Letter Sequence Response to RAI |
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Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release FractionsML16032A011 |
Person / Time |
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Site: |
Oconee, Mcguire, Catawba, McGuire ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
02/01/2016 |
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From: |
Repko R Duke Energy Carolinas |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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RA-16-0006, TAC MF6480, TAC MF6481, TAC MF6482, TAC MF6483, TAC MF6484, TAC MF6485, TAC MF6486 |
Download: ML16032A011 (17) |
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Category:Letter type:RA
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) 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-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024 Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval RA-23-0320, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2023-12-14014 December 2023 Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. 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-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report RA-23-0182, Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency2023-11-16016 November 2023 Duke Energy Carolinas, LLC - License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program for a One-Time Extension of the Units 1, 2 and 3 Type a Leak Rate Test Frequency 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-23-0304, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0)2023-11-14014 November 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 32 (Revision 0) RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power 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-23-0275, 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-23-0268, Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan2023-09-29029 September 2023 Transmittal of Sixth 10-Year Inservice Testing Interval Program Plan RA-23-0234, Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS)2023-09-28028 September 2023 Update to the Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations for Oconee Nuclear Station (ONS) RA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report 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-23-0228, Registration for Use of General License Spent Fuel Cask Number 1752023-09-14014 September 2023 Registration for Use of General License Spent Fuel Cask Number 175 RA-23-0215, Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks2023-08-28028 August 2023 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks RA-23-0222, On-Shift Staffing Analysis (Ossa), Revision 12023-08-23023 August 2023 On-Shift Staffing Analysis (Ossa), Revision 1 RA-23-0223, Registration for Use of General License Spent Fuel Cask Numbers 173 and 1742023-08-23023 August 2023 Registration for Use of General License Spent Fuel Cask Numbers 173 and 174 RA-23-0211, Reply to a Notice of Violation (NOV) 05000270/2023010-022023-08-17017 August 2023 Reply to a Notice of Violation (NOV) 05000270/2023010-02 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-23-0186, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)2023-07-18018 July 2023 Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3) RA-23-0184, Registration for Use of General License Spent Fuel Cask Numbers 171 and 1722023-07-10010 July 2023 Registration for Use of General License Spent Fuel Cask Numbers 171 and 172 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-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record 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-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications 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-23-0041, 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-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report RA-23-0105, Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core2023-05-0404 May 2023 Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core RA-23-0018, Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 12023-05-0404 May 2023 Relief Request (RA-23-0018) to Utilize Code Case N-853 PWR Class 1 Primary Piping Alloy 600 Full Penetration Branch Connection Weld Metal Buildup for Material Susceptible to Primary Water Stress Corrosion Cracking Section XI, Division 1 RA-23-0118, Cycle 29, Revision 1, Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) RA-23-0117, Report of Changes to Duke Energy McGuire Emergency Plan Annex2023-05-0101 May 2023 Report of Changes to Duke Energy McGuire Emergency Plan Annex RA-23-0111, Withdrawal of License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-27027 April 2023 Withdrawal of License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies 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-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 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-23-0099, Subsequent License Renewal Application Second Annual Amendment to the License Renewal Application2023-04-25025 April 2023 Subsequent License Renewal Application Second Annual Amendment to the License Renewal Application RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-23-0091, Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 42023-04-13013 April 2023 Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 RA-22-0292, License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-04-0404 April 2023 License Amendment Request to Revise Technical Specification 5.5.2, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies 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-23-0036, 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-23-0037, Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis)2023-03-30030 March 2023 Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis) 2024-01-08
[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-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023 Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage 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-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023 Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023 End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) 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-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle2022-06-29029 June 2022 Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle 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-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology 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-22-0003, 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-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 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 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 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-21-0321, Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-12-14014 December 2021 Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report 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-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-10-0404 October 2021 Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 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 2023-07-07
[Table view] |
Text
Regis T. Repko 526 S. Church Street Charlotte, NC 28202 Mailing Address:
EC07H / P.O. Box 1006 Charlotte, NC 28202 704.382.4126 Regis.Repko@duke-energy.com Serial: RA-16-0006 10 CFR 50.90 February 1, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 CATAWBA NUCLEAR STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-413 AND 50-414 RENEWED LICENSE NOS. NPF-35 AND NPF-52 MCGUIRE NUCLEAR STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-369 AND 50-370 RENEWED LICENSE NOS. NPF-9 AND NPF-17 OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3 DOCKET NOS. 50-269, 50-270 AND 50-287 RENEWED LICENSE NOS. DPR-38, DPR-47 AND DPR-55
SUBJECT:
RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION (RAI)
REGARDING APPLICATION TO USE ALTERNATE FISSION GAS GAP RELEASE FRACTIONS
REFERENCE:
- 1. Duke Energy letter, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods that Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11, dated July 15, 2015 (ADAMS Accession No. ML15196A093).
- 2. Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, Revision 0, U.S. Nuclear Regulatory Commission, July 2000.
- 3. NRC letter, Catawba Nuclear Station, Units 1 and 2; McGuire Nuclear Station, Units 1 and 2; and Oconee Nuclear Station, Units 1, 2, and 3: Request for Additional Information Regarding License Amendment Request to Use an Alternate Fission Gas Gap Release Fraction (TAC Nos. MF6480, MF6481, MF6482, MF6483, MF6484, MF6485 and MF6486), dated December 17, 2015 (ADAMS Accession No. ML15348A260).
Ladies and Gentlemen:
In Reference 1, Duke Energy Carolinas, LLC (Duke Energy) submitted a license amendment request (LAR) for Catawba Nuclear Station (CNS), Units 1 and 2; McGuire Nuclear Station (MNS), Units 1 and 2; and Oconee Nuclear Station (ONS), Units 1, 2 and 3. The request for
U.S. Nuclear Regulatory Commission RA-16-0006 Page2 amendment proposes to revise the facilities as described in the Updated Final Safety Analysis Reports (UFSAR) to provide gap release fractions for high-burnup fuel rods that exceed the 6.3 kW/ft linear heat generation rate (LHGR) limit detailed in Table 3 of Reference 2. In Reference 3, the Nuclear Regulatory Commission (NRC) requested additional information (RAI) regarding the original Duke Energy submittal. The enclosure provides Duke Energy's response to the NRC RAI requested in Reference 3.
This submittal contains no new regulatory commitments.
In accordance with 10 CFR 50.91, Duke Energy is transmitting a copy of this letter to the designated state officials of North Carolina and South Carolina. Should you have any questions concerning this letter and its enclosure, 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 February 1, 2016.
Sincerely, Zr~
Regis T. Repko Senior Vice President - Governance, Projects and Engineering
Enclosure:
Response to NRC Request for Additional Information cc: (all with Enclosure unless otherwise noted)
L.D. Wert, Regional Administrator USNRC Region II (Acting)
E.L. Crowe, USNRC Senior Resident Inspector - ONS G.A. Hutto, USNRC Senior Resident Inspector - CNS J. Zeiler, USNRC Senior Resident Inspector - MNS J.R. Hall, NRR Senior Project Manager- ONS G.E. Miller, NRR Project Manager - MNS J. Whited, NRR Project Manager - CNS W.L. Cox, Ill, Section Chief, NC DHSR S.E. Jenkins, Manager, Radioactive and Infectious Waste Management Section (SC)
U.S. Nuclear Regulatory Commission RA-16-0006 Page 3 bcc: (all with Enclosure unless otherwise noted)
Chris Nolan Art Zaremba Jordan Vaughan Dave Culp Geoff Pihl Tracy Saville ELL File: (Corporate)
Steven Capps Jeff Robertson P.T. Vu Kay Crane (for MNS Licensing/Nuclear Records)
MNS Master File 801.01 - MG02DM Scott Batson Chris Wasik Steve Newman Tom Ray Ed Burchfield Terry Patterson Judy Smith (for ONS Licensing/Nuclear Records)
ONS Master File 801.01 - ON03DM Kelvin Henderson Cecil Fletcher Larry Rudy NCMPA-1 PMPA NCEMC Toni Pasour (for CNS Licensing/Nuclear Records)
CNS Master File 801.01 - CN04DM
Enclosure to RA-16-0006 Page 1 of 14 Enclosure Response to NRC Request for Additional Information
Enclosure to RA-16-0006 Page 2 of 14 NRC Request for Additional Information:
By letter dated July 15, 2015 (Agencywide Documents Access and Management System Accession No. ML15196A093), Duke Energy Carolinas, LLC, license amendment requires to use a set of fission gas gap release fractions for high burnup fuel rods that exceed the linear heat generation rate limit detailed in Regulatory Guide 1.183, Table 3, Footnote 11. In order for the U.S. Nuclear Regulatory Commission (NRC) staff to complete its review of the request, the following additional information is requested.
ARCB-RAI-1 For those changes to the current licensing basis (CLB) parameters used in the affected dose consequence analyses provide additional information describing, for each affected design basis accident, all the basic parameters used in the dose consequence analyses. For each parameter, please indicate; the CLB value, the revised value where applicable, the basis for any changes made to the CLB values, and the applicable reference location within either the Updated Final Safety Analysis Report or Technical Specifications. If possible, the NRC staff requests that this information be presented in separate tables for each accident evaluated.
Duke Energy Response to ARCB-RAI-1:
The affected design basis accidents for the three nuclear stations covered by the license amendment request (LAR) under NRC review are as follows:
Catawba Nuclear Station (CNS)
- Fuel handling accident outside containment (CNS UFSAR Sections 15.7.4.2.1 &
15.7.4.3.1)
- Fuel handling accident inside containment (CNS UFSAR Sections 15.7.4.2.2 &
15.7.4.3.2)
- Weir gate drop (CNS UFSAR Sections 15.7.4.2.3 & 15.7.4.3.3)
- Spent fuel cask drop (denotes a drop of a loaded but unsealed spent fuel cask into a fuel pit) (CNS UFSAR Section 15.7.5)
McGuire Nuclear Station (MNS)
- Fuel handling accident inside containment (MNS UFSAR Section 15.7.4.1)
- Fuel handling accident in the fuel building (MNS UFSAR Section 15.7.4.2)
- Weir gate drop (MNS UFSAR Section 15.7.4.3)
- Spent fuel cask drop (denotes a drop of a loaded but unsealed spent fuel cask into a fuel pit) (MNS UFSAR Section 15.7.4.4)
Oconee Nuclear Station (ONS)
- Fuel handling accident (single assembly event) (ONS UFSAR Sections 15.11.2.1 &
15.11.2.2)
Enclosure to RA-16-0006 Page 3 of 14
- Fuel cask handling accident (multiple assembly event) (ONS UFSAR Sections 15.11.2.4
& 15.11.2.5.3)
For the Alternate Source Term (AST) dose analyses of the aforementioned design basis accidents, the values were changed for only two parameters as follows:
Parameter 1 (revised for CNS Only)
The limiting isotopic activity values in a fuel assembly used in the AST analysis of the fuel handling accidents and weir gate drop at CNS were revised. The replacement isotopic activities are based on a peaking factor of 1.65; the isotopic activities in the CLB are based on a burnup dependent peaking factor (CNS UFSAR Sections 15.7.4.2.1, 15.7.4.2.2 & 15.7.4.2.3 and Reference 1). The limiting isotopic activities calculated for a fuel assembly at MNS and ONS already account for a constant peaking factor (ONS UFSAR Sections 15.11.2.1 & 15.11.2.4 and Reference 2) and were not revised. The CLB and revised fuel assembly isotopic activities for CNS are listed in Table 1 below.
Table 1: Fuel Assembly Isotopic Activities Used in the AST Analysis of the Fuel Handling Accidents and Weir Gate Drop at CNS Isotope CLB (Ci) Revised (Ci) Isotope CLB (Ci) Revised (Ci)
Noble Gases Halogens Kr83m 1.25E+05 1.32E+05 Br83 1.31E+05 Kr85m 2.80E+05 2.98E+05 Br85 2.99E+05 Kr85 6.78E+03 7.48E+03 Br87 4.95E+05 Kr87 5.76E+05 6.15E+05 I130 2.32E+04 3.95E+04 Kr88 8.14E+05 8.69E+05 I131 7.46E+05 8.09E+05 Kr89 1.05E+06 1.12E+06 I132 1.10E+06 1.18E+06 Xe131m 3.97E+03 1.24E+04 I133 1.61E+06 1.67E+06 Xe133m 4.71E+04 5.20E+04 I134 1.86E+06 1.95E+06 Xe133 1.53E+06 1.65E+06 I135 1.53E+06 1.60E+06 Xe135m 2.84E+05 3.62E+05 I136 7.91E+05 Xe135 3.36E+05 4.12E+05 Xe137 1.46E+06 1.55E+06 Alkali Metals Xe138 1.51E+06 1.59E+06 Rb86 2.54E+03 Rb88 8.89E+05 Rb89 1.18E+06 Rb90 1.12E+06 Cs134 2.06E+05 Cs136 5.92E+04 Cs137 9.23E+04 Cs138 1.66E+06 Cs139 1.58E+06
Enclosure to RA-16-0006 Page 4 of 14 Notes on Table 1:
- 1) The CLB isotopic activity values are taken from Table 15-45 of the CNS UFSAR. The revised values are taken from Table 7 of the Duke Energy LAR that was submitted on July 15, 2015 and is currently under NRC review.
- 2) The activities used in the dose analysis in the CLB account for isotopes of noble gases (krypton and xenon) and iodine. Further discussion for bromine and alkali metals is provided in the Duke Energy request for partial scope implementation of AST at CNS (Reference 1) which was approved by the NRC (Reference 3).
- 3) The revised source term does not include 136I. The half-life for this isotope, less than a minute, is very short compared to the minimum pre-event decay time taken in the AST analysis of any fuel handling type accident (3 days). Its daughter is 136Xe, a stable isotope. Accordingly, 136I does not contribute discernibly to the radiation doses following fuel handling accidents or a weir gate drop.
Parameter 2 Gap fraction values were revised for 25 fuel pins in each fuel assembly for which operation beyond the current limit of Regulatory Guide 1.183, Table 3, Footnote 11 is assumed in the supporting dose analyses. Also listed in Tables 6 and 8 of the Duke Energy LAR that was submitted on July 15, 2015 and currently under NRC review, the initial and revised values of the gap fractions are listed in Table 2 below.
Table 2: Non-LOCA Gap Fractions (CNS, MNS & ONS)
Gap Fraction from Non-LOCA Gap Isotope or Isotope Table 3 of Reg Guide Fractions for Rods Group 1.183 (Rev. 0) Operated in Excess of the RG 1.183, Table 3, Footnote 11 Limit I-131 0.08 0.16 Kr-85 0.10 0.30 Xe-133 0.05 0.15 Cs-134 (Alkali Metal) 0.12 0.36 Cs-137 (Alkali Metal) 0.12 0.36 Other Noble Gases 0.05 0.10 Other Halogens 0.05 0.10 Other Alkali Metals 0.12 0.24 The values for all other parameters represented in the AST analyses of the fuel handling accidents, weir gate drop and fuel cask drop are unchanged from their CLB values. The three tables presented below provide the locations of the CLB values for these parameters separately for CNS, MNS and ONS.
Enclosure to RA-16-0006 Page 5 of 14 Table 3: Parameters Associated with the Dose Analysis of Fuel Handling Accidents at CNS Parameters Common to the Dose Analyses of All Fuel Handling Type Accidents Parameter: Pool decontamination factor (DF) for noble gases Location: UFSAR Section 15.7.4.2.1, Bullet 7 and Table 15-46, Line Item 2.a Notes: No credit is taken for retention of noble gases in the pool.
Parameter: Pool decontamination factor (DF) for iodine isotopes Location: UFSAR Section 15.7.4.2.1, Bullet 9 and Table 15-46, Line Item 2.a Notes: The value may be found in both the text and table as indicated. See UFSAR Section 15.7.4.2.1, Bullet 5 for related discussion.
Parameter: Chemical composition fractions for iodine released to the environment Location: UFSAR Section 15.7.4.2.1, Bullet 9 and Table 15-46, Line Item 2.b Notes: The value may be found in both the text and table as indicated.
Parameter: Profile of release to the environment Location: UFSAR Section Table 15-46, Line Item 2.c Notes: Refer to UFSAR Section 15.7.4.2.1, Bullet 11 for additional discussion.
Parameter: No credit for the ventilation system for the building in which the accident starts Location: UFSAR Section 15.7.4.2.1, Bullet 14 Notes: This applies to the ventilation systems in the building in which the event starts.
The ventilation system associated with the fuel handling accident in containment is the Containment Purge Ventilation System (see also UFSAR Section 15.7.4.2.2, Bullet 1). The Fuel Handling Ventilation Exhaust System is associated with the fuel handling accident in the fuel building, weir gate drop, and the fuel cask drop.
Parameter: Exclusion Area Boundary (EAB) atmospheric dispersion factor (/Q)
Location: UFSAR Table 15-46, Line Item 3.a.
Parameter: Low Population Zone boundary (LPZ) /Q Location: UFSAR Table 15-46, Line Item 3.b Notes: This is the 0-8 hour value. Refer to Table 15-40, Pg. 5 for values for the other intervals.
Parameter: Number of Control Room Area Ventilation System (CRAVS) intakes open Location: UFSAR Table 15-46, Line Item 4.a Notes: CNS is equipped with two CRAVS intakes but in these analyses only one is assumed to be initially open.
Parameter: Control room /Q Location: UFSAR Table 15-46 Line Item 4.b Notes: This is the 0-2 hour value. See Table 15-40, Pg. 5 for values for the remaining averaging intervals.
Enclosure to RA-16-0006 Page 6 of 14 Parameter: Control room volume Location: UFSAR Table 15-46, Line Item 5.a Parameter: CRAVS (total and recirculation) airflow rates Location: UFSAR Table 15-46, Line Item 5.b Notes: Total and recirculation airflow rates are given. The outside airflow rate is found by subtracting the recirculation airflow rate from the total airflow rate.
Parameter: Rate of unfiltered inleakage to the control room Location: Duke Energy request for partial scope implementation of AST at CNS (Reference
- 1) and Attachment 8 under the header Rate of unfiltered CR inleakage."
Notes: Two values are given for this parameter. The higher value corresponds to no CRAVS operation; the lower value corresponds to at least one CRAVS train in operation.
Parameter: CRAVS efficiencies Location: UFSAR Table 15-46, Line Item 5.b Parameter: Control room occupancy factors Location: Reference 1, Attachment 8 under the header Control Room Occupancy Factors Parameter: Dose coefficients Location: UFSAR Table 15-46, Line Item 6 Parameters Common to the Dose Analyses of the Fuel Handling Accidents and Weir Gate Drop Parameter: Normal AC / offsite power Location: UFSAR Section 15.7.4.2.1, Bullet 16 Notes: The assumption is conservative based on the associated assumptions pertaining to CRAVS operation.
Parameter: CRAVS operation Location: UFSAR Section 15.7.4.2.1, Bullet 17 Parameter: CRAVS start time Location: UFSAR Section 15.7.4.2.1, Bullet 17
Enclosure to RA-16-0006 Page 7 of 14 Parameters Common to the Dose Analysis of the Fuel Handling Accidents Parameter: Number of fuel assemblies damaged Location: UFSAR Section 15.7.4.2.1, Bullet 2 and Table 15-46, Line Item 1.d Parameter: Pre-event decay time Location: UFSAR Section 15.7.4.2.1, Bullet 1 and Table 15-46, Line Item 1.b Parameters Associated with the Dose Analysis of the Weir Gate Drop Parameter: Number of fuel assemblies damaged Location: UFSAR Section 15.7.4.2.3, Bullet 2 and Table 15-58, Line Item 1.b Parameter: Pre-event decay time Location: UFSAR Section 15.7.4.2.3, Bullet 1 and Table 15-58, Line Item 1.a Parameters Associated with the Dose Analysis of the Fuel Cask Drop Parameter: Number of fuel assemblies damaged Location: UFSAR Section 15.7.5 Parameter: Pre-event decay time Location: UFSAR Section 15.7.5 Parameter: Isotopic activities released to the pool Location: UFSAR Section 15.7.5 Parameter: Isotopic activities released from the pool Location: UFSAR Section 15.7.5 Parameter: CRAVS operating status Value: Both CRAVS are on-line at event initiation with each CRAVS train providing the airflow rates listed in Table 15-46, Line Item 5.b. The operators turn off one CRAVS train 30 minutes into the event.
Enclosure to RA-16-0006 Page 8 of 14 Table 4: Parameters Associated with the Dose Analysis of Fuel Handling Accidents at MNS Parameters Common to the Dose Analyses of All Fuel Handling Type Accidents Parameter: Pool decontamination factor (DF) for noble gases Location: UFSAR Section 15.7.4.1.2 Parameter: Pool decontamination factor (DF) for iodine isotopes Location: Reference 2, Attachment 2, Table 3 Parameter: Chemical composition fractions for iodine released to the environment Location: Reference 2, Attachment 2, Table 3 Parameter: No credit for the ventilation system for the building in which the accident starts Location: UFSAR Section 15.7.4.1.2 Notes: See the Tornado Missile Accident section for details for that accident.
Parameter: Exclusion Area Boundary (EAB) atmospheric dispersion factor (/Q)
Location: Reference 2, Attachment 4, Table 5 Parameter: Low Population Zone boundary (LPZ) /Q Location: Reference 2, Attachment 4, Table 5 Parameter: Number of Control Room Area Ventilation System (CRAVS) intakes open Location: Reference 2, Section 3.3.1.2 Parameter: Control room /Q Location: Reference 2, Section 3.3.1.2 points to the LAR submitted December 20, 2005 Appendix D of Attachment 3 (Reference 4)
Parameter: Control room volume Location: Reference 4, Attachment 3, Appendix D Parameter: Rate of unfiltered inleakage to the control room Location: Reference 2, Attachment 2, Table 3 Notes: See the Tornado Missile Accident section for details for that accident.
Parameter: CRAVS efficiencies Location: Reference 2, Attachment 2, Table 3 Parameter: Control room occupancy factors Location: Reference 2, Attachment 2, Table 3 Parameter: Dose coefficients Location: Reference 4, Attachment 3, Section 6
Enclosure to RA-16-0006 Page 9 of 14 Parameters Common to the Dose Analyses of the Fuel Handling Accidents and Weir Gate Drop Parameter: CRAVS operation Location: Reference 2, Attachment 2, Table 3 Parameter: CRAVS start time Location: Reference 2, Attachment 2, Table 3 Parameters Common to the Dose Analysis of the Fuel Handling Accidents Parameter: Number of fuel rods damaged Location: Reference 2, Attachment 2, Table 3 Parameter: Pre-event decay time Location: Reference 2, Attachment 2, Table 3 Parameters Associated with the Dose Analysis of the Weir Gate Drop Parameter: Number of fuel rods damaged Location: Reference 2, Attachment 2, Table 3 Parameter: Pre-event decay time Location: Reference 2, Attachment 2, Table 3 Parameters Associated with the Dose Analysis of the Fuel Cask Drop Parameter: Number of fuel assemblies damaged Location: UFSAR Section 15.7.4.4 Parameter: Pre-event decay time Location: UFSAR Section 15.7.4.4 Parameter: Isotopic activities released to the pool Location: UFSAR Section 15.7.4.4 Parameter: Isotopic activities released from the pool Location: UFSAR Section 15.7.4.4
Enclosure to RA-16-0006 Page 10 of 14 Parameters Associated with the Dose Analysis of the Tornado Missile Accident Parameter: Number of fuel assemblies damaged Location: UFSAR Section 15.10 and UFSAR Table 15-39 Parameter: Pre-event decay time Location: UFSAR Section 15.10 and UFSAR Table 15-39 Parameter: Credit for the fuel building (VF) ventilation system Location: UFSAR Section 15.10 and UFSAR Table 15-39 Notes: Credit is only assumed in the sense that it impacts the release point. The release point is the rollup door and not the unit vent. No credit is assumed for VF filtration.
Parameter: Rate of unfiltered inleakage to the control room Location: UFSAR Table 15-39 Parameter: Offsite /Q Location: UFSAR Table 15-39
Enclosure to RA-16-0006 Page 11 of 14 Table 5: Parameters Associated with the Dose Analysis of Fuel Handling Accidents at ONS Parameters Common to the Analyses of All Fuel Handling Type Accidents Parameter: Pool decontamination factor (DF) for noble gases Location: UFSAR Section 15.11.2.1 and ONS AST SER (Reference 5), Table 3 (page 25)
Parameter: Pool decontamination factor (DF) for iodine isotopes Location: UFSAR Sections 15.11.2.1, 15.11.2.2 and 15.11.2.4 and Reference 5, Table 3 (page 25)
Parameter: Chemical composition fractions for iodine released to the environment Location: ONS Supplement to LAR for Full-scope Implementation of AST (Reference 6),
page 67 Parameter: No credit for removal of fission products by the PRVS, SFPVS, or the RB purge exhaust filtration system Location: Reference 5, page 6 Parameter: Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) atmospheric dispersion factor (/Q)
Location: Reference 5, page 26 (Table 4)
Parameter: Control room /Q Location: Unadjusted values listed in UFSAR Table 15-61. Airflow imbalance of 55% / 45%
is then applied for dual intakes as described in UFSAR Section 15.1.10 and Reference 5, Section 3.4.3. For the FHA accidents, the unit vent release location is limiting.
Parameter: Control room volume (Unit 1&2 control room is associated with limiting dose),
CRVS airflow rate, CRVS filter efficiencies, and control room occupancy factors Location: ONS AST LAR (Reference 7), Attachment 3, pages 21 and 22 Parameter: Rate of unfiltered inleakage to the control room Location: Unit 1&2 values are associated with the limiting dose: post-pressurization inleakage of 150 cfm from Reference 7, Attachment 3, page 21 and pre-pressurization inleakage of 1202 cfm.
Parameter: Dose coefficients (from Federal Guidance Report 11 and 12)
Location: Reference 7, Attachment 3, page 19
Enclosure to RA-16-0006 Page 12 of 14 Parameters Associated with the Analysis of the Fuel Handling Accident (Single Assembly Event)
Parameter: Number of fuel assemblies damaged, fission product decay period and radial peaking factor Location: Reference 5, Table 3 (page 25)
Parameters Associated with the Analysis of a Fuel Cask Handling Accident (Multiple Assembly Event)
Parameter: Number of fuel assemblies damaged and fission product decay period Location: Reference 5, Table 3 (page 25). Detailed description of parameter combinations for each case is given in Reference 6, page 61. The limiting dose is associated with the case of a transport cask drop into the Unit 1&2 SFP with 576 assemblies damaged (354 assemblies decayed over 55 days and 222 assemblies decayed over 1 year).
Parameter: Radial peaking factor Location: Reference 5, Table 3 (page 25)
ARCB-RAI-2 Appendix B of RG 1.183, Regulatory Position 1.1 states:
"The number of fuel rods damaged during the accident should be based on a conservative analysis that considers the most limiting case. This analysis should consider parameters such as the weight of the dropped heavy load or the weight of a dropped fuel assembly (plus any attached handling grapples), the height of the drop, and the compression, torsion, and shear stresses on the irradiated fuel rods. Damage to adjacent fuel assemblies, if applicable (e.g., events over the reactor vessel), should be considered."
Please explain how the revised fuel handling accident analysis determines the most limiting case, and how it shows that the limiting case is not the drop of an object other than an irradiated fuel assembly.
Duke Energy Response to ARCB-RAI-2:
As demonstrated in the original July 15, 2015 LAR submittal, the weir gate drop is the fuel handling accident at CNS associated with the highest calculated values for offsite and control room radiation doses. It is assumed in the AST analysis of the weir gate drop that all fuel pins in seven spent fuel assemblies are damaged. This assumption is unchanged from the AST analysis originally reviewed by the NRC (References 1 and 3) and the original NRC review of the analysis of radiological consequences of the weir gate drop (Reference 8).
Of all of the fuel handling type accidents in the MNS CLB, the weir gate drop is associated with the highest calculated values for exclusion area boundary radiation doses, while the tornado missile accident is limiting for the low population zone and control room radiation doses. It is
Enclosure to RA-16-0006 Page 13 of 14 assumed in the weir gate drop dose analysis that seven of the impacted spent fuel pool assemblies are damaged. For the tornado missile accident, twelve fuel assemblies are assumed to fail. These assumptions are unchanged from the CLB dose analyses contained in the MNS UFSAR.
Of all of the fuel handling type accidents in the ONS CLB, the fuel cask handling accident (drop into the spent fuel pool) is associated with the highest calculated values for offsite and control room radiation doses. It is assumed in the limiting dose analysis that all fuel pins in the 576 impacted spent fuel pool assemblies are damaged. This assumption is unchanged from the dose analysis reviewed by the NRC (Reference 5).
References:
- 1. Duke Energy letter, Duke Energy Corporation Catawba Nuclear Station Unit (s) 1 and 2 Docket Numbers 50-413 and 50-414 Revision to Proposed Amendment for Partial Scope Implementation of the Alternate Source Term and Proposed Amendment to Technical Specifications (TS) 3.7.10, Control Room Area Ventilation System, TS 3.7.11, Control Room Area Chilled Water System, TS 3.7.13, Fuel Handling Ventilation Exhaust System, and TS 3.9.3, Containment Penetrations, dated March 26, 2002 (ADAMS Accession No. ML020930658).
- 2. NRC letter, McGuire Nuclear Station, Units 1 and 2, Issuance of Amendments Regarding Implementation of Alternative Source Term Methodology (TAC Nos. MC9746 and MC9747), dated December 22, 2006 (ADAMS Accession No. ML063100406).
- 3. NRC letter, Catawba Nuclear Station, Units 1 and 2 RE: Issuance of Amendments (TAC Nos. MB3758 and MB3759), dated April 23, 2002 (ADAMS Accession No. ML021140431).
- 4. Duke Energy letter, Duke Energy Corporation McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 License Amendment Request for Selective Implementation of the Alternative Source Term and Revision to Technical Specification 3.9.4, Containment Penetrations, dated December 20, 2005 (ADAMS Accession No. ML060250098).
- 5. NRC letter, Oconee Nuclear Station, Units 1, 2 and 3 RE: Issuance of Amendments (TAC Nos. MB3537, MB3538, and MB3539), dated June 1, 2004 (ADAMS Accession No. ML041540097).
- 6. Duke Energy letter, Oconee Nuclear Station Docket Numbers 50-269, 270, and 287 Supplement to License Amendment Request for Full-Scope Implementation of the Alternate Source Term Technical Specification Change (TSC) Number 2001-07, dated May 20, 2002 (ADAMS Accession No. ML021430249).
Enclosure to RA-16-0006 Page 14 of 14
- 7. Duke Energy letter, Duke Energy Corporation Oconee Nuclear Station Units 1, 2, and 3 Docket Nos. 50-269, 50-270, 50-287 License Nos. NPF-38, NPF-47, and NPF-55 Licensed Amendment Request for Full-Scope Implementation of the Alternative Source Term and Technical Specifications 3.3.5, Engineered Safeguards Protective System (ESPS) Analog Instrumentation; 3.3.6, Engineered Safeguards Protective System (ESPS) Manual Initiation; 3.3.7, Engineered Safeguards Protective System (ESPS)
Digital Automatic Actuation Logic Channels; 3.7.10, Penetration Room Ventilation System; 3.7.17 Spent Fuel Pool Ventilation System; 3.9.3, Containment Penetrations; 5.5.2, Containment Leakage Rate Testing Program; and 5.5.12, Ventilation Filter Testing Program Technical Specification Change Number 01-07, dated October 16, 2001 (ADAMS Accession No. ML020030487).
- 8. NRC letter, Catawba Nuclear Station - Supplement to the Catawba Safety Evaluation Report (NUREG-0954), Postulated Weir Gate Drop Accident (TAC MA0135 and MA0136), dated May 21, 1998.