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| document type = Letter, Report, Technical, Response to Request for Additional Information (RAI) | | document type = Letter, Report, Technical, Response to Request for Additional Information (RAI) | ||
| page count = 25 | | page count = 25 | ||
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Revision as of 18:52, 26 February 2018
| ML16258A343 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/14/2016 |
| From: | Glover R M Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RNP-RA/16-0073 MCOE-LTR-16-33, Rev.0 | |
| Download: ML16258A343 (25) | |
Similar Documents at Robinson | |
|---|---|
Category:Letter
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Robinson Steam Electric Plant, Unit No. 2, References 9-1 Through E-6 RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 5042003-04-28028 April 2003 Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504 ML0311207052003-04-18018 April 2003 Review of 90-day Steam Generator Tube Inservice Inspection Report for a Refueling Outage in 2001 ML0305202692003-02-15015 February 2003 Follow-up Report, Reference Event #39516 RNP-RA/03-0012, Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent2003-02-11011 February 2003 Request for Relief Pertaining to Examination Coverage Less than Essentially 100 Percent RNP-RA/02-0172, Steam Generator Tube Plugging During Refueling Outage 212002-11-11011 November 2002 Steam Generator Tube Plugging During Refueling Outage 21 RNP-RA/02-0164, Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License2002-11-0606 November 2002 Part 17 of 17, CD-ROM Providing the Review Tool Supporting the Application for Renewal of Operating License ML0230402682002-09-19019 September 2002 Part 4 of 4 - Westinghouse Technology Manual, Course Outline for R-104P and Course Manual ML0221103432002-01-31031 January 2002 Caldon, Inc Engineering Report: ER-267N, Bounding Uncertainty Analysis for Thermal Power Determination at CP&L Robinson Nuclear Power Station Using the LEFM Check Plus System ML18288A3691990-10-31031 October 1990 ANF-88-054(NP)(A), PDC-3: Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2. NRC Generic Letter 1979-451979-09-25025 September 1979 NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation Experiences 2023-07-12 Category:Response to Request for Additional Information (RAI) MONTHYEARRA-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
[Table view]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-23-0015, Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-02-0909 February 2023 Response to Request for Additional Information (RAI) Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-22-0245, Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.162022-09-0808 September 2022 Response to Request for Additional Information (RAI) Regarding Removal of 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 RA-22-0210, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-07-28028 July 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0144, Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-022022-05-19019 May 2022 Response to NRC Request for Additional Information Regarding Supplemental Response to Generic Letter 2004-02 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-22-0106, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-04-28028 April 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0230, Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2021-09-30030 September 2021 Duke Energy - Final Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors 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-20-0048, Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections2020-03-0404 March 2020 Response to Request for Additional Information for Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Vessel Cold Leg Dissimilar Metal Weld Inspections RA-20-0018, Supplement to Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding; Integrated Assessment Submittal2020-01-23023 January 2020 Supplement to Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding; Integrated Assessment Submittal RA-19-0460, Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal2019-12-19019 December 2019 Revised Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal RA-19-0452, Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident2019-12-12012 December 2019 Seismic Probabilistic Risk Assessment (Spra), Response to March 12, 2012, Request for Information Regarding Recommendation 2.1: Seismic, of the Near-Term Task Force Related to the Fukushima Dai-ichi Accident RA-19-0421, Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145)2019-11-13013 November 2019 Response to Request for Additional Information (RAI) Regarding Reactor Pressure Vessel (RPV) Surveillance Capsule Removal (RA-19-0145) RA-19-0386, Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.12019-10-24024 October 2019 Response to Request for Additional Information (RAI) Regarding License Amendment Request Proposing to Revise Technical Specification 3.8.2, AC Sources - Shutdown, Surveillance Requirement 3.8.2.1 RA-19-0154, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2019-05-0606 May 2019 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors 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) RA-18-0185, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report2018-12-10010 December 2018 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.46 Annual Report, Including Revised Robinson Large Break Loss of Coolant Accident Report RA-18-0194, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 32018-11-13013 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt TSTF-425, Revision 3 RA-18-0193, Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power ..2018-11-13013 November 2018 Response to NRC Request for Additional Information (RAI) Regarding Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power .. RNP-RA/18-0050, Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change2018-08-0101 August 2018 Response to Supplemental Request for Additional Information Regarding License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Change RA-18-0016, Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2018-06-0505 June 2018 Response to Request for Additional Information Regarding Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses RNP-RA/18-0036, Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ...2018-05-16016 May 2018 Response to Request for Additional Information (RAI) Regarding Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use ... RNP-RA/17-0085, Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2018-01-0808 January 2018 Request for Additional Information Regarding Application to Revise Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RA-17-0055, Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 02017-12-19019 December 2017 Response to Second Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 RA-17-0048, Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2)2017-10-30030 October 2017 Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Rev. 0 (Part 2) RA-17-0043, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 02017-10-0909 October 2017 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3009, Revision 0 RNP-RA/17-0068, Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles2017-09-28028 September 2017 Response to NRC Request for Additional Information Related to License Amendment Request Regarding Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-16-0042, Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed2016-11-17017 November 2016 Response to Request for Additional Information Application to Revise Technical Specifications for Methodology Reports DPC-NF-2010, Revision 3 & DPC-NE-2011-P, Revision 2. Redacted Version Enclosed ML16315A2722016-11-10010 November 2016 Duke Energy Transmittal of Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-3008, Revision 0 RNP-RA/16-0079, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-10-0505 October 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. ML16280A2002016-10-0505 October 2016 Response to Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RA-16-0036, Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 02016-10-0303 October 2016 Regarding Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Methodology Report DPC-NE-1008, Rev 0 RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation RNP-RA/16-0072, Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 22016-09-14014 September 2016 Response to Request for Additional Information Regarding Application for Technical Specification Change to Adopt Technical Specifications Task Force (TSTF)-339, Relocate TS Parameters to the COLR Consistent with WCAP-14483, Rev. 2 RNP-RA/16-0073, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-09-14014 September 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits ML16230A2342016-07-25025 July 2016 Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805 RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations ML16158A0062016-05-25025 May 2016 Response to Request for Additional Information Re License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. Pages 1-21 RNP-RA/16-0038, Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-1742016-05-25025 May 2016 Transition Report, Revision 1, Transition to National Fire Protection Association Standard 805, with Attachments a, I, J, L, M, and V. Pages 22-174 RNP-RA/16-0031, Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-05-0909 May 2016 Supplemental Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits2016-03-31031 March 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Reactor Coolant System Pressure and Temperature Limits RNP-RA/16-0017, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants.2016-03-16016 March 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Light Water Reactor Electric Generating Plants. ML16063A1032016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/16-0011, Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals2016-02-18018 February 2016 Response to NRC Request for Additional Information Related to the Pressurized Water Reactor Internals Program Plan for Aging Management of Reactor Internals RNP-RA/15-0117, Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-12-22022 December 2015 Supplement to Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits 2023-07-07 |
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