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Category:Letter
MONTHYEARIR 05000269/20243012024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 2024-08-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-24-0136, Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 52024-05-24024 May 2024 Subsequent License Renewal Application Third Annual Update to the License Renewal Application and Subsequent License Renewal Application Supplement 5 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-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-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-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-22-0285, Subsequent License Renewal - Appendix E Environmental Report Supplement 22022-11-0707 November 2022 Subsequent License Renewal - Appendix E Environmental Report Supplement 2 RA-22-0157, Subsequent License Renewal Application First Annual Amendment to the License Renewal Application and Subsequent License Renewal Application Supplement 42022-06-0707 June 2022 Subsequent License Renewal Application First Annual Amendment to the License Renewal Application and Subsequent License Renewal Application Supplement 4 RA-22-0057, License Amendment Request to Address Technical Specifications Mode Change Limitations2022-03-31031 March 2022 License Amendment Request to Address Technical Specifications Mode Change Limitations RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0316, Subsequent License Renewal Application Supplement 32021-12-15015 December 2021 Subsequent License Renewal Application Supplement 3 RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-21-0297, Subsequent License Renewal Application, Appendix E, Environmental Report Supplement 12021-11-11011 November 2021 Subsequent License Renewal Application, Appendix E, Environmental Report Supplement 1 RA-21-0288, Subsequent License Renewal Application Supplement 22021-11-11011 November 2021 Subsequent License Renewal Application Supplement 2 RA-21-0249, Subsequent License Renewal Application Supplement 12021-10-28028 October 2021 Subsequent License Renewal Application Supplement 1 RA-21-0005, Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump on a Temporary Basis2021-09-0202 September 2021 Application to Revise Technical Specification 3.7.7, Low Pressure Service Water (LPSW) System, to Extend the Completion Time for One Required Inoperable LPSW Pump on a Temporary Basis RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-19-0039, License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes2020-04-13013 April 2020 License Amendment Request to Revise Technical Specifications to Adopt Two NRC-Approved Generic Technical Specification Changes RA-19-0144, License Amendment Request for Measurement Uncertainty Recapture Power Uprate2020-02-19019 February 2020 License Amendment Request for Measurement Uncertainty Recapture Power Uprate RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RA-19-0253, Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building2019-08-28028 August 2019 Proposed License Amendment Request to Revise the Oconee Nuclear Station Current Licensing Basis for High Energy Line Breaks Outside of the Containment Building RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-0136, License Amendment Request Proposing a Revised 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, ...2018-11-0101 November 2018 License Amendment Request Proposing a Revised 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, ... RA-18-0026, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis2018-09-14014 September 2018 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Sections Associated with the Oconee Tornado Licensing Basis RA-18-0023, License Amendment Request (2017-05) to Add a Surveillance Requirement to Technical Specification 3.8.1, AC Sources2018-05-17017 May 2018 License Amendment Request (2017-05) to Add a Surveillance Requirement to Technical Specification 3.8.1, AC Sources RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ONS-2017-074, Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-032017-10-20020 October 2017 Proposed Amendment to the Renewed Facility Operating Licenses Regarding Revisions to the Updated Final Safety Analysis Report Section Associated with Tile Standby Shutdown Facility License Amendment Request No. 2017-03 RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17095A5302017-03-30030 March 2017 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process; License Amendment Request No. 2015-03 ONS-2016-082, Technical Specification Bases Change for TS Bases 3.4.16, Steam Generator Tube Integrity2016-09-0808 September 2016 Technical Specification Bases Change for TS Bases 3.4.16, Steam Generator Tube Integrity ML16209A2232016-07-21021 July 2016 Amendment Request to Add the Copernic Fuel Performance Code to Technical Specifications 2.1.1.1, Reactor Core Safety Limits, and 5.6.5, Core Operating Limits Report (COLR) ONS-2016-052, License Amendment Request to Revise Technical Specifications Associated with Dry Spent Fuel Storage Cask Loading and Unloading Requirements; License Amendment Request No. 2016-042016-07-20020 July 2016 License Amendment Request to Revise Technical Specifications Associated with Dry Spent Fuel Storage Cask Loading and Unloading Requirements; License Amendment Request No. 2016-04 ML16064A0202016-02-26026 February 2016 License Amendment Request for a Temporary Technical Specification Change to Add a Required Action Completion Time for One Keowee Hydro Unit Inoperable for Generator Stator Replacement, LAR No. 2015-08 ONS-2015-106, Technical Specification (TS) Bases Change2015-10-26026 October 2015 Technical Specification (TS) Bases Change ML15232A0172015-07-17017 July 2015 License Amendment Request (LAR) to Correct Usage Problem with Recently Issued Amendment to Technical Specification 3.8.1, License Amendment Request No. 2014-04 RA-15-001, Catawba, McGuire, and Oconee - 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, Foot2015-07-15015 July 2015 Catawba, McGuire, and Oconee - 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, Footn RA-15-0013, 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 112015-07-15015 July 2015 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 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4392015-06-24024 June 2015 Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-523, Rev. 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 1 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 ONS-2015-045, License Amendment Request to Change the Emergency Plan to Upgrade ONS Emergency Action Levels Based on NEI 99-01, Revision 6, License Amendment Request No. 2015-042015-06-23023 June 2015 License Amendment Request to Change the Emergency Plan to Upgrade ONS Emergency Action Levels Based on NEI 99-01, Revision 6, License Amendment Request No. 2015-04 ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-052015-05-19019 May 2015 License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05 ONS-2014-105, License Amendment Request for Adoption of Technical Specification Task Force (TSTF) - 513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation; License Amendment Request No. 2011-032014-09-18018 September 2014 License Amendment Request for Adoption of Technical Specification Task Force (TSTF) - 513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation; License Amendment Request No. 2011-03 RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014 License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area ONS-2014-080, License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-032014-06-30030 June 2014 License Amendment Request (LAR) to Reduce Allowed Maximum Rated Thermal Power When High Pressure Injection (HPI) Equipment Is Inoperable License Amendment Request No. 2013-03 ONS-2014-020, License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement, LAR No. 2013-052014-05-20020 May 2014 License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement, LAR No. 2013-05 ONS-2014-020, Oconee, Units 1, 2 and 3 - License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement,2014-05-20020 May 2014 Oconee, Units 1, 2 and 3 - License Amendment Request to Remove Obsolete Information from Technical Specifications, Delete Surveillance Requirements That Equipment Design Cannot Support and Correct a Non-Conservative Condition Statement, LAR ONS-2014-012, Submittal of Technical Specification Bases Change2014-02-0303 February 2014 Submittal of Technical Specification Bases Change 2024-05-24
[Table view] Category:Technical Specifications
MONTHYEARRA-24-0092, Application to Revise Technical Specification 3.7.7, “Low Pressure Service Water (LPSW) System,” to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis2024-07-29029 July 2024 Application to Revise Technical Specification 3.7.7, “Low Pressure Service Water (LPSW) System,” to Extend the Completion Time for One Required LPSW Pump Inoperable on a One-Time Basis ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22096A1872022-07-15015 July 2022 Issuance of Amendment Nos. 424, 426, and 425 Revise TS 3.7.7, Low Pressure Service Water (LPSW) System to Extend the Completion Time for One Required Inoperable LPSW Pump RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17103A5092017-05-11011 May 2017 Issuance of Amendments Allowing the Use of the Copernic Fuel Performance Code ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16138A3322016-06-0606 June 2016 Issuance of Amendments to Correct Usage Problem with Technical Specification 3.8.1 ML16088A3302016-04-29029 April 2016 Issuance of Amendments to Add High Flux Trip for Three Reactor Coolant Pump Operation ML16075A3012016-04-26026 April 2016 Issuance of Amendments Regarding the Revision of the Steam Generator Technical Specifications to Reflect the Adoption of TSTF-510(CAC Nos. MF6139,MF6140,MF6141,MF6142,MF6143,MF6144. ML15166A3872015-09-24024 September 2015 Issuance of Amendments Regarding Allowed Maximum Rated Thermal Power ML15170A0552015-07-27027 July 2015 Issuance of Amendments Regarding Adoption of TSTF-513 ML15174A2672015-07-0707 July 2015 Issuance of Amendments Regarding the Inservice Testing Program ML15050A6712015-06-19019 June 2015 Issuance of Amendments Regarding Inspection Plan for Reactor Vessel Internals ML15133A4532015-06-11011 June 2015 McGuire Nuclear Station, Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Cyber Security Plan Implementation Schedule Milestone 8 ML15093A3492015-04-23023 April 2015 Issuance of Amendments Regarding Keowee Hydro Unit (Khu) Steady State Frequency Requirements ML15002A3242015-02-12012 February 2015 McGuire Nuclear Station, and Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Areas ML14195A3552014-10-21021 October 2014 Issuance of Amendments ML14254A2462014-09-25025 September 2014 Issuance of Amendments Regarding Quality Assurance Requirements for the Standby Shutdown Facility Equipment ML14206A7902014-08-13013 August 2014 Issuance of Amendments Regarding Implementation of the Protected Service Water System ML14106A4182014-04-30030 April 2014 Issuance of Amendment Regarding Use of Reverse Osmosis System ONS-2103-005, Additional Information Associated with License Amendment Request for Reverse Osmosis System Operation, License Amendment Request No. 2012-05, Supplement 42013-10-21021 October 2013 Additional Information Associated with License Amendment Request for Reverse Osmosis System Operation, License Amendment Request No. 2012-05, Supplement 4 ML13231A0132013-08-23023 August 2013 Issuance of Amendments Regarding the Technical Specification for Keowee Hydro Units (TAC Nos. ME9880, ME9881, and ME9882) ML12307A2192012-10-30030 October 2012 License Amendment Request for Approval to Operate a Reverse Osmosis System to Remove Silica from the Borated Water Storage Tanks and Spent Fuel Pools During Unit Operation and Associated Proposed Tech Specs and Bases.. ML12086A2892012-04-20020 April 2012 Issuance of Amendments Regarding Revising the Frequency of Certain Technical Specifications Surveillance Requirements from 18 Months to 24 Months ML12097A2482012-04-0303 April 2012 License Amendment Request for a One-Time, 15-Month Extension to the Integrated Leak Rate Test Interval License Amendment Request No. 2012-03 ML12109A3452012-03-16016 March 2012 Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate, License Amendment Request No. 2011-02, Supplement 2 ML1020302532010-07-14014 July 2010 License Amendment Request (LAR 2009-08) for Adoption of NRC Approved Technical Specification Task Force Change to Standard Technical Specifications, TSTF-52, Implement 10CFR50, App J, Option B ML1013304992010-05-0606 May 2010 License Amendment Request to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles License Amendment Request No. 2010-001 ML0935600772009-12-15015 December 2009 Technical Specifications Revision Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity. ML0924003112009-09-21021 September 2009 Issuance of Amendments Regarding Proposed Implementation of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from Ts. 5.2.2 to Support Compliance with 10 CFR Part 26. Catawba Units 1& 2, McGuire, Units 1 & 2, Oconee, Units 1, 2, & ML0924501082009-08-31031 August 2009 License Amendment Request to Amend Technical Specification Required Action to Permit Replacement of the 230 Kv 125 Volt Switchyard Batteries, License Amendment Request No. 2006-20 ML0914102832009-05-18018 May 2009 License Amendment Request to Revise the Definition of Shutdown Margin (SDM) ML0816504752008-05-30030 May 2008 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition). License Amendment Request (LAR) No. 2008-01 L-96-006, Response to RAI Regarding License Amendment Request for Low Pressure Service Water Reactor Building Waterhammer Prevention System Modification to Mitigate Waterhammers Described in Generic Letter 96-06 and Associated Technical..2008-05-0707 May 2008 Response to RAI Regarding License Amendment Request for Low Pressure Service Water Reactor Building Waterhammer Prevention System Modification to Mitigate Waterhammers Described in Generic Letter 96-06 and Associated Technical.. ML0806304962008-03-28028 March 2008 Technical Specifications, Issuance of Amendments Regarding a Change in Corporate Name of License & Oconee Independent Spent Fuel Storage Installation (TAC Nos. 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Duke SB. R.A.JONES OWPowere Vice President A Duke Energy Company Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax February 17, 2003 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Oconee Nuclear Station Docket Numbers 50-269, 270, and 287 License Amendment Request for Standby Shutdown Facility 3.10.1, Surveillance Requirement 3.10.1.9 Technical Specification Change (TSC) Number 2002-11 Pursuant to Title 10, Code of Federal Regulations, Part 50, Section 90 (10 CFR 50.90), Duke Energy Corporation (Duke) proposes to amend Appendix A, Technical Specifications, for Facility Operating Licenses DPR-38, DPR-47 and DPR-55 for Oconee Nuclear Station (ONS), Units 1, 2, and 3. Technical Specification (TS) 3.10.1 Standby Shutdown Facility (SSF),
Surveillance Requirement (SR) 3.10.1.9 currently verifies the SSF diesel generator (DG) is synchronized and loaded and operated for Ž 60 minutes at a load Ž 3000 kW. This SR is specified to be performed on a 92 day frequency. The proposed license amendment request (LAR) revises TS 3.10.1, SR 3.10.1.9, to load the DG Ž 3280 kW. This change supports resolution of an Oconee design basis issue associated with SSF Pressurizer heater capacity.
The revised Technical Specification pages are included in Attachment 1. Attachment 2 contains the markup of the current Technical Specification pages.
The Technical Justification for the amendment request is included in Attachment 3. Attachments 4 and 5 contain the No Significant Hazards Consideration Evaluation and the Environmental Impact Analysis, respectively.
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U. S. Nuclear Regulatory Commission February 17, 2003 Page 2 This proposed change to the TS has been reviewed and approved by the Plant Operations Review Committee and Nuclear Safety Review Board.
Approval of this proposed LAR is requested to coincide with the implementation of the modification to increase the SSF DG loading. The completion of this modification is presently scheduled for August 1, 2003. A 90 day implementation window is requested.
Implementation of these changes will not result in an undue risk to the health and safety of the public.
The Oconee Updated Final Safety Analysis Report has been reviewed and no changes are necessary to support this LAR.
Pursuant to 10 CFR 50.91, a copy of this proposed amendment is being sent to the South Carolina Department of Health and Environmental Control for review, and as deemed necessary and appropriate, subsequent consultation with the NRC staff.
If there are any additional questions, please contact Reene' Gambrell at (864) 885-3364.
Very l1y yours, R. A Jones, Vice President Oconee Nuclear Site
U. S. Nuclear Regulatory Commission February 17, 2003 Page 3 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C. 20555 Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission -Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. C. Shannon Senior Resident Inspector Oconee Nuclear Station Mr. Virgil R. Autry, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201
U. S. Nuclear Regulatory Commission February 17, 2003 Page 4 R. A. Jones, being duly sworn, states that he is Vice President, Oconee Nuclear Site, Duke Energy Corporation, that he is authorized on the part of said Company to sign and file with the U. S. Nuclear Regulatory Commission this revision to the Renewed Facility Operating License Nos. DPR 38, DPR-47, DPR-55; and that all the statements and matters set forth herein are true and correct to the best of his knowledge.
rones, Vice President Occ Nuclear Site scrib and sworn to before me this P/ day of 2003 Notary Public My Commission Expires:
"SEAL
ATTACHMENT 1 TECHNICAL SPECIFICATION Remove Page Insert Page 3.10.1-4 3.10.1-4
SSF 3.10.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.10.1.7 Verify the fuel oil transfer system operates to 92 days automatically transfer fuel oil from the storage tank to the day tank.
SR 3.10.1.8 Verify the fuel oil properties of the fuel oil 92 days stored in the day tank and underground storage tank are tested in accordance with, and maintained within the limits of the Diesel Fuel Oil Testing Program.
SR 3.10.1.9 --------------- NOTES --------------
- 1. DG loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not invalidate this test.
- 3. All DG starts may be preceded by an engine prelube period followed by a warmup period prior to loading.
Verify the SSF DG is synchronized and 92 days loaded and operated for >_60 minutes at a load > 3280 kW. I SR 3.10.1.10 Verify for required SSF battery that the cells, 12 months cell plates and racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.
(continued)
OCONEE UNITS 1, 2, & 3 3.10.1-4 Amendment Nos. XXX, XXX, & XXX I
ATTACHMENT 2 MARKUP OF TECHNICAL SPECIFICATION
SSF 3.10.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.10.1.7 Verify the fuel oil transfer system operates to 92 days automatically transfer fuel oil from the storage tank to the day tank.
SR 3.10.1.8 Verify the fuel oil properties of the fuel oil 92 days stored in the day tank and underground storage tank are tested in accordance with, and maintained within the limits of the Diesel Fuel Oil Testing Program.
SR 3.10.1.9 --------------- NOTES ---------------------------
- 1. DG loadings may include gradual loading as recommended by the manufacturer.
- 2. Momentary transients outside the load range do not invalidate this test.
- 3. All DG starts may be preceded by an engine prelube period followed by a warmup period prior to loading.
Verify the SSF DG is synchronized and 92 days loaded and operated for > 60 minutes at a load __3904-kW.
I SR 3.10.1.10 Verify for required SSF battery that the cells, 12 months cell plates and racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.
(continued)
OCONEE UNITS 1, 2, &3 3.10.1-4 Amendment Nos. , , & 9-Q- I
Attachment 3 Technical Justification
Attachment 3 Technical Justification
Background
For event or transient scenarios involving decay heat removal via the steam generators, an adequate number of pressurizer (PZR) heaters must be functional to compensate for ambient losses in order to maintain a PZR steam bubble for reactor coolant system (RCS) pressure control and ensure adequate natural circulation cooling. Therefore, Technical Specifications (TS) require a specific number of PZR heaters to be operable for normal plant operation. A Selected Licensee Commitment (SLC) is also in place for normal plant conditions. TS 3.4.9.b and SLC 16.5.8a contain these heater requirements.
Technical Specification (TS) 3.10.1 requires the Standby Shutdown Facility (SSF) and its subsystems to be operable in modes 1, 2, and 3. One of the functional requirements is to maintain reactor coolant pressure control following an event.
Manually controlled PZR heaters (126 kW of PZR heater capacity) are currently capable of being powered from the SSF to meet this functional requirement. Per the Bases of the TS, these PZR heaters are considered a support system for SSF Auxiliary Service Water (ASW), so an adequate number of these PZR heaters must be operable for the SSF ASW system to be considered operable. Pursuant to the SSF TS, the SSF ASW system is used to maintain single phase RCS natural circulation flow. The PZR heaters, powered from the SSF diesel generator (DG), are considered a support system for the SSF ASW.
In March 2002, Duke identified a condition associated with PZR ambient heat losses and documented it in the corrective action program. At the time it was revealed that due to greater than anticipated ambient heat losses and non conservative capacity estimates from a 1972 calculation, the existing 126 kW of heating capacity available from the SSF DG would not be sufficient to overcome these ambient losses. As such, if called upon, the ability of the SSF to maintain RCS pressure control and natural circulation, utilizing the PZR heaters, would have been challenged.
Although an event that challenged this system has not occurred at the station, it is reasonable to assume that this condition has existed since initial SSF operation in 1986 and Page 1
has similarly affected all three Oconee Units. Additionally, the applicable SSF abnormal operating procedures in-use at the time of discovery did not provide adequate guidance to the operators on how to appropriately respond to this type of condition.
In addition to this condition being reported via 10 CFR 50.72 and 50.73 criteria, several corrective actions are planned or have been implemented, specifically:
- 1) The abnormal procedure used for SSF operation during postulated events to provide guidance for maintaining stable shutdown conditions with the RCS system water solid was revised,
- 2) An improved heat loss calculation was performed that addressed the heat load capacity deficiencies from the previous calculation,
- 3) By modification, additional heater capacity will be added to the SSF DG, and
- 4) Evaluate options to repair and/or upgrade the PZR insulation.
Description of the Technical Specification Change and Technical Justification The proposed revision to TS will revise TS 3.10.1, SR 3.10.1.9 to require increasing the loading of the DG from 3000 kW to Ž 3280 kW. This loading increase is necessary to accommodate the additional PZR heater capacity required as a result of the PZR ambient heat loss condition. The proposed change also includes a revision of the current capacity number from an allowable value, i.e, includes instrument error, to an analytical limit that does not. This change is necessary since it is the TS convention that values not contain instrument errors.
The ONS Updated Final Safety Analysis Report states that the SSF Power System is provided with standby power from a dedicated DG. This SSF DG is rated for continuous operation at 3500 kW, 0.8 pf, and 4160 VAC.
A calculation was completed that successfully verified both the capacity and capability of the SSF electrical power system to support the required loads under worst case design basis conditions. It evaluated the SSF electrical system adequacy under safe shutdown conditions while the system is Page 2
isolated and supplied by the offsite power system or the SSF diesel generator. Conservative conditions, such as motors operating at rated horsepower, space/duct heaters operating at 100% capacity and sump and other intermittent loads all operating at rated horsepower, were applied.
The following support system calculations were also revised based on the increase in SSF DG loading from the additional pressurizer heaters:
"* SSF service water system piping and components design temperature calculation.
"* SSF diesel jacket water and SSF lube oil heat exchangers maximum operating temperature limits calculation.
"* SSF service water system inventory and supply water temperature calculation.
In addition, an assessment of SSF HVAC calculations revealed that increases in SSF HVAC load due to the increase in diesel load would be negligible.
Based on these results, it was concluded that the increase in SSF DG load would be acceptable and that no new or different operator actions would be required as a result of this change. Although some decrease in design margins will result due to the increased load, the diesel will continue to operate below the DG's 3500 KW design rated load.
In summary, the proposed change to SR 3.10.1.9 to increase the DG loading from Ž 3000 to 2 3280 kW is necessary and technically justifiable. The proposed change is part of a effort to resolve a design deficiency and thus, increases assurance that the equipment will be able to perform as designed.
Page 3
ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION
Attachment 4 No Significant Hazards Consideration Pursuant to 10 CFR 50.91, Duke Power Company (Duke) has made the determination that this amendment request involves a No Significant Hazards Consideration by applying the standards established by the NRC regulations in 10 CFR 50.92. This ensures that operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated:
No. This change revises the loading of the Standby Shutdown Facility (SSF) Diesel Generators (DG) to Ž 3280 kW. The design rating of the DG is currently 3500 kW.
Since the proposed loading is within the design rating already evaluated, this proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
(2) Create the possibility of a new or different kind of accident from any kind of accident previously evaluated:
No. As stated above, the proposed revision revises the DG loading to an analytical value that is within the equipment's design limit. Applicable load and support system calculations have been revised and results have shown that the increase does not adversely affect the ability of the SSF diesel generator or SSF to perform its intended safety function. Additionally, this change is bounded by all of the existing accidents and does not create the possibility of a new or different kind of accident from any kind of accident previously evaluated.
(3) Involve a significant reduction in a margin of safety.
No. The proposed change does not adversely affect any plant safety limits, set points, or design parameters.
The change also does not adversely affect the fuel, fuel cladding, Reactor Coolant System, or containment integrity. Therefore, the proposed change does not involve a reduction in a margin of safety.
Duke has concluded, based on the above, that there are no significant hazards considerations involved in this amendment request.
ATTACHMENT 5 ENVIRONMENTAL ASSESSMENT
ATTACHMENT 5
, Environmental Assessment Pursuant to 10 CFR 51.22(b), an evaluation of the license amendment request (LAR) has been performed to determine whether or not it meets the criteria for categorical exclusion set forth in 10 CFR 51.22(c)9 of the regulations.
The LAR does not involve:
- 1) A significant hazards consideration.
This conclusion is supported by the determination of no significant hazards contained in Attachment 4.
- 2) A significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
This LAR will not significantly change the types or amounts of any effluents that may be released offsite.
- 3) A significant increase in the individual or cumulative occupational radiation exposure.
This LAR will not increase the individual or cumulative occupational radiation exposure.
In summary, this LAR meets the criteria set forth in 10 CFR 51.22 (c)9 of the regulations for categorical exclusion from an environmental impact statement.