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MONTHYEARML0703900492007-01-31031 January 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds Project stage: Request ML0706001692007-02-22022 February 2007 Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds Project stage: Request ML0707901132007-03-27027 March 2007 Confirmatory Action Letter Project stage: Other ML0715605042007-05-29029 May 2007 Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Project stage: Request ML0721304972007-09-12012 September 2007 Completion of Actions for Confirmatory Action Letter NRR-07-022 Project stage: Other ML0726201492007-09-13013 September 2007 Fourth Ten Year Inservice Inspection Interval Request for Relief No. 07-ON-004 Project stage: Request 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 Project stage: Request ML0801602112008-01-30030 January 2008 Closure of Confirmatory Action Letter NRR-07-022 Project stage: Other 2007-03-27
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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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BRUCE H HAMILTON Duke Vice President Energye Oconee Nuclear Station Duke Energy Corporation ONO] VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy.com December 13, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2, and 3 Docket No. 50-270,-287 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 By letters dated January 31, 2007 (ADAMS Accession #
ML070390049) and February 22, 2007 (ADAMS Accession #
ML070600169), Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC (Duke) committed to a mitigation schedule regarding Alloy 82/182 butt welds on Pressurizer piping for Units 2 and 3 of the Oconee Nuclear Station (Oconee). The NRC Confirmatory Action Letter (CAL) of March 27, 2007 (ADAMS Accession # ML070790113) regarding Alloy 82/182 butt welds requires a report within 60 days of unit restart of any mitigative actions taken on the subject welds.
In order to support these mitigative actions, on March 12, 2007 Duke submitted Relief Requests (RR) 07-ON-001 (ADAMS Accession #
ML070790293) to support application of full structural weld overlays on various pressurizer nozzle to flange, nozzle-to-safe end, and surge line welds. NRC verbally approved this request on May 17, 2007 and provided written approval by letter dated August 6, 2007 (ADAMS Accession #. ML071280781). In this request Duke committed to provide a report summarizing the results of the UT examinations of the weld overlays within 14 days of completion of the UT examinations.
By letter dated May 29,. 2007, (ADAMS Accession # ML071560504)
Duke notified the NRC of the completion of the actions '
applicable to Unit 2 within the scope of the CAL, and included www. duke-energy. com 0 W
U. S. Nuclear Regulatory Commission Page 2 December 13,. 2007 the report relative to UT examinations for associated weld overlays as committed in RR 07-ON-001.
In addition, on September 13, 2007, Duke submitted RR 07-ON-004 (ADAMS Accession # ML072620149), applicable to all three Oconee units, to seek similar relief related to full structural weld overlays on the Decay Heat Removal (DHR) Drop line to Hot Leg Nozzle welds. These welds are not subject to the CAL, but the RR also included a commitment to provide the results of the UT examinations within 14 days of completion of examinations on the DHR line overlay. The NRC staff provided verbal approval of RR 07-ON-004 on November 27, 2007.
This letter is to inform you of the completion of the mitigative repairs for Oconee Unit 3 as listed oh Enclosure 4 of our January 31, 2007 letter. These actions were completed during 3EOC23 refueling outage and complete the actions related to all three Oconee units to satisfy the CAL. Enhanced leakage detection requirements committed to in our February 22, 2007 letter are no longer required on any Oconee unit due to the completion of mitigation of the subject welds.
Also, the Unit 3 UT examinations of the Pressurizer and DHR drop line weld overlays were completed November 30, 2007. No flaws outside the IWB-3514 criteria were identified, and no.repairs were made to. the weld overlays, the original base materials or original 82/182 weld materials. The attached Enclosure provides a report summarizing the results of these examinations, per the commitments contained in RR 07-ON-001 and RR 07-ON-004, respectively.
Thus this letter provides the required response for the CAL and its Enclosures satisfy the RR commitments for work performed during 3E0C23.
If there are any questions, please contact Randy Todd at (864) 885-3418.
Very truly yours, B.H.*Hamilton Vice President Oconee Nuclear Site Enclosure 2 of 5
U. S. Nuclear Regulatory Commission Page 3 December 13, 2007 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D.C. 20555 Dr. W. D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. D. W. Rich Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Section Manager Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.
Columbia, SC 29201
U. S. Nuclear Regulatory Commission Page 4 December 13, 2007 bxc w/att:
R. L. Gill, Jr.
T. J. Coleman D. W. Peltola P. A. Wells D. H. Llewellyn C. R. Frye J. M. Shupping W. R. Cauthen V. B. Dixon B. W. Carney, Jr.
R. P. Todd M. A. Pyne E. B. Miller, Jr.
L. C. Keith G. L. Brouette (ANII)
J. J. Mc Ardle III D. B. Coyle J. E. Smith ISI Relief Request File' NRIA File/ELL EC050 Document Control 4 of 5
U. S. Nuclear Regulatory Commission December 13, 2007 Enclosure Weld Overlay Ultrasonic Examination 3EOC23 Summary Report Pressurizer Weld Overlays Reference Relief Request 07-ON-001 Safety/Relief Nozzle Weld: 3-PZR-WP91-3 Safety/Relief Nozzle Weld: 3-PZR-WP91-1 Safety/Relief Nozzle Weld: 3-PZR-WP91-2 Spray Nozzle Welds: 3-PZR-WP45; 3-PSP-1 Surge Nozzle Weld: 3-PZR-WP23 Hot Leg Surge Nozzle Welds: 3-PHB-17; 3-PSL-10 Decay Heat Removal Drop Line Weld Overlay Reference Relief Request 07-ON-004 Hot Leg Decay Heat Nozzle Welds:
3-PHA-17; 3-53A-18-11 1 of 5
Ultrasonic Examination Procedure SI-UT-126 Revision 3, Procedurefor the PhasedArray UltrasonicExamination of Weld OverlaidSimilar and DissimilarMetal Welds, was used during the examinations. This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center. No flaws outside the ASME Section XI Table IWB-3514-1, Table IWB-3514-2, or Table IWB-3514-3 acceptance standards were identified and no repairs were made to the weld overlays, the original base materials or original 82/182 weld materials.
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-3 Examination Date: November 22, 2007 Examination Time: 12:23 - 13:25 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 0' through 830 (in 10 Increments Circumferential Examination Angles: 0' through 64' (in 1' Increments)
Examination Summary: One subsurface flaw indication in the weld overlay material (above the interface of the butt weld and the inconel buttering) was observed during the examinations. The flaw was not crack-like and is believed to be welding-related. The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3 514-2 and was found to be acceptable. The following Table provides flaw evaluation details:
Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%
1.0" 0.025" 0.025 5.56% 9.22%
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-1 Examination Date: November 22, 2007 Examination Time: 02:34 - 02:59 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 640 (in 10 Increments)
Attachment to SIR-07-393, Rev. 1 2 of 5 Structural IntegrityAssociates, Inc.
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-2 Examination Date: November 22, 2007 Examination Time: 02:34 - 03:04 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 0' through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 64' (in 10 Increments)
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Spray Nozzle Weld Overlay Examination Component Identification: Nozzle to Safe End Weld: 3-PZR-WP45 Safe End to Pipe Weld: 3-PSP-1 Examination Date: November 22, 2007 Examination Time: 03:05 - 03:44 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 820 (in 1V Increments)
Circumferential Examination Angles: 0' through 640 (in 10 Increments)
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-07-393, Rev. 1 3 of 5 Structural IntegrityAssociates, Inc.
Surge Nozzle Weld Overlay Examination Component Identification: Nozzle to Safe End Weld: 3-PZR-WP23 Examination Date: November 23, 2007 Examination Time: 23:28 to 01:26 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments) - Circumferential Examination Angles: 00 through 68' (in 10 Increments)
Examination Summary: One subsurface flaw indication in the ferritic nozzle material (about 0.50" below the ferritic steel surface and 0.35" from the nozzle buttering) was observed during the examinations. The flaw was not crack-like and is believed to be nozzle material-related. The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3514-1 and was found to be acceptable. The following Table provides flaw evaluation details:
Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%
1.0" 0.033" 0.03 2.88% 12.37%
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Hot Leg Surge Nozzle Weld Overlay Examination Component Identification: Nozzle to Butter/Safe End Weld: 3-PHB-17 3-PSL-10 Examination Date: November 30, 2007 Examination Time: 14:46 to 16:49 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 650 (in 10 Increments)
Examination Summary: Two subsurface flaw indications in the weld overlay material (about 0.05" above the surface of the inconel buttering) were observed during the examinations. The flaw was not crack-like and is believed to be welding-related. The flaw indications were sized, Attachment to SIR-07-393, Rev. 1 4 of 5 Structural IntegrityAssociates, Inc.
characterized and compared to the acceptance standards of Table IWB-3514-2 and were found to be acceptable. The following Table provides flaw evaluation details:
Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%
2.90" 0.004" 0.00 0.55% 8.85%
2.30" 0.006" 0.00 0.79% 8.85%
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Hot Leg Decay Heat Nozzle Weld Overlay Examination Component Identification: Nozzle to Butter/Safe End Weld: 3-PHA-17 3-53A-18-11 Examination Date: November 30, 2007 Examination Time: 20:30 to 21:30 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 700 (in 10 Increments)
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-07-393, Rev. 1 5 of 5 U StructuralIntegrityAssociates, Inc.