Letter Sequence Response to RAI |
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CAC:MF8439, Revise Topical Report References in ITS 5.6.5, Colr (Approved, Closed) |
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MONTHYEARRA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P2016-10-0303 October 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P Project stage: Supplement ML16312A3882016-11-0707 November 2016 NRR E-mail Capture - Harris and Robinson - Accepted for Review of License Amendment Request Project stage: Approval 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 Project stage: Response to RAI 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 Project stage: Response to RAI RA-17-0012, Withholding of Proprietary Information in DPC-NE-3008 - Request for Additional Information (RAI)2017-03-0808 March 2017 Withholding of Proprietary Information in DPC-NE-3008 - Request for Additional Information (RAI) Project stage: Request ML17079A5372017-03-24024 March 2017 Request for Withholding of Proprietary Information from Public Disclosure Project stage: Withholding Request Acceptance RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)2017-08-15015 August 2017 Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) Project stage: Request 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 Project stage: Response to RAI 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) Project stage: Response to RAI 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 Project stage: Request ML17332A4642017-12-21021 December 2017 Request for Withholding of Proprietary Information from Public Disclosure for Shearon Harris Nuclear Power Plant, Unit 1, and H. B. Robinson Steam Electric Plant Unit No. 2 Project stage: Withholding Request Acceptance ML18075A2622018-03-26026 March 2018 Transmittal of Draft SE for Proposed Amendment Methodology Reports DPC-NE-3008-P, Rev. 0, Thermal-Hydraulic Models for Transient Analysis, and DPC-NE-3009-P, Rev. 0, Fsar/Ufsar Ch. 15 Transient Analysis Methodology Project stage: Draft Approval ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) Project stage: Approval 2017-12-19
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Category:Letter type:RA
MONTHYEARRA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-24-0006, 10 CFR 50.54(q) Evaluation2024-01-0404 January 2024 10 CFR 50.54(q) Evaluation RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2023-09-21021 September 2023 Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0195, Notice of Intentions Regarding Apparent Violation Response; (EA-23-060)2023-07-20020 July 2023 Notice of Intentions Regarding Apparent Violation Response; (EA-23-060) 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-23-0136, 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-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0120, Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.22023-05-31031 May 2023 Supplemental Information Regarding Addition of Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0064, Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval2023-04-24024 April 2023 Inservice Testing Program Plan and Snubber Program Plan for Sixth 10-Year Inservice Testing (1ST) Program Interval RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0098, Annual Environmental (Nonradiological) Operating Report2023-04-19019 April 2023 Annual Environmental (Nonradiological) Operating Report RA-23-0080, Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube2023-04-0505 April 2023 Refueling Outage 32 Steam Generator Tube Inspection Report Supplement Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube RA-23-0043, Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations2023-03-30030 March 2023 Refuel 33 (R2R33) Inservice Inspection Program Ninety Day Owner'S Activity Report and Analytical Evaluations RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0055, Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 22023-03-24024 March 2023 Notice of Intent to Pursue Subsequent License Renewal for H. B. Robinson Steam Electric Plant, Unit Number 2 RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements 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-22-0081, License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications2023-02-0707 February 2023 License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-23-0029, Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2023-01-30030 January 2023 Technical Specifications Section 5.6.6 Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-23-0027, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 20222023-01-30030 January 2023 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report for 2022 RA-23-0011, End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report2023-01-26026 January 2023 End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0347, Transmittal of Core Operating Limits Report2022-12-0202 December 2022 Transmittal of Core Operating Limits Report RA-22-0314, Notification of Source Water Resiliency and Response Plan Submission2022-11-0202 November 2022 Notification of Source Water Resiliency and Response Plan Submission RA-22-0302, Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range)2022-11-0101 November 2022 Technical Specifications (TS) Section 5.6.6, Post Accident Monitoring Instrumentation Report for Inoperable Containment Sump Water Level (Wide Range) RA-22-0297, Cycle 25 Core Operating Limits Report, Revisions 0 and 12022-10-17017 October 2022 Cycle 25 Core Operating Limits Report, Revisions 0 and 1 RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. 2024-02-05
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific 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-23-0015, 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-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative 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-21-0203, Response to Request for Additional Information Regarding License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-07-15015 July 2021 Response to Request for Additional Information Regarding License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications 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-21-0067, Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval2021-02-25025 February 2021 Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval 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-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in .2020-11-24024 November 2020 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . RA-20-0321, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Comple2020-11-11011 November 2020 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completi RA-20-0287, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protectiv2020-10-0202 October 2020 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective 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-19-0453, Response to Request for Additional Information Regarding License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-12-20020 December 2019 Response to Request for Additional Information Regarding License Amendment Request to Modify Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type 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-19-0316, Response to Request for Additional Information Regarding License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from TS2019-09-0303 September 2019 Response to Request for Additional Information Regarding License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from TS 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-19-0153, 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 ..2019-04-23023 April 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 .. 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-18-0261, Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints2018-12-27027 December 2018 Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints RA-18-0248, Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change2018-12-17017 December 2018 Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change 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-18-0193, 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 .. 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-18-0175, 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.2018-10-18018 October 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 (Sscs) for Nuclear Power Reactors. RA-18-0171, Supplemental Information for License Amendment Request Regarding Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints2018-09-24024 September 2018 Supplemental Information for License Amendment Request Regarding Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints RA-18-0106, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information Response2018-09-19019 September 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement and Request for Additional Information Response 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 ... HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses 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 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements 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) HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements 2023-07-07
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KELVIN HENDERSON Senior Vice President Nuclear Corporate 526 South Church Street, EC-07H Charlotte, NC 28202 980-373-1295 Kelvin.Henderson@duke
-energy.com
PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ATTACHMENT 3 THIS LETTER IS UNCONTROLLED PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ATTACHMENT 3 THIS LETTER IS UNCONTROLLED Serial: RA-16-0042 10 CFR 50.90 November 1 7, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
-0001 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50
-400 / RENEWED LICENSE NO. NPF
-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50
-261 / RENEWED LICENSE NO.
DPR-23
SUBJECT:
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING APPLICATION TO REVISE TECHNICAL SPECIFICATIONS FOR METHODOLOGY REPORTS DPC-NF-2010, REVISION 3 AND DPC
-NE-2011-P , REVISION 2
REFERENCES:
- 1. Duke Energy letter, Application to Revise Technical Specifications for Methodology Report DPC
-NE-1008-P Revision 0, "Nuclear Design Methodology Using CASMO
-5/SIMULATE
-3 for Westinghouse Reactors
," dated August 19, 2015 (ADAMS Accession No. ML15236A044) 2. Duke Energy letter, Supplemental Information for License Amendment Request Regarding Methodology Report DPC
-NE-1 008-P, dated May 4, 2016 (ADAMS Accession No. ML16125A420) 3. NRC letter , Request for Additional Information Regarding Application to Adopt DPC
-NF-2010, Revision 3 , "Nuclear Physics Methodology for Reload Design," and DPC-NE-2011-P, Revision 2, "Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors" (CAC Nos. MF7693 and MF7694), dated October 26, 2016 (ADAMS Accession No.
ML16288A078) Ladies and Gentlemen:
In Reference 1, Duke Energy Progress, LLC (formerly referred to as Duke Energy Progress, Inc.), referred to henceforth as "Duke Energy," submitted a request for an amendment to the Technical Specifications (TS) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP) and H. B. Robinson Steam Electric Plant, Unit No. 2 (RNP). In Reference 2, Duke Energy submitted a supplement to the amendment request that superseded Reference 1 in its entirety. In Reference 2, Duke Energy requested, in part, NRC review and approval of DPC-NF-2010 ,
PROPRI ETA RY I NFO R MATIO N -W IT HH O LD UNDER 10 CFR 2.390 U PON RE M O VA L OF ATIAC H ME NT 3 TH IS LETIE R IS U N CO NTR OLL E D U.S. Nuclear Regulatory Commission RA-16-0042 Page2 Revision 3, Physics Methodology for Reload and DPC-NE-2011-P, Revision 2, "Nuclear Design Methodology Report for Core Operating Limits of Westinghouse Reactors*
and adoption of these two methodologies into the TS for HNP and RNP. In Reference 3, the NRC requested additional information (RAI) regarding DPC-NF-2010 and DPC-NE-2011-P.
Attachment 3 provides Duke Energy's response to the Reference 3 RAl's. Attachment 3 contains Information that is proprietary to Duke Energy. In accordance with 10 CFR 2.390, Duke Energy requests that Attachment 3 be withheld from public disclosure.
An affidavit Is Included (Attachment
- 1) attesting to the proprietary nature of Attachment
- 3. A non-proprietary version of Attachment 3 Is Included in Attachment
- 2. This submittal contains no new regulatory commitments.
In accordance with 1 O CFR 50.91, Duke Energy is notifying the states of North Caronna and South Carolina by transmitting a copy of this letter to the designated state officials.
Should you have any questions concerning this letter, or require additional Information, please contact Art Zaremba, Manager -Nuclear Fleet Licensing , at 980-373-2062. I declare under penalty of perjury that the foregoing is true and correct. Executed on November 17, 2016. Kelvin Henderson Senior Vice President
-Nuclear Corporate JBO Attachments
- 1. Affidavit of Kelvin Henderson
- 2. Response to NRC Request for Additional Information (Redacted)
- 3. Response to NRC Request for Additional Information (Proprietary)
PROPRIETARY INFORMATION
-WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ATIACHMENT 3 THIS LETIER IS UNCONTROLLED PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ATTACHMENT 3 THIS LETTER IS UNCONTROLLED U.S. Nuclear Regulatory Commission RA-16-0042 Page 3 PROPRIETARY INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ATTACHMENT 3 THIS LETTER IS UNCONTROLLED cc: (all with Attachments unless otherwise noted)
C. Haney, Regional Administrator USNRC Region II M. Riches, USNRC Senior Resident Inspector - HNP J. Zeiler, USNRC Senior Resident Inspector - RNP M. C. Barillas, NRR Project Manager - HNP D. J. Galvin, NRR Project Manager - RNP W. L. Cox, III, Section Chief, NC DHSR (Without Attachment 3) S. E. Jenkins, Manager, Radioactive and Infectious Waste Management Section (SC)
(Without Attachment 3) A. Wilson, Attorney General (SC)
(Without Attachment 3) A. Gantt, Chief, Bureau of Radiological Health (SC) (Without Attachment 3) RA-16-0042
Attachment 1 Affidavit of Kelvin Henderson RA-16-0042 Page 1 of 3 AFFIDAVIT of Kelvin Henderson
- 1. I am Senior Vice President of Nuclear Corporate, Duke Energy Corporation, and as such have the responsibility of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear plant licensing and am authorized to apply for its withholding on behalf of Duke Energy.
- 2. I am making this affidavit in conformance with the provisions of 10 CFR 2.390 of the regulations of the Nuclear Regulatory Commission (NRC) and in conjunction with Duke Energy's application for withholding which accompanies this affidavit.
- 3. I have knowledge of the criteria used by Duke Energy in designating information as proprietary or confidential. I am familiar with the Duke Energy information contained in Attachment 3 to Duke Energy RAI response letter RA-16-0042 regarding application to revise technical specifications for reports DPC-NF-2010 and DPC
-NE-2011-P.
- 4. Pursuant to the provisions of paragraph (b) (4) of 10 CFR 2.390, the following is furnished for consideration by the NRC in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is owned by Duke Energy and has been held in confidence by Duke Energy and its consultants.
(ii) The information is of a type that would customarily be held in confidence by Duke Energy. Information is held in confidence if it falls in one or more of the following categories.
(a) The information requested to be withheld reveals distinguishing aspects of a process (or component, structure, tool, method, etc.) whose use by a vendor or consultant, without a license from Duke Energy, would constitute a competitive economic advantage to that vendor or consultant.
(b) The information requested to be withheld consist of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), and the application of the data secures a competitive economic advantage for example by requiring the vendor or consultant to perform test measurements, and process and analyze the measured test data.
(c) Use by a competitor of the information requested to be withheld would reduce the competitor's expenditure of resources, or improve its competitive position, in the design, manufacture, shipment, installation assurance of quality or licensing of a similar product.
(d) The information requested to be withheld reveals cost or price information, production capacities, budget levels or commercial strategies of Duke Energy or its customers or suppliers.
RA-16-0042 Page 2 of 3 (e) The information requested to be withheld reveals aspects of the Duke Energy funded (either wholly or as part of a consortium ) development plans or programs of commercial value to Duke Energy.
(f) The information requested to be withheld consists of patentable ideas.
The information in this submittal is held in confidence for the reasons set forth in paragraphs 4(ii)(a) and 4(ii)(c) above. Rationale for this declaration is the use of this information by Duke Energy provides a competitive advantage to Duke Energy over vendors and consultants, its public disclosure would diminish the information's marketability, and its use by a vendor or consultant would reduce their expenses to duplicate similar information. The information consists of analysis methodology details, analysis results, supporting data, and aspects of development programs, relative to a method of analysis that provides a competitive advantage to Duke Energy.
(iii) The information was transmitted to the NRC in confidence and under the provisions of 10 CFR 2.390, it is to be received in confidence by the NRC.
(iv) The information sought to be protected is not available in public to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld is that which is marked in to Duke Energy RAI response letter RA 0042 regarding application to revise technical specifications for reports DPC
-NF-2010 and DPC
-NE-2011-P. This information enables Duke Energy to:
(a) Support license amendment requests for its Harris and Robinson reactors.
(b) Support reload design calculations for Harris and Robinson reactor cores.
(vi) The proprietary information sought to be withheld from public disclosure has substantial commercial value to Duke Energy.
(a) Duke Energy uses this information to reduce vendor and consultant expenses associated with supporting the operation and licensing of nuclear power plants. (b) Duke Energy can sell the information to nuclear utilities, vendors, and consultants for the purpose of supporting the operation and licensing of nuclear power plants.
(c) The subject information could only be duplicated by competitors at similar expense to that incurred by Duke Energy.
- 5. Public disclosure of this information is likely to cause harm to Duke Energy because it would allow competitors in the nuclear industry to benefit from the results of a significant development program without requiring a commensurate expense or allowing Duke Energy to recoup a portion of its expenditures or benefit from the sale of the information.
Attachment 1 RA-16-0042 Page 3of 3 Kelvin Henderson affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
I declare under penalty of perjlM)' that the foregoing is true and correct. Executed on November 17, 2016. RA-16-0042
Attachment 2 Response to NRC Request for Additional Information (Redacted)
Note: Text that is within double brackets (original NRC RAI wording) or brackets with an "a,c" superscript (Duke Energy response) is proprietary to Duke Energy and has been removed.
Attachment 2 RA-16-0042 Page 1 of 5 NRC RAI 1 In DPC-NF-2010 Rev. 3, Duke Energy indicates that the hot zero power (HZP) and hot full power (HFP) isothermal temperature coefficient (ITC) and moderator temperature coefficient (MTC) are used to support startup and operation.
The report also states that the ITC may be used to determine the MTC. The MTC is governed by limiting condition for operation (LCO) 3.1.1.3 in the HNP TSs and LCO 3.1.3 in the RNP TSs. Section 10.4.1 of Revision 3 of the DPC-NF-2010 methodology, as proposed in the LAR, added a new means of measuring the ITC. Please clarify how the new method of ITC measurement in Revision 3 differs from the method in Revision 2 of the report.
Duke Energy RAI 1 Response There are two generally industry accepted methods for performing an ITC measurement during startup testing following a refueling outage. The first method is referred to as the "slope method", and the second method is referred to as the "end
-point method".
Both methods require the reactor to be stable at hot zero power conditions prior to the start of the test. Stable is implied to mean that primary and secondary system parameters are constant (to the extent possible) such that the initial core reactivity is zero or nearly zero. The slope method is the measurement method used at McGuire and Catawba to measure the ITC. It is also the method described in Revision 2 of DPC
-NF-2010. The measurement is started by initiation of a controlled reactor coolant system (RCS) cooldown. During the RCS cooldown, both core reactivity and temperature are measured with the reactivity computer, and a reactivity versus RCS temperature derivative is continuously calculated. This calculation is performed until a specified minimum temperature change has occurred and the standard error of the reactivity versus temperature derivative is converged. This derivative, or slope, is the measured ITC. Next, a RCS heat
-up is initiated and the measurement process is repeated. The slope of the cooldown and heat
-up values are averaged to obtain the measured ITC. The "end
-point" method (added in Revision 3 of DPC
-NF-2010 to reflect the measurement method currently used at HNP and RNP) is similar to the "slope method" in that both a cooldown and heat
-up of the RCS is performed. This method differs from the "slope method" in that the ITC is determined using the total reactivity change divided by the temperature change for each portion of the test. The cooldown and heat
-up values are similarly averaged to obtain the measured ITC. In both methods, the MTC is calculated by subtracting the predicted Doppler temperature coefficient from the measured ITC.
Attachment 2 RA-16-0042 Page 2 of 5 NRC RAI 2 Axial flux difference (AFD), which is a measure of how much power is generated in the top of the core versus the bottom of the core, is a key core power distribution parameter. AFD is controlled in LCO 3.2.1 in the HNP TSs and LCO 3.2.3 in the RNP TSs. One of the primary changes requested in DPC
-NE-2011, Revision 2, is a change in the way abnormal xenon distributions are generated in order to define abnormal power shapes and set the AFD operational space provided in the plants' TSs. The proposed language clarifies that control rods are only to be inserted at most to the control rod insertion limit. Though this modification appears to make DPC
-NE-2011 more consistent to existing approved industry methodologies, the justification provided for the proposed Change 2
-3 in the LAR raised several questions about the modifications to the process and whether the AFD limits would be appropriately defined. a. Please clarify how Duke Energy will ensure that the full AFD operational space is covered by abnormal xenon transients (and thus, abnormal power distributions) over the full range of powers and the length of the cycle. Explain how appropriate coverage of the operating space allowed by the TSs is assured. Describe if there are a variety of xenon transients initiated from a variety of initial conditions.
- b. Part of Duke Energy's justification for the proposed change in the generation of abnormal xenon distributions is that [[
]] This is illustrated in Figure 1 of the justification of Change 2-3 in the LAR. However, Figure 2 seems to contradict this justification. [
[
]] Please explain how a change to the method that is intended to [[
]] only [[
]]. c. To justify the operational AFD limits, the analyzed operational space should be slightly wider than the final limits. Please describe how far beyond the limits is the analyzed operational space. Describe if the abnormal xenon distributions include an allowance for the time allowed to be outside of the rod insertion and AFD limits by the TSs.
Attachment 2 RA-16-0042 Page 3 of 5 Duke Energy RAI 2.a Response The design xenon transients are selected based on experience to create power distributions that are wider than the operational AFD limits allowed by Technical Specifications. Xenon transients are performed at different times during core life to produce both top and bottom peaked power distributions. [
]a,c Xenon distributions from each xenon transient are evaluated and combined with control rod positions that span the ARO condition to the Technical Specification rod insertion limits to produce the power distributions which are evaluated against thermal limits. Results from the thermal limits calculation are used to establish the Technical Specification AFD limits. Maneuvering Analysis power distribution calculations are performed for each reload core design. As previously noted, the design xenon transients were selected to create power distributions that are wider than the Technical Specification AFD limits. For example, the combination of xenon and control rod positions (as constrained by rod insertion limits) used to generate Figure 2 in the technical justification for change 2
-3 [
]a,c Duke Energy RAI 2.b Response The power peaking that occurs during transient xenon conditions is based on both the radial and axial xenon concentration. The xenon transient induced from a [
Attachment 2 RA-16-0042 Page 4 of 5
]a,c The benefit of the proposed change is realized when Technical Specification AFD limits are established in the range of AFD's where the proposed change provides increased Fq margin. In the example given (Figure 2 for change 2
-3), [
]a,c 1.41.51.61.71.81.9 22.12.22.32.42.5-35-30-25-20-15-10-5 0 5 10 15 20 25 30 35 FqAxial Flux Difference (%)Figure AFq Dependency on Xenon and Rod Position225 SWD, Xe Trans. Based on Ctl D at 117 SWD225 SWD, Xe Trans. Based on Ctl D at 153 SWD185 SWD, Xe Trans. Based on Ctl D at 117 SWD185 SWD, Xe Trans. Based on Ctl D at 153 SWDSolid lines represent xenon conditions developed with control rods initially positioned at 117 SWD.Dashed lines represent xenon conditions developed with control rods initially positioned at 153 SWD.a,c Attachment 2 RA-16-0042 Page 5 of 5 Duke Energy RAI 2.c Response The AFD space analyzed in the Maneuvering Analysis is discussed in the response to question 2a. As discussed in this response, design xenon transients are selected to create power distributions that are wider than the operational AFD limits allowed by Technical Specifications.
[
]a,c The xenon distributions generated in the Maneuvering Analysis [
]a,c is also included in the control rod positions considered in the generation of the core power distributions used to establish Technical Specification operating AFD limits. The power distributions generated to establish AFD limits consist of combinations of control rod positions that span the rod insertion limits, and xenon distributions that span the time [
]a,c [
]a,c