Letter Sequence Response to RAI |
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Category:Letter type:ONS
MONTHYEARONS-2018-025, 2017 Annual Radiological Environmental Operating Report (AREOR)2018-05-15015 May 2018 2017 Annual Radiological Environmental Operating Report (AREOR) ONS-2018-024, 2017 Annual Radioactive Effluent Release Report (ARERR)2018-04-30030 April 2018 2017 Annual Radioactive Effluent Release Report (ARERR) ONS-2018-032, Ufsar/Selected Licensee Commitment Changes2018-04-17017 April 2018 Ufsar/Selected Licensee Commitment Changes ONS-2018-029, Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 32018-04-0404 April 2018 Technical Specifications Task Force (TSTF) - 448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 3 ONS-2018-027, Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-0022018-03-28028 March 2018 Oconee, Units 1, 2, and 3, Submittal of Emergency Plan Revision 2018-002 ONS-2018-023, Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency2018-03-20020 March 2018 Response to Nrc'S Request for Additional Information Regarding Relief Request 17-ON-001; Alternative to Extend the Code Case N-770, Inspection Item B, Examination Frequency ONS-2018-017, Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan2018-03-15015 March 2018 Oconee, Units 1, 2, and 3, Submittal of Revised Evaluation to Emergency Plan ONS-2018-021, ISFSI - Submittal of 2017 Annual Effluent Release Report2018-03-0101 March 2018 ISFSI - Submittal of 2017 Annual Effluent Release Report ONS-2018-020, Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2018-02-26026 February 2018 Refuel 28 (O2R28) In-service Inspection (ISI) and Steam Generator In-service Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes ONS-2018-015, Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cabl2018-02-19019 February 2018 Duke Energy Response to Request for Additional Information; Request for Alternative to Codes and Standards Requirements Pursuant to 10 CFR 50.55a(z) to Satisfy 10 CFR 50.55a(h)(2) Associated with Bronze Tape Wrapped Emergency Power Cables i ONS-2018-014, License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-012018-02-12012 February 2018 License Amendment Request (LAR) for Changes to the Duke Energy Physical Security Plan - License Amendment Request No. 2018-01 ONS-2018-019, Submittal of Emergency Plan, Section B2018-02-0505 February 2018 Submittal of Emergency Plan, Section B ONS-2018-011, Ufsar/Selected Licensee Commitment Changes2018-01-25025 January 2018 Ufsar/Selected Licensee Commitment Changes ONS-2017-087, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ...2017-12-0404 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from ... ONS-2017-083, Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 02017-11-21021 November 2017 Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 0 ONS-2017-041, Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments2017-11-15015 November 2017 Revision to Tornado/Helb Mitigation Strategies and Regulatory Commitments ONS-2017-085, Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR)2017-11-15015 November 2017 Duke Energy Comments on the October 24, 2017, Public Meeting with NRC Committee to Review Generic Requirements (CRGR) ONS-2017-079, Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-11-13013 November 2017 Supplemental Information to Support NRC Review of Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-078, Emergency Plan Revision 2017-0042017-11-0909 November 2017 Emergency Plan Revision 2017-004 ONS-2017-074, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-032017-10-20020 October 2017 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-03 ONS-2017-067, Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 22017-10-16016 October 2017 Response to Request for Additional Information Regarding License Amendment Request for TSTF-448, Revision 3, Control Room Habitability, License Amendment Request No. 2015-03, Supplement 2 ONS-2017-069, (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement2017-10-13013 October 2017 (ONS) - Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement ONS-2017-070, Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0022017-10-0505 October 2017 Transmittal of Oconee, Units 1, 2, and 3, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-002 ONS-2017-072, Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency2017-10-0303 October 2017 Fifth Ten Year Lnservice Inspection Interval, Relief Request No. 17-0N-001; Alternative to Extend the Code Case N-770, Inspection Item B Examination Frequency ONS-2017-066, Registration for Use of General License Spent Fuel Cask Numbers 147 and 1482017-09-20020 September 2017 Registration for Use of General License Spent Fuel Cask Numbers 147 and 148 ONS-2017-061, Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations2017-08-10010 August 2017 Revised Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator License Examinations ONS-2017-060, Registration for Use of General License Spent Fuel Cask Numbers 145 and 1462017-08-0303 August 2017 Registration for Use of General License Spent Fuel Cask Numbers 145 and 146 ONS-2017-059, Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary2017-07-31031 July 2017 Transmittal of Response to March 12, 2012 Request for Information, Recommendation 2.1 Flooding, Required Response 3, Flooding Focused Evaluation Summary ONS-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 ONS-2017-047, Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 1442017-06-27027 June 2017 Registration for Use of General License Spent Fuel Cask Numbers 142, 143, and 144 ONS-2017-042, Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 22017-06-0101 June 2017 Additional Information Regarding License Amendment Request for Temporary Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, License Amendment Request No. 2015-08, Supplement 2 ONS-2017-040, Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0032017-05-22022 May 2017 Transmittal of Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-003 ONS-2017-037, 2016 Annual Radiological Environmental Operating Report2017-05-15015 May 2017 2016 Annual Radiological Environmental Operating Report ONS-2017-026, Submittal of Ufsar/Selected Licensee Commitment Change2017-04-11011 April 2017 Submittal of Ufsar/Selected Licensee Commitment Change ONS-2017-024, Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program2017-03-16016 March 2017 Revision 028 to ERTG-001, Emergency Response Organization and Emergency Services Training Program ONS-2017-001, Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 0452017-03-0202 March 2017 Submittal of Emergency Plan Program Procedure HP/O/B/1009/001 Rev 045 ONS-2017-017, Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 1, Revision 2017-001 ONS-2017-018, Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-0012017-03-0202 March 2017 Emergency Plan Implementing Procedures Manual Volume 2, Revision 2017-001 ONS-2017-015, End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval2017-02-24024 February 2017 End of Cycle 29 (1 EOC29) Refueling Outage Lnservice Inspection (ISI) and Steam Generator Lnservice Inspection (SG-ISI) Report, Fifth 10-Year ISI Interval ONS-2017-019, Technical Specification Bases Change 2015-092017-02-23023 February 2017 Technical Specification Bases Change 2015-09 ONS-2017-011, Emergency Plan Revised Evaluation2017-02-0202 February 2017 Emergency Plan Revised Evaluation ONS-2017-009, Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events.2017-02-0101 February 2017 Units 1, 2 & 3 - Notification of Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events. ONS-2017-004, Submittal of Core Operating Limits Report2017-01-12012 January 2017 Submittal of Core Operating Limits Report ONS-2017-006, Emergency Plan Revision 2016-0032017-01-12012 January 2017 Emergency Plan Revision 2016-003 ONS-2016-097, Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S)2016-11-17017 November 2016 Emergency Plan/Emergency Plan Implementing Procedures Manual, Revised 10CFR 50.54(q) Evaluation(S) ONS-2016-098, Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors2016-11-14014 November 2016 Special Report Per Technical Specification 5.6.6, Inoperability of Post Accident Monitoring Containment High Range Radiation Monitors ONS-2016-096, Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations2016-11-10010 November 2016 Revised Response to NRC Regulatory Issue Summary 2015-05, Preparation and Scheduling of Operator Licensing Examinations 2018-05-15
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0275, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-10-12012 October 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0146, Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI)2023-06-20020 June 2023 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information (RCI) RA-23-0104, Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report2023-04-26026 April 2023 Response to Request for Additional Information (RAI) Regarding Oconee Unit 3, Refuel 31 (O3R31) Steam Generator Tube Inspection Report 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 RA-22-0270, Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations2022-10-0707 October 2022 Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations RA-22-0192, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a2022-09-0202 September 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4a RA-22-0160, Subsequent License Renewal Application: Responses to ONS SLRA - Second Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.62022-07-25025 July 2022 Subsequent License Renewal Application: Responses to ONS SLRA - Second Round RAIs - Trp 76 (Irradiation Structural) - FE 3.5.2.2.2.6 RA-22-0193, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4b2022-07-0808 July 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI B2.1.7-4b RA-22-0158, Subsequent License Renewal Application - Response to ONS SLRA Second Round RAI B2.1.9-2a2022-06-0808 June 2022 Subsequent License Renewal Application - Response to ONS SLRA Second Round RAI B2.1.9-2a RA-22-0159, Subsequent License Renewal Application Response to ONS SLRA Request for Additional Information (RAI) 3.1.2-12022-05-27027 May 2022 Subsequent License Renewal Application Response to ONS SLRA Request for Additional Information (RAI) 3.1.2-1 RA-22-0137, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI 4.6.1-1a2022-05-20020 May 2022 Subsequent License Renewal Application Response to ONS SLRA Second Round RAI 4.6.1-1a RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0145, Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - RAI 3.5.2.2.2.6-L2022-05-11011 May 2022 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - RAI 3.5.2.2.2.6-L RA-22-0124, Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 42022-04-22022 April 2022 Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 4 RA-22-0129, Subsequent License Renewal Application, Response to ONS SLRA 2nd Round RAI B4.1-32022-04-20020 April 2022 Subsequent License Renewal Application, Response to ONS SLRA 2nd Round RAI B4.1-3 RA-22-0089, Response to Request for Additional Information Regarding Application to Revise Technical Specification 3.7.7, Low Pressure Service Water System, to Extend the Completion Time for One Required Inoperable LPSW2022-04-14014 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specification 3.7.7, Low Pressure Service Water System, to Extend the Completion Time for One Required Inoperable LPSW RA-22-0111, Subsequent License Renewal Application, Follow-up Request for Additional Information Set 2 and 3 Updates2022-03-31031 March 2022 Subsequent License Renewal Application, Follow-up Request for Additional Information Set 2 and 3 Updates RA-22-0105, Subsequent License Renewal Application - Responses to NRC Requests for Confirmation of Information - Set 42022-03-22022 March 2022 Subsequent License Renewal Application - Responses to NRC Requests for Confirmation of Information - Set 4 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 RA-22-0040, Subsequent License Renewal Application: Responses to NRC Request for Additional Information Set 32022-02-21021 February 2022 Subsequent License Renewal Application: Responses to NRC Request for Additional Information Set 3 RA-22-0023, Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information - Set 32022-01-21021 January 2022 Subsequent License Renewal Application - Response to NRC Requests for Confirmation of Information - Set 3 RA-22-0025, Supplemental Information for Relief Request to Utilize an Alternative Acceptance Criteria for Code Case, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material2022-01-20020 January 2022 Supplemental Information for Relief Request to Utilize an Alternative Acceptance Criteria for Code Case, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material RA-21-0332, Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 1 and Second Round Request for Additional Information B2.1.27-1a2022-01-0707 January 2022 Subsequent License Renewal Application Responses to NRC Request for Additional Information Set 1 and Second Round Request for Additional Information B2.1.27-1a ML22019A1182022-01-0707 January 2022 Enclosures 1,2 & 3: Oconee Nuclear Station, Units 1, 2 & 3, Subsequent License Renewal Application, Appendix E, Environmental Report - Index of Duke Energy'S Responses, Responses to NRC Requests for Confirmation of Information and NRC Reque ML22019A1232022-01-0707 January 2022 Subsequent License Renewal Application, Appendix E, Responses to Requests for Additional Information and Request for Confirmation of Information ML22019A1202022-01-0707 January 2022 Appendix K ML22019A1192022-01-0707 January 2022 Appendix 1-A - Oconee Nuclear Station 122.21(r)(2)-(13) Submittal Requirement Checklist ML22019A1242022-01-0707 January 2022 Attachment 1: Oconee Nuclear Station, Units 1, 2 & 3, Subsequent License Renewal Application, Appendix E - HDR, Inc., 2020 Clean Water Act Documents ML22019A1212022-01-0707 January 2022 Appendix 13-B Peer Reviewer Communication Log ML22019A1222022-01-0707 January 2022 Calculation of Permeability by the Falling Head Method RA-22-0002, Appendix 10-B - Pump and Pipe Selection Calculations for a Hypothetical Cooling Tower Retrofit at Oconee Nuclear Station2022-01-0707 January 2022 Appendix 10-B - Pump and Pipe Selection Calculations for a Hypothetical Cooling Tower Retrofit at Oconee Nuclear Station ML22007A0152022-01-0707 January 2022 Subsequent License Renewal Application, Appendix E Responses to Requests for Additional Information (Rai), and Request for Confirmation of Information RA-21-0325, Response to NRC Requests for Confirmation of Information - Set 22021-12-17017 December 2021 Response to NRC Requests for Confirmation of Information - Set 2 RA-21-0307, Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - Set 12021-12-0202 December 2021 Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - Set 1 RA-21-0269, Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-282021-11-0909 November 2021 Response to Request for Additional Information Regarding Alternative Request to Utilize American Society of Mechanical Engineers (ASME) Code Case OMN-28 RA-21-0270, Response to Second Request for Additional Information (RAI) Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-8532021-10-28028 October 2021 Response to Second Request for Additional Information (RAI) Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-853 RA-21-0242, Response to Request for Additional Information, Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection2021-08-31031 August 2021 Response to Request for Additional Information, Regarding Relief Request to Utilize an Alternative Acceptance Criteria for Code Case N-853, PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection RA-21-0219, Response to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals2021-08-0505 August 2021 Response to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Intervals RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-20-0267, Proposed License Amendment Request to Revise Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of Containment Building - Responses to Request for Additional Information2020-09-17017 September 2020 Proposed License Amendment Request to Revise Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of Containment Building - Responses to Request for Additional Information RA-19-0281, Response to NRC Request for Additional Information for the Fall 2018 Oconee Unit 1 Steam Generator Tube Rupture Inspection Report (RA-19-0093)2019-07-31031 July 2019 Response to NRC Request for Additional Information for the Fall 2018 Oconee Unit 1 Steam Generator Tube Rupture Inspection Report (RA-19-0093) RA-19-0301, Proposed Amendment to Renewed Facility Operating Licenses Regarding Revisions to Final Safety Analysis Report Sections Associated with Oconee Tornado Licensing Basis -Responses to Request for Additional Information2019-07-31031 July 2019 Proposed Amendment to Renewed Facility Operating Licenses Regarding Revisions to Final Safety Analysis Report Sections Associated with Oconee Tornado Licensing Basis -Responses to Request for Additional Information RA-19-0134, Duke Energy Response to NRC Request for Additional Information (RAI) Related to Oconee License Amendment Request 2018-052019-03-0707 March 2019 Duke Energy Response to NRC Request for Additional Information (RAI) Related to Oconee License Amendment Request 2018-05 RA-19-0116, Duke Energy Response to NRC Request for Additional Information (RAI) Related to Oconee License Amendment Request 2017-052019-02-26026 February 2019 Duke Energy Response to NRC Request for Additional Information (RAI) Related to Oconee License Amendment Request 2017-05 RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) 2023-07-07
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ENERGY 0NS-2016-050 June 1, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Duke Energy Carolinas, LLC (Duke Energy) Oconee Nuclear Station, Units 1, 2 and 3 Docket Numbers 50-269, 50-270, 50-287 Renewed License Numbers DPR-38, DPR-47, and DPR-55 Scott L. Batson Vice President Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.327 4 F. 864.873. 4208 Scott. Batson@duke-energy.com 10 CFR 50.55a
Subject:
Response to Request for Additional Information (RAI) for Oconee Relief Requests 15-0N-002
& 003, Limited.Volume Inspections from 1EOC27, 2EOC26 and 3EOC27 Pursuant to 10 CFR 50.55a(g)(5)(iii), Duke Energy submitted Relief Requests 15-0N-002 and 15-0N-003 on July 15, 2015, requesting that the NRC grant relief from the American Society of. Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) with respect to Limited Volume inspections due to the impracticality of inspecting the required volume in the fourth 10-year inservice inspection (ISi) interval.
The NRC submitted a Draft Request for Additional Information (RAI) via email dated February 22, 2016 regarding this Relief Request. Duke Energy determined no clarifications were needed to the draft RAI questions and thus is submitting answers to those RAI questions as an enclosure to this letter. There are no regulatory commitments associated with this letter. If there are any questions, or further information is needed, you *may contact David Haile in Regulatory Affairs at (864) 873-4742.
Sincerely, Scott L. Batson Vice President Oconee Nuclear Station
Enclosure:
Oconee Nuclear Station Unit 1, 2 and 3, Response to Request for Additional Information (RAI), regarding Relief Requests 15-0N-002
& 003 for Limited Volume Inspections.
ONS-2016-050 June 1, 2016 Page 2 cc: Ms. Catherine Haney Administrator Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. James R. Hall, Project Manager (ONS) (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-881 Rockville, MD 20852 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station ONS-2016-050
Enclosure:
Response to Request For Additional Information Enclosure Oconee Nuclear Station Unit 1, 2 and 3, Response to Request for Additional Information (RAI), regarding Relief Requests 15-0N-002
& 003 for Limited Volume Inspections.
RAI Response re: 15-0N-002
&003 Page 1 ONS-2016-050
Enclosure:
Response to Request For Additional Information
- 1. SCOPE (from NRC's RA/ document)
By two separate letters dated July 15, 2015 (ML 15202A032
& ML 15202A052), the licensee, Duke Energy Carolinas, LLC (Duke Energy), submitted Requests for Relief 15-0N-002 and 003 from requirements of the ASME Boiler and Pressure Vessel Code (Code),Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components for ONS 1, 2, and 3. These requests for relief apply to the fourth 10-year inservice inspection interval, in which ONS 1, 2, and 3 adopted the 1998 Edition through the 2000 Addenda of ASME Code,Section XI. In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee has submitted the subject requests for relief for limited examinations in multiple ASME Code Examination Categories.
The ASME Code requires that 100 percent of the examination volumes described in Tables IWB-2500 and IWC-2500 be performed during each interval.
The licensee stated that 100 percent of the ASME Code-required volumes are impractical to obtain at ONS 1, 2 and 3. 1 O CFR 50.55a(g)(5)(iii) states that when licensees determine that conformance with ASME Code requirements is impractical at their facility, they shall submit information to support this determination.
The U.S. Nuclear Regulatory Commission (NRC) will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to public safety and the burden imposed on the licensee.
NRC staff has reviewed the information submitted by the licensee, and based on this review, determined the following additional information or clarification is required to complete the technical evaluation.
- 2. REQUEST FOR ADDITIONAL INFORMATION 2.1 Requests for Relief 15-0N-002 and 15-0N-003, Examination Category B-A, Item 81.21, Pressure Retaining Welds in Reactor Vessel RA/ Question 2.1.1 The ASME Code states that essentially 100% of the "accessible length" of circumferential head welds must be examined.
The licensee stated that approximately 36 percent of the ASME-required volumetric coverage could be obtained on reactor pressure vessel (RPV) transition piece-to-lower head Welds 1-RPV-WR35, 2-RPV-WR35, and 3-RPV-WR35, on ONS 1, 2 and 3, respectively.
Schematics have been provided of the RPV lower lower head area depicting examination limitations caused by the incore instrumentation nozzles and flow stabilizers.
However, it is difficult to determine from the submitted drawings whether the 36 percent obtained is related to the entire weld length, or applies to only the ASME Code "accessible length" of the weld. Please state the accessible length of each of the RPV circumferential head welds, and clarify whether the 36% volumetric coverage obtained is applicable to the accessible length, or to the entire length of the weld. If applicable to the entire length, and the licensee has completed 100% of the accessible length, relief may not be required.
Duke Energy's Response RAI 2.1.1: The 36% coverage obtained is applicable to the entire length of the weld. The entire length of each weld was 449.25 inches and the obstruction length was 242.97 inches, leaving 206.28 inch of accessible weld length. The percentage coverage based on accessible length for these welds is also below the 90% minimum required.
RAI Response re: 15-0N-002
&003 Page2 ONS-2016-050
Enclosure:
Response to Request For Additional Information 2.2 Requests for Relief 15-0N-002, Examination Category B-J, Item 89.11, Pressure Retaining Welds in Piping RA/ Question 2.2.1 Configuration of Weld# 1-PDA 1-1: Section 6.4of15-0N-002 describes the configuration of the components joined by weld# 1-PDA 1-1. This weld joint includes a stainless steel safe end, but the licensee request does not provide any detail on components adjacent to the safe end which might affect the inspectability of the component.
Please clarify the following: (a) Clarify whether the safe end is welded to adjacent components such as pipe or elbow, and whether the ultrasonic beam will pass through the safe end, adjacent weld, and adjacent component (e.g., pipe or elbow) during inspection of the weld for which relief is requested; and (b) If the ultrasonic beam will pass through adjacent weld and components, identify the materials for the adjacent weld and components, and provide the distance between these components and weld # 1-PDA 1-1. Duke Energy's Response RAI 2.2.1: (a) The safe-end is about 2 feet long. On one end, weld 1-PDA1-1 attaches the safe-end to the Reactor Coolant Pump nozzle and on the other end a separate weld attaches the safe-end to an elbow. The weld to the "adjacent component" does not interfere with the inspection of weld 1-PDA 1-1. (b) The ultrasonic beam only passes through the stainless steel base material (Mat. Spec. A376 Type 316) during the safe-end side of the examination.
RA/ Question 2.2.2 Examination Coverage of Weld # 1-PDA 1-1: Section 6. 4 of 15-0N-002 describes the examination coverage of the component, which is reduced because the cast stainless steel material does not allow meaningful interrogation from the RCP-1A 1 side. Please clarify whether the licensee's best effort ultrasonic examination coverage included the weld root and heat affected zone (HAZ) of base materials typically susceptible to high stresses and potential degradation.
Duke Energy's Response RAI 2.2.2: The examination utilizes the best-effort ultrasonic techniques for the upper 2/3 of component volume. The procedure uses ultrasonic techniques identified in EPRI Report TR-107481, "Status of the Ultrasonic Examination of Reactor Coolant Loop Cast Stainless Materials." This procedure is a demonstrated procedure as opposed to an ASME Section XI, Appendix VIII qualified procedure.
Note: Refer to NRC Staff Evaluation (Accession Number ML 13365A023) regarding approved Relief Request 12-0N-001 and 002 addressing this weld on other pumps. RAI Response re: 15-0N-002
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Enclosure:
Response to Request For Additional Information RA/ Question 2.2.3 UT Performance Qualification and Demonstration:
Section 6.4of15-0N-002 states that this component was scanned manually with conventional methods, and that the scanning requirements are described in 10 CFR 50.55a(b)(2)(xv)(A)(1). (a) Discuss whether the UT used was qualified and demonstrated; and (b) If Appendix VIII was used for the UT performance qualification and demonstration, provided the supplement number. Duke Energy's Response RAI 2.2.3: (a) The procedure utilized from the Safe-End surface is an ASME Section XI Appendix VIII qualified procedure.
The procedure utilized from the pump nozzle surface is a demonstrated procedure. (b) The examination from the Safe-End surface is qualified under ASME Section XI Appendix VIII Supplement
- 2. The techniques applied to the Safe-End surface have been qualified through the industry's Performance Demonstration Initiative (POI), which meet ASME Code Section XI, Appendix VIII requirements for flaws located on the near-side of the welds; far-side detection of flaws is considered to be a "best-effort." No ASME Code,Section XI, Appendix VIII requirements currently exist for qualification of ultrasonic examination procedures through cast austenitic materials.
2.3 Editorial Discrepancies Noted in Requests for Relief 15-0N-002 and 15-0N-003 RA/ Question 2.3.1 Weld #s 1-LDCB-INLET and 1-LDCB-OUTLET:
In Sections 4.4 and 5.4of15-0N-002, the diameter of the Letdown Cooler circumferential head welds are listed as 8. 75 inches. On page 16 and 29 of Attachment A, the diameters are listed as 8.625 inches. Please clarify the correct diameter.
Duke Energy's Response RAI 2.3.1: The diameter listed in Sections 4.4 and 5.4 of 15-0N-002 is the outside diameter which is 8. 75 inch. The diameter listed on page 16 and 29 of Attachment A of 15-0N-002 is the inside diameter which 'is 8.625 inch. The Limitation calculation was performed using the inside diameter of 8.625 inch. The inside diameter is the correct value to be applied to the calculation for limitations.
RA/ Question 2.3.2 Weld #s 1-LDCB-INLET, 1-LDCB-OUTLET, 3-LDCA-IN-1, and 3-LDCA-OUT-WJ35V:
In Sections 4.4 and 5.4 of 15-0N-002 and Sections 5.4 and 6.4 of 15-0N-003, the impracticality section states that in order to scan all of the required volume for these welds, the "shell-to-sampling nozzle" weld would have to be redesigned and replaced.
Please clarify whether the correct statement should be the "channel body-to-chemical connector nozzle" weld. Duke Energy's Response RAI 2.3.2: The statement should refer to the channel body-to-chemical connector nozzle weld. RAI Response re: 15-0N-002
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Enclosure:
Response to Request For Additional Information RA/ Question 2.3.3 Weld# 2-LDCB-OUT-WJ36V:
In Section 15.4 of 15-0N-002, the impracticality section states that the configuration of the "inlet nozzle to the channel body" does not allow interrogation from Surface 2. Please clarify whether the correct statement should be the "outlet nozzle to the channel body. " Duke Energy's Response RAI 2.3.3: The statement should refer to the outlet nozzle to the channel body. RA/ Question 2.3.4 Weld# 2-SGB-W69:
In Section 16.4of15-0N-002, the component materials are identified as being carbon steel. However, Section 16. 5 of 15-0N-002 states that the coverage limitation is "created by the component cast stainless material':
Please clarify and correct as needed. Duke Energy's Response RAI 2.3.4: The component materials are carbon steel ASME SA-508 CL. The statement in Section 16.5 "component cast stainless material" should be changed to "various obstructions from the restraints, trunnions and manway components." RAI Response re: 15-0N-002
&003 Page 5 ENERGY 0NS-2016-050 June 1, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Duke Energy Carolinas, LLC (Duke Energy) Oconee Nuclear Station, Units 1, 2 and 3 Docket Numbers 50-269, 50-270, 50-287 Renewed License Numbers DPR-38, DPR-47, and DPR-55 Scott L. Batson Vice President Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.327 4 F. 864.873. 4208 Scott. Batson@duke-energy.com 10 CFR 50.55a
Subject:
Response to Request for Additional Information (RAI) for Oconee Relief Requests 15-0N-002
& 003, Limited.Volume Inspections from 1EOC27, 2EOC26 and 3EOC27 Pursuant to 10 CFR 50.55a(g)(5)(iii), Duke Energy submitted Relief Requests 15-0N-002 and 15-0N-003 on July 15, 2015, requesting that the NRC grant relief from the American Society of. Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) with respect to Limited Volume inspections due to the impracticality of inspecting the required volume in the fourth 10-year inservice inspection (ISi) interval.
The NRC submitted a Draft Request for Additional Information (RAI) via email dated February 22, 2016 regarding this Relief Request. Duke Energy determined no clarifications were needed to the draft RAI questions and thus is submitting answers to those RAI questions as an enclosure to this letter. There are no regulatory commitments associated with this letter. If there are any questions, or further information is needed, you *may contact David Haile in Regulatory Affairs at (864) 873-4742.
Sincerely, Scott L. Batson Vice President Oconee Nuclear Station
Enclosure:
Oconee Nuclear Station Unit 1, 2 and 3, Response to Request for Additional Information (RAI), regarding Relief Requests 15-0N-002
& 003 for Limited Volume Inspections.
ONS-2016-050 June 1, 2016 Page 2 cc: Ms. Catherine Haney Administrator Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. James R. Hall, Project Manager (ONS) (by electronic mail only) U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-881 Rockville, MD 20852 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station ONS-2016-050
Enclosure:
Response to Request For Additional Information Enclosure Oconee Nuclear Station Unit 1, 2 and 3, Response to Request for Additional Information (RAI), regarding Relief Requests 15-0N-002
& 003 for Limited Volume Inspections.
RAI Response re: 15-0N-002
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Enclosure:
Response to Request For Additional Information
- 1. SCOPE (from NRC's RA/ document)
By two separate letters dated July 15, 2015 (ML 15202A032
& ML 15202A052), the licensee, Duke Energy Carolinas, LLC (Duke Energy), submitted Requests for Relief 15-0N-002 and 003 from requirements of the ASME Boiler and Pressure Vessel Code (Code),Section XI, Rules for lnservice Inspection of Nuclear Power Plant Components for ONS 1, 2, and 3. These requests for relief apply to the fourth 10-year inservice inspection interval, in which ONS 1, 2, and 3 adopted the 1998 Edition through the 2000 Addenda of ASME Code,Section XI. In accordance with 10 CFR 50.55a(g)(5)(iii), the licensee has submitted the subject requests for relief for limited examinations in multiple ASME Code Examination Categories.
The ASME Code requires that 100 percent of the examination volumes described in Tables IWB-2500 and IWC-2500 be performed during each interval.
The licensee stated that 100 percent of the ASME Code-required volumes are impractical to obtain at ONS 1, 2 and 3. 1 O CFR 50.55a(g)(5)(iii) states that when licensees determine that conformance with ASME Code requirements is impractical at their facility, they shall submit information to support this determination.
The U.S. Nuclear Regulatory Commission (NRC) will evaluate such requests based on impracticality, and may impose alternatives, giving due consideration to public safety and the burden imposed on the licensee.
NRC staff has reviewed the information submitted by the licensee, and based on this review, determined the following additional information or clarification is required to complete the technical evaluation.
- 2. REQUEST FOR ADDITIONAL INFORMATION 2.1 Requests for Relief 15-0N-002 and 15-0N-003, Examination Category B-A, Item 81.21, Pressure Retaining Welds in Reactor Vessel RA/ Question 2.1.1 The ASME Code states that essentially 100% of the "accessible length" of circumferential head welds must be examined.
The licensee stated that approximately 36 percent of the ASME-required volumetric coverage could be obtained on reactor pressure vessel (RPV) transition piece-to-lower head Welds 1-RPV-WR35, 2-RPV-WR35, and 3-RPV-WR35, on ONS 1, 2 and 3, respectively.
Schematics have been provided of the RPV lower lower head area depicting examination limitations caused by the incore instrumentation nozzles and flow stabilizers.
However, it is difficult to determine from the submitted drawings whether the 36 percent obtained is related to the entire weld length, or applies to only the ASME Code "accessible length" of the weld. Please state the accessible length of each of the RPV circumferential head welds, and clarify whether the 36% volumetric coverage obtained is applicable to the accessible length, or to the entire length of the weld. If applicable to the entire length, and the licensee has completed 100% of the accessible length, relief may not be required.
Duke Energy's Response RAI 2.1.1: The 36% coverage obtained is applicable to the entire length of the weld. The entire length of each weld was 449.25 inches and the obstruction length was 242.97 inches, leaving 206.28 inch of accessible weld length. The percentage coverage based on accessible length for these welds is also below the 90% minimum required.
RAI Response re: 15-0N-002
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Enclosure:
Response to Request For Additional Information 2.2 Requests for Relief 15-0N-002, Examination Category B-J, Item 89.11, Pressure Retaining Welds in Piping RA/ Question 2.2.1 Configuration of Weld# 1-PDA 1-1: Section 6.4of15-0N-002 describes the configuration of the components joined by weld# 1-PDA 1-1. This weld joint includes a stainless steel safe end, but the licensee request does not provide any detail on components adjacent to the safe end which might affect the inspectability of the component.
Please clarify the following: (a) Clarify whether the safe end is welded to adjacent components such as pipe or elbow, and whether the ultrasonic beam will pass through the safe end, adjacent weld, and adjacent component (e.g., pipe or elbow) during inspection of the weld for which relief is requested; and (b) If the ultrasonic beam will pass through adjacent weld and components, identify the materials for the adjacent weld and components, and provide the distance between these components and weld # 1-PDA 1-1. Duke Energy's Response RAI 2.2.1: (a) The safe-end is about 2 feet long. On one end, weld 1-PDA1-1 attaches the safe-end to the Reactor Coolant Pump nozzle and on the other end a separate weld attaches the safe-end to an elbow. The weld to the "adjacent component" does not interfere with the inspection of weld 1-PDA 1-1. (b) The ultrasonic beam only passes through the stainless steel base material (Mat. Spec. A376 Type 316) during the safe-end side of the examination.
RA/ Question 2.2.2 Examination Coverage of Weld # 1-PDA 1-1: Section 6. 4 of 15-0N-002 describes the examination coverage of the component, which is reduced because the cast stainless steel material does not allow meaningful interrogation from the RCP-1A 1 side. Please clarify whether the licensee's best effort ultrasonic examination coverage included the weld root and heat affected zone (HAZ) of base materials typically susceptible to high stresses and potential degradation.
Duke Energy's Response RAI 2.2.2: The examination utilizes the best-effort ultrasonic techniques for the upper 2/3 of component volume. The procedure uses ultrasonic techniques identified in EPRI Report TR-107481, "Status of the Ultrasonic Examination of Reactor Coolant Loop Cast Stainless Materials." This procedure is a demonstrated procedure as opposed to an ASME Section XI, Appendix VIII qualified procedure.
Note: Refer to NRC Staff Evaluation (Accession Number ML 13365A023) regarding approved Relief Request 12-0N-001 and 002 addressing this weld on other pumps. RAI Response re: 15-0N-002
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Enclosure:
Response to Request For Additional Information RA/ Question 2.2.3 UT Performance Qualification and Demonstration:
Section 6.4of15-0N-002 states that this component was scanned manually with conventional methods, and that the scanning requirements are described in 10 CFR 50.55a(b)(2)(xv)(A)(1). (a) Discuss whether the UT used was qualified and demonstrated; and (b) If Appendix VIII was used for the UT performance qualification and demonstration, provided the supplement number. Duke Energy's Response RAI 2.2.3: (a) The procedure utilized from the Safe-End surface is an ASME Section XI Appendix VIII qualified procedure.
The procedure utilized from the pump nozzle surface is a demonstrated procedure. (b) The examination from the Safe-End surface is qualified under ASME Section XI Appendix VIII Supplement
- 2. The techniques applied to the Safe-End surface have been qualified through the industry's Performance Demonstration Initiative (POI), which meet ASME Code Section XI, Appendix VIII requirements for flaws located on the near-side of the welds; far-side detection of flaws is considered to be a "best-effort." No ASME Code,Section XI, Appendix VIII requirements currently exist for qualification of ultrasonic examination procedures through cast austenitic materials.
2.3 Editorial Discrepancies Noted in Requests for Relief 15-0N-002 and 15-0N-003 RA/ Question 2.3.1 Weld #s 1-LDCB-INLET and 1-LDCB-OUTLET:
In Sections 4.4 and 5.4of15-0N-002, the diameter of the Letdown Cooler circumferential head welds are listed as 8. 75 inches. On page 16 and 29 of Attachment A, the diameters are listed as 8.625 inches. Please clarify the correct diameter.
Duke Energy's Response RAI 2.3.1: The diameter listed in Sections 4.4 and 5.4 of 15-0N-002 is the outside diameter which is 8. 75 inch. The diameter listed on page 16 and 29 of Attachment A of 15-0N-002 is the inside diameter which 'is 8.625 inch. The Limitation calculation was performed using the inside diameter of 8.625 inch. The inside diameter is the correct value to be applied to the calculation for limitations.
RA/ Question 2.3.2 Weld #s 1-LDCB-INLET, 1-LDCB-OUTLET, 3-LDCA-IN-1, and 3-LDCA-OUT-WJ35V:
In Sections 4.4 and 5.4 of 15-0N-002 and Sections 5.4 and 6.4 of 15-0N-003, the impracticality section states that in order to scan all of the required volume for these welds, the "shell-to-sampling nozzle" weld would have to be redesigned and replaced.
Please clarify whether the correct statement should be the "channel body-to-chemical connector nozzle" weld. Duke Energy's Response RAI 2.3.2: The statement should refer to the channel body-to-chemical connector nozzle weld. RAI Response re: 15-0N-002
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Enclosure:
Response to Request For Additional Information RA/ Question 2.3.3 Weld# 2-LDCB-OUT-WJ36V:
In Section 15.4 of 15-0N-002, the impracticality section states that the configuration of the "inlet nozzle to the channel body" does not allow interrogation from Surface 2. Please clarify whether the correct statement should be the "outlet nozzle to the channel body. " Duke Energy's Response RAI 2.3.3: The statement should refer to the outlet nozzle to the channel body. RA/ Question 2.3.4 Weld# 2-SGB-W69:
In Section 16.4of15-0N-002, the component materials are identified as being carbon steel. However, Section 16. 5 of 15-0N-002 states that the coverage limitation is "created by the component cast stainless material':
Please clarify and correct as needed. Duke Energy's Response RAI 2.3.4: The component materials are carbon steel ASME SA-508 CL. The statement in Section 16.5 "component cast stainless material" should be changed to "various obstructions from the restraints, trunnions and manway components." RAI Response re: 15-0N-002
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