil Coolers that are within the scope of License Renewal. The Turbine Guide Bearing Oil Coolers provide the necessary flow of lubricating oil to the Keowee turbine guide bearings.
Although the Turbine Guide Bearing Oil Coolers were originally included within the scope of License Renewal in the original LRA, the heat transfer intended function for these heat exchangers was not identified at that time, only the pressure boundary intended function. Heat transfer has since been identified as a License Renewal intended function for these components as part of the Problem Investigation Program (PIP).
Impact on ONS UFSAR Chapter 18 A new UFSAR section has been generated and incorporated into Chapter 18, Section 3.17, Preventative Maintenance Activities.
Tables 3.1 and 3.2 contain the AMR review summary for internal and external environments.
U. S. Nuclear Regulatory Commission July 1, 2013 Attachment Page 13 Table 3.1 Aging Management Review Summary Table Keowee Turbine Guide Bearing Oil Coolers Internal Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity Heat 3.1.1 Heat Transfer Tubes Transfer Stainless Steel Raw Water Degradation - 3.1.2 Preventative
_Fouling Maintenance Activities Table 3.2 Aging Management Review Summary Table Keowee Turbine Guide Bearing Oil Coolers External Environments Component Intended Material Environment Aging Effect Requiring Aging Management Type Function Management Program/Activity TueHTasera Heat tilesSeeti HKeowee Heat Transfer Oil Sampling Program Tubes Transfer Stainless Steel Oil Degradation - Fouling Preventative Maintenance I I_ I I I Activities