Letter Sequence Other |
---|
EPID:L-2022-LLR-0060, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. (Open) |
|
MONTHYEARML22139A2302022-05-19019 May 2022 NRR E-mail Capture - Acceptance Review for Summer TS 4.6.2.1.d LAR (L-2022-LLR-0060) Project stage: Acceptance Review RA-22-0174, Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems.2022-07-27027 July 2022 Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems. Project stage: Request ML22235A6552022-08-23023 August 2022 Acceptance of Requested Licensing Action Proposed Alternative to Use ASME Code Case N-752 Project stage: Acceptance Review ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 Project stage: RAI RA-23-0051, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities2023-03-0909 March 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to Use American Society of Mechanical Engineers Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities Project stage: Response to RAI ML23125A1452023-05-0505 May 2023 Change in Estimated Review Schedule and Level of Effort for Proposed Alternative to Use Code Case N-752 Project stage: Other 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 Project stage: Other ML23269A0412023-08-22022 August 2023 Code Case N-752 Audit; August 22, 2023, E-mail Providing Additional Information Regarding Design and Quality Program Requirements Project stage: Other ML23270B8362023-09-26026 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 Project stage: Other 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 Project stage: Other ML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) Project stage: RAI ML23331A9212023-11-16016 November 2023 Public - Non-Concurrence of SE for Proposed Alternative RR-22-0174 for Oconee Nuclear Station, Units 1, 2, and 3 Duke Energy Carolinas, LLC Project stage: Request 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 Project stage: Other 2023-12-13
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML23349A0272023-12-15015 December 2023 Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 5.5.2 ML23284A3322023-10-11011 October 2023 Request for Additional Information Alternative Request (RA-22-0174) (L-2022-LLR-0060) ML23270B8362023-09-26026 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 ML23267A0032023-09-21021 September 2023 RP Inspection Document Request ML23269A0412023-08-22022 August 2023 Code Case N-752 Audit; August 22, 2023, E-mail Providing Additional Information Regarding Design and Quality Program Requirements ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23144A0862023-05-24024 May 2023 Acceptance of Requested Licensing Action Proposed Relief Request (RA-23-0018) to Use ASME Code Case 853 ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23125A1452023-05-0505 May 2023 Change in Estimated Review Schedule and Level of Effort for Proposed Alternative to Use Code Case N-752 ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23095A0052023-04-0404 April 2023 002 Radiation Safety Baseline Inspection Information Request ML23086C0362023-03-27027 March 2023 Request for Additional Information Steam Generator Tube Inspection Report (03R31) ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML23038A1832023-02-0707 February 2023 Request for Additional Information Alternative Request (RA-22-0174) to Use ASME Code Case N-752 ML23031A1552023-01-17017 January 2023 1/17/2023 Email from John Moses, Deputy Director, Division of Rulemaking, Environmental, and Financial Support, to Diane Curran, Counsel to Beyond Nuclear and the Sierra Club, Request for Extension of Scoping Comment Period for Oconee EIS ML22294A0812022-10-21021 October 2022 Nrc/Duke Steam Generator Inspection Call for November 8, 2022 NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22251A2902022-09-0808 September 2022 Request for Additional Information Additional Mode Change Limitations Applicable to the Adoption of Technical Specifications Tasks Force Traveler (TSTF) No. 359, Revision 9 ML22235A6552022-08-23023 August 2022 Acceptance of Requested Licensing Action Proposed Alternative to Use ASME Code Case N-752 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22234A1262022-07-0808 July 2022 Email from NRC to Duke - Feedback on Trp 76 RAI Responses - July 8, 2022 ML22234A1272022-06-14014 June 2022 Email from NRC to Duke - Feedback on Trp 76 RAI Responses - June 14, 2022 ML22154A2142022-06-0101 June 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - 2nd Round RAI B2.1.7-4b ML22157A0012022-06-0101 June 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Additional NRC Comments on RAI 4.6.1-1a ML22124A2052022-05-0404 May 2022 Summary of May 4, 2022, Clarification Call with Duke Energy Carolinas, LLC, Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System ML22124A1612022-05-0303 May 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.7-4a ML22122A0192022-04-28028 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B2.1.9-2a ML22122A1322022-04-27027 April 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round Requests for Additional Information (FE 3.5.2.2.2.6 - Irradiation Structural) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22130A0112022-04-25025 April 2022 Email: Oconee SLRA - RAI 4.6.1-1a - NRC Staff Comments ML22112A1892022-04-22022 April 2022 Acceptance Review for Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9 ML22112A0072022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Confirmation of Information 3.5.2.2.2.6-L ML22113A0082022-04-20020 April 2022 Email from Marieliz Johnson (NRC) to Steve Snider (Duke) - Oconee SLRA - Request for Additional Information 3.1.2-1 ML22088A0452022-03-28028 March 2022 Radiation Safety Baseline Inspection Initial Information Request Inspection Report 2022002 ML22081A0052022-03-21021 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - 2nd Round RAI B4.1-3 ML22080A0792022-03-16016 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 4 (2nd Round Rais) ML22075A2032022-03-11011 March 2022 Email from Duke to NRC - Follow-Up Items from March 7, 2022 Public Meeting ML22074A0022022-03-11011 March 2022 Email from Duke to NRC - Follow-up Item from March 7, 2022 Public Meeting - SSW Tendon AMP ML22069A0022022-03-0808 March 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Confirmation of Information - Set 4 ML22063A4502022-03-0404 March 2022 Request for Additional Information Application to Revise TS 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump ML22063A1152022-02-23023 February 2022 Email from Duke to NRC - Follow Up Item from February 17, 2022 Public Meeting ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22035A1892022-01-31031 January 2022 Email from NRC (Angela Wu) to Duke (Paul Guill) - Oconee SLRA - Request for Public Meeting ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22019A1032022-01-18018 January 2022 Email from Angela Wu (NRC) to Steve Snider (Duke) - Oconee SLRA - Requests for Additional Information - Set 3 ML22012A0432022-01-11011 January 2022 SLRA - Requests for Additional Information - Set 2 2023-09-26
[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
[Table view] |
Text
From: Vaughan, Jordan L To: Shawn Williams Cc: Varnedoe, Jennifer Maye
Subject:
[External_Sender] Duke Follow-up on Code Explanation and Owners Requirements Date: Tuesday, September 26, 2023 4:27:53 PM Attachments: Owners Requirements Discussion_Final.pdf
- Shawn, See attached. As discussed earlier today, Duke is comfortable with this information being made publicly available (including this e-mail) and referenced in the Audit Summary.
This write-up has also been added to the Certrec Portal for the reviewers.
Jordan
Concerns expressed by NRC
- 1. An owner could use Owner's Requirements to establish all the requirements for an item and completely circumvent use of Construction Codes
- 2. Use of may/shall in the case and submittal permit use of engineering judgment in lieu of code and standards Duke Response:
Owner's Requirements is a defined term with specific meaning in Section XI that distinguishes Owners Requirements from Code requirements, establishing two separate sets of requirements. This is a Section XI convention that exists in the base code editions/addenda and was implemented in Code Case N-752 and the Oconee submittal to retain consistency with code editions/addenda in use in the industry.
In laymans terms, the Design Specification requirements for an item are comprised of code requirements, regulatory requirements (e.g. conditions applicable to a construction code), and Owner's Requirements.
Duke submittal paragraph 5.2.E.4, patterned after Code Case N-752, -1420(d), states:
Items used for repair/replacement activities shall meet the Owners Requirements or revised Owners Requirements as permitted by the licensing basis.
Duke submittal paragraph 5.2.E.5, patterned after Code Case N-752, -1420(e), states:
Items used for repair/replacement activities shall meet the Construction Code to which the original item was constructed. Alternatively, items used for repair/replacement activities shall meet the technical requirements of a nationally recognized code, standard, or specification applicable to that item as permitted by the licensing basis.
Application:
Paragraph 5.2.E.4 establishes the Owners Requirements for items to be used for repair/replacement under Code Case N-752. Since Owner's Requirements is given specific meaning distinct from Code requirements, paragraph 5.2.E.5 is needed to establish code requirements for an item to be used for replacement under Code Case N-752. The two sets of requirements comprise a full set of requirements for an item, Owners and Code Requirements. Submittal paragraphs 5.2.E.4 and 5.2.E.5 are parallels to the 2017 edition of ASME Section XI, IWA-4221, Construction Code and Owners Requirements which describes use of Owners and Code requirements. These two paragraphs are consistent with current Section XI code requirements.
Paragraph 5.2.E.4 is met by either meeting the original Owner's Requirements for the item or revised Owner's Requirements. This paragraph does not discuss use of Owner's Requirements in lieu of Code requirements and does not grant any permissions in that regard. Revised Owner's Requirements must be evaluated as required by 5.2.E.3.
Paragraph 5.2.E.5 requires that replacement items meet the original Construction Code or, alternatively, technical requirements of a nationally recognized code, standard, or specification applicable to that item as permitted by the licensing basis. Thus, Owner's
Requirements cannot wholly replace Construction Code requirements because items must meet one of these two 5.2.E.5 requirements (original construction code or alternate code).
The continued use of distinct Owners and Code requirements in Code Case N-752 and the submittal has been similarly established in code edition/addenda, and the specific requirements provided for each to prevent indiscriminate substitution of Owners Requirements for Code requirements.
Code Case N-752 does provide two specific owner permissions and similar permissions are requested in the submittal in paragraphs 5.2.E.7 and 5.2.E.8 which will be discussed below.
Duke submittal paragraph 5.2.E.6, patterned after Code Case N-752, -1420(f), states:
The repair methods of nationally recognized post-construction codes and standards (e.g., PCC-2, API-653) applicable to the item may be used.
Application:
This paragraph allows the use of nationally recognized post-construction codes and standards applicable to the item. The word shall is not used because shall would establish that these nationally recognized post-construction codes and standards must be used. The use of the word may retains the flexibility to use Section XI code, if desired or if there is not a nationally recognized post-construction codes or standard applicable to the item.
Duke submittal paragraph 5.2.E.7, patterned after Code Case N-752, -1420(g), states:
Performance of repair/replacement activities, and associated nondestructive examination (NDE), shall be in accordance with the Owners Requirements and, as applicable, the Construction Code, or postconstruction code or standard, selected for the repair/replacement activity. Alternative examination methods may be used as approved by the Owner. NDE personnel may be qualified in accordance with IWA2300 in lieu of the Construction Code.
Duke submittal paragraph 5.2.E.8, patterned after Code Case N-752, -1420(h), states:
Pressure testing of the repair/replacement activity shall be performed in accordance with the requirements of the Construction Code selected for the repair/replacement activity or shall be established by the Owner.
Application:
Paragraph 5.2.E.7 states that performance of repair/replacement activities (reference IWA-4110b) will have both the Owners Requirements and either the Construction Code, or postconstruction code or standard, selected for the repair/replacement activity. The activities (e.g. welding, brazing, defect removal, procurement, design, fabrication, installation, examination and pressure testing of items) will follow a nationally recognized Construction Code, or postconstruction code or standard similar to the requirement in submittal paragraph 5.2.E.5.
It also allows alternate NDE examination methods which are discussed below along with paragraph 5.2.E.8.
These paragraphs (the NDE portion of 5.2.E.7 and all of 5.2.E.8) permit specific alternatives to the code or standard, but not wholesale use of Owners Requirements to substitute for code requirements. Paragraph 5.2.E.7 allows for alternative NDE methods and 5.2.E.8 allows for pressure testing requirements to be determined by the owner.
However, these permissions are also subject to paragraph 5.2.E.3, which states:
Changes in configuration, design, materials, fabrication, examination, and pressure-testing requirements used in the repair/replacement activity shall be evaluated, as applicable, to ensure the structural integrity and leak tightness of the system are sufficient to support the design bases functional requirements of the system.
Duke submittal paragraph 5.2.E.9, patterned after Code Case N-752, -1420(i), states in part:
Baseline examination (e.g., preservice examination) of the items affected by the repair/replacement activity, if required, shall be performed in accordance with requirements of the applicable program(s) specifying periodic inspection of items.
Application:
In paragraph 5.2.E.9, the if required statement pertains to the scoping of the preservice ISI or IST examinations. The ASME Code Case N-752 LSS components may, or may not, be within the scope of those programs. If the ASME Code Case N-752 LSS components are not within the scope of those programs, then the examinations are not required. If the ASME Code Case N-752 LSS components are within the scope of those programs, then the examinations are determined by the program requirements.
Duke submittal paragraph 5.2.E.16 states:
As permitted by Code Case N-752, Duke Energy intends to implement the exemption on IWA-4000 applicable to repair/replacement activities. Article IWA-4000 of the ASME Section XI Code specifies administrative, technical, and programmatic requirements for performing repair/replacement activities on pressure-retaining items and their supports. As specified in IWA-4110(b), repair/replacement activities "include welding, brazing, defect removal, metal removal by thermal means, rerating, and removing, adding, and modifying items or systems.
These requirements are applicable to procurement, design, fabrication, installation, examination, and pressure testing of items within the scope of this Division". In lieu of these IWA-4000 requirements, Duke Energy will perform repair/replacement activities on LSS items in accordance with an Owner-defined program that complies with paragraph -1420 of Code Case N-752. The Duke Energy program will utilize existing Duke Energy processes such as those applicable to procurement, design, re-rating, fabrication, installation, modifications, welding, defect removal, metal removal by thermal processes and supplement those process requirements as necessary to comply with Code Case N-752. Duke Energy believes this program will ensure, with reasonable confidence, that LSS items remain capable of performing their safety-related functions under design basis conditions. Finally, the exemption of IWA-4000 requirements and the alternative use of Owner-defined treatment requirements for LSS items is consistent with the NRCs position on risk- informed programs as specified in 10 CFR 50.69(b)(1)(v) and (d)(2).
Application:
This paragraph is stating Duke will use existing infrastructure (e.g. Welding Program, Design Control, Procurement, procedures and practices, etc.) to implement Code Case N-752. Specifically, how the activities listed in paragraph 5.2.E.16 would be completed are addressed in items 5.1.E 1-17.
==
Conclusion:==
Select repair/replacement tasks (e.g. NDE methods, pressure testing) allow the Owner to establish requirements for the activity. Code Case N-752 requires that repair / replacement activities on LSS items follow a nationally recognized Construction Code, or post-construction code or standard, with the possible exception of Owner defined NDE methods and pressure testing. These requirements confirm, with reasonable confidence, that each LSS item will remain capable of performing its safety-related functions under design-basis conditions.
Furthermore, the Owner is required to ensure the structural integrity and leak tightness of the system are sufficient to support the design basis functional requirements of the system.
Condition monitoring programs (e.g. Technical Specifications, RI-ISI, License Renewal Aging Management, etc.) remain in effect to provide continued assurance that unknown degradation of these pressure retaining items is not occurring. Further, these condition monitoring programs monitor for operational leakage, which has the effect of ensuring Technical Specification structures, systems, and components remain operable and able to perform their safety function.
Finally, LSS categorized components that are classified as ASME BPV Code Class 2 and 3, and are required to be operable by plant Technical Specifications, will be treated in accordance with the licensees approved relief request requirements (aka in accordance with Code Case N-752). Even though the categorization process assumes a failure probability of 1.0 and shows that failure of these LSS SSCs will have a negligible impact on public health and safety, the relief request requires that, with reasonable confidence, LSS SSCs remain capable of performing their safety related functions under design basis conditions.