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Category:Letter
MONTHYEARIR 05000269/20240032024-10-31031 October 2024 Integrated Inspection Report 05000269/2024003 and 05000270/2024003 and 05000287/2024003 (2) ML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24297A6172024-10-11011 October 2024 PCA Letter to NRC Oconee Hurricane Helene ML24269A0912024-10-0909 October 2024 Request for Withholding Information from Public Disclosure ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation 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 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification 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 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr 05000270/LER-2023-001, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee2024-02-29029 February 2024 Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee 05000287/LER-2023-002, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications2024-02-29029 February 2024 Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24019A1442024-02-13013 February 2024 Letter to Reid Nelson, Executive Director, Achp; Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24011A1532024-02-13013 February 2024 Letter to Tracy Watson EPA-Oconee Nuclear Sta, Unites 1, 2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, SHPO; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML24011A1482024-02-13013 February 2024 Letter to Steven M. Snider-Oconee Nuclear Sta, Unites 1,2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staff’S 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) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 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 2024-08-26
[Table view] Category:Technical Specification
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 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-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-21-0005, 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 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations 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-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-19-0006, 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-18-0282, Technical Specification Bases Changes2019-06-26026 June 2019 Technical Specification Bases Changes RA-18-0281, Technical Specification Bases Changes2019-06-25025 June 2019 Technical Specification Bases Changes 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 ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes 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-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 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-2017-019, Technical Specification Bases Change 2015-092017-02-23023 February 2017 Technical Specification Bases Change 2015-09 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 ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change2016-08-0404 August 2016 Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change ONS-2016-059, Technical Specification Bases Changes2016-07-11011 July 2016 Technical Specification Bases Changes RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ONS-2016-049, Technical Specification Bases Change2016-06-0606 June 2016 Technical Specification Bases Change ONS-2016-029, Technical Specification (TS) Bases Change2016-03-29029 March 2016 Technical Specification (TS) Bases Change ONS-2016-009, Technical Specification (TS) Bases Change2016-02-0909 February 2016 Technical Specification (TS) Bases Change ML16028A1912016-01-20020 January 2016 Technical Specification Base Change ONS-2015-106, Technical Specification (TS) Bases Change2015-10-26026 October 2015 Technical Specification (TS) Bases Change 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 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 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 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 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 ONS-2015-069, Technical Specification (TS) Bases Change2015-06-23023 June 2015 Technical Specification (TS) Bases Change 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-2015-057, Technical Specification (TS) Bases Changes2015-05-18018 May 2015 Technical Specification (TS) Bases Changes ONS-2015-033, Technical Specification (TS) Bases Change2015-03-18018 March 2015 Technical Specification (TS) Bases Change ONS-2015-006, Technical Specification (TS) Bases Change2015-01-29029 January 2015 Technical Specification (TS) Bases Change ONS-2014-145, Submittal of Technical Specification Bases Change2014-11-20020 November 2014 Submittal of Technical Specification Bases Change ONS-2014-103, Technical Specification (TS) Bases Change2014-07-23023 July 2014 Technical Specification (TS) Bases Change 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-2014-093, Technical Specification (TS) Bases Change2014-07-10010 July 2014 Technical Specification (TS) Bases Change ONS-2014-079, Submittal of Technical Specification (TS) Bases Change2014-06-0303 June 2014 Submittal of Technical Specification (TS) Bases Change ONS-2014-064, Technical Specification (TS) Bases Change2014-05-12012 May 2014 Technical Specification (TS) Bases Change ONS-2014-031, Technical Specification (TS) Bases Change2014-03-0404 March 2014 Technical Specification (TS) Bases Change ONS-2014-012, Submittal of Technical Specification Bases Change2014-02-0303 February 2014 Submittal of Technical Specification Bases Change ML13357A6742014-01-0808 January 2014 Issuance of Amendments Regarding the Temporary Technical Specification Change to Extend the Completion Time for an Inoperable Keowee Hydro Unit (TAC ME9021, ME9022, and ME9023) ONS-2013-006, Technical Specification Bases Change2013-11-13013 November 2013 Technical Specification Bases Change ML13234A3362013-08-0808 August 2013 Technical Specification Bases Change 2024-07-29
[Table view] Category:Bases Change
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 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-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-21-0005, 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-19-0039, 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-18-0282, Technical Specification Bases Changes2019-06-26026 June 2019 Technical Specification Bases Changes RA-18-0281, Technical Specification Bases Changes2019-06-25025 June 2019 Technical Specification Bases Changes 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 ONS-2018-013, Technical Specification Bases Changes2018-02-22022 February 2018 Technical Specification Bases Changes ONS-2017-050, Technical Specification Bases Change 2017-042017-07-21021 July 2017 Technical Specification Bases Change 2017-04 ONS-2017-052, Technical Specification Bases Change 2017-032017-07-20020 July 2017 Technical Specification Bases Change 2017-03 ONS-2017-043, Technical Specification Bases Change 2017-012017-07-20020 July 2017 Technical Specification Bases Change 2017-01 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-2017-019, Technical Specification Bases Change 2015-092017-02-23023 February 2017 Technical Specification Bases Change 2015-09 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 ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change2016-08-0404 August 2016 Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change ONS-2016-059, Technical Specification Bases Changes2016-07-11011 July 2016 Technical Specification Bases Changes RA-16-0007, Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process2016-06-23023 June 2016 Duke Energy Carolinas, LLC, Application to Revise TS to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability Using the Consolidated Line Item Improvement Process ONS-2016-049, Technical Specification Bases Change2016-06-0606 June 2016 Technical Specification Bases Change ONS-2016-029, Technical Specification (TS) Bases Change2016-03-29029 March 2016 Technical Specification (TS) Bases Change ONS-2016-009, Technical Specification (TS) Bases Change2016-02-0909 February 2016 Technical Specification (TS) Bases Change ML16028A1912016-01-20020 January 2016 Technical Specification Base Change ONS-2015-106, Technical Specification (TS) Bases Change2015-10-26026 October 2015 Technical Specification (TS) Bases Change 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 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 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 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 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 ONS-2015-069, Technical Specification (TS) Bases Change2015-06-23023 June 2015 Technical Specification (TS) Bases Change 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-2015-057, Technical Specification (TS) Bases Changes2015-05-18018 May 2015 Technical Specification (TS) Bases Changes ONS-2015-033, Technical Specification (TS) Bases Change2015-03-18018 March 2015 Technical Specification (TS) Bases Change ONS-2015-006, Technical Specification (TS) Bases Change2015-01-29029 January 2015 Technical Specification (TS) Bases Change ONS-2014-145, Submittal of Technical Specification Bases Change2014-11-20020 November 2014 Submittal of Technical Specification Bases Change ONS-2014-103, Technical Specification (TS) Bases Change2014-07-23023 July 2014 Technical Specification (TS) Bases Change 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-2014-093, Technical Specification (TS) Bases Change2014-07-10010 July 2014 Technical Specification (TS) Bases Change ONS-2014-079, Submittal of Technical Specification (TS) Bases Change2014-06-0303 June 2014 Submittal of Technical Specification (TS) Bases Change ONS-2014-064, Technical Specification (TS) Bases Change2014-05-12012 May 2014 Technical Specification (TS) Bases Change ONS-2014-031, Technical Specification (TS) Bases Change2014-03-0404 March 2014 Technical Specification (TS) Bases Change ONS-2014-012, Submittal of Technical Specification Bases Change2014-02-0303 February 2014 Submittal of Technical Specification Bases Change ONS-2013-006, Technical Specification Bases Change2013-11-13013 November 2013 Technical Specification Bases Change ML13234A3362013-08-0808 August 2013 Technical Specification Bases Change ML13211A2832013-07-24024 July 2013 Technical Specification Bases (Tsb) Change ML12333A3152012-11-27027 November 2012 Technical Specification Bases (Tsb) Changes ML12319A4792012-11-12012 November 2012 Technical Specification Bases (Tsb) Changes 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.. ML12310A3822012-10-29029 October 2012 Technical Specification Bases (Tsb) Changes ML12243A4012012-08-29029 August 2012 Technical Specification Bases (Tsb) Change 2024-07-29
[Table view] |
Text
- f V Duke T. PRESTON GILLESPIE, JR.
Vice President VrEnergy Oconee Nuclear Station Duke Energy ON01 VP / 7800 Rochester Hwy.
Seneca, SC 29672 864-873-4478 864-873-4208 "ax T.Gillespie@duke-energy.com August 29, 2012 U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station Docket Numbers 50-269, 50-270, and 50-287 Technical Specification Bases (TSB) Change On August 1, 2012, Station Management approved a revision to TSB 3.7.1, Main Steam Relief Valves, to clearly document in the Bases that the MSRVs may be considered OPERABLE following maintenance provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This clarifies that operation can proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
Attachment 1 contains the new TSB pages. Attachment 2 contains the marked up version of the TSB pages.
If additional information is needed, please contact Sandra Severance at (864)873-3466.
Sincerely, T. Preston Gillespie, Jr.
Vice President Oconee Nuclear Station RGJ/rgj Attachments www. duke-energy,comr
U. S. Nuclear Regulatory Commission August 29, 2012 Page 2 cc: Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. John P. Boska, Project Manager (By electronic mail only)
U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation One White Flint North, M/S O-8G9A 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector Oconee Nuclear Station Ms. Susan E. Jenkins, Manager Radioactive & Infectious Waste Management SC Dept. of Health and Env. Control 2600 Bull St.
Columbia, SC 29201
Attachment #1 Revised TSB
TS Bases revision Remove Page Insert Page B 3.7.1-1 B 3.7.1-1 B 3.7.1-2 B 3.7.1-2 B 3.7.1-3 B 3.7.1-3 B 3.7.1-4
MSRVs B 3.7.1 B 3.7 PLANT SYSTEMS B 3.7.1 Main Steam Relief Valves (MSRVs)
BASES BACKGROUND The primary purpose of the MSRVs is to provide overpressure protection for the secondary system. The MSRVs also provide protection against overpressurizing the reactor coolant pressure boundary (RCPB) by providing a heat sink for removal of energy from the Reactor Coolant System (RCS) if the preferred heat sink, provided by the Condenser and Circulating Water System, is not available.
Eight MSRVs are located on each main steam header, outside containment as described in the UFSAR, Section 10.3 (Ref. 1). The MSRV rated capacity passes the full steam flow at 114% RTP with the valves full open.
This meets the requirements of the ASME Code,Section III (Ref. 2). The MSRV design includes staggered setpoints, (Ref. 1) so that only the needed number of valves will actuate. Staggered setpoints reduce the potential for valve chattering because of insufficient steam pressure to fully open the valves.
APPLICABLE The design basis of the MSRVs (Ref. 2) is to limit secondary system SAFETY ANALYSES pressure to <_110% of design pressure when passing 105% of design steam flow. This design basis is sufficient to cope with any anticipated transient or accident considered in the accident and transient analysis.
The events that challenge the relieving capacity of the MSRVs, and thus RCS pressure, are those characterized as decreased heat removal or increased heat addition events. MSRV relief capacity is utilized in the UFSAR (Ref. 3 and Ref. 4) for mitigation of the following events:
- a. Loss of main feedwater;
- b. Steam line break;
- c. Steam generator tube rupture;
- d. Rod withdrawal at rated power; and
- e. Loss of Electric Load.
OCONEE UNITS 1, 2, & 3 B 3.7. 1-1 BASES REVISION DATED 08/08/12 I
MSRVs B 3.7.1 BASES APPLICABLE The MSRVs satisfy Criterion 3 of 10 CFR 50.36, (Ref. 5).
SAFETY ANALYSIS (continued)
LCO The MSRVs are provided to prevent overpressurization as discussed in the Applicable Safety Analysis section of these Bases. The LCO requires sixteen MSRVs, eight on each main steam line, to be OPERABLE to ensure compliance with the ASME Code following accidents and transients initiated at full power. Operation with less than a full complement of MSRVs is not permitted. To be OPERABLE, lift setpoints must remain within limits, specified in the UFSAR.
The safety function of the MSRVs is to open, relieve steam generator overpressure, and reseat when pressure has been reduced.
OPERABILITY of the MSRVs requires periodic surveillance testing in accordance with the Inservice Testing Program.
The lift settings correspond to ambient conditions of the valve at nominal operating temperature and pressure.
This LCO provides assurance that the MSRVs will perform the design safety function.
APPLICABILITY In MODES 1, 2, and 3, the MSRVs must be OPERABLE to prevent overpressurization of the main steam system.
In MODES 4 and 5, there is no credible transient requiring the MSRVs.
The steam generators are not normally used for heat removal in MODES 5 and 6, and thus cannot be overpressurized. There is no requirement for the MSRVs to be OPERABLE in these MODES.
ACTIONS A.1 and A.2 With one or more MSRVs inoperable, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in MODE 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
OCONEE UNITS 1, 2, & 3 B 3.7.1-2 BASES REVISION DATED 08/08/12 I
MSRVs B 3.7.1 BASES (continued)
SURVEILLANCE SR 3.7.1.1 REQUIREMENTS This SR verifies the OPERABILITY of the MSRVs by the verification of MSRV lift setpoints in accordance with the Inservice Testing Program. The safety and relief valve tests are performed in accordance with ANSI/ASME Code (Ref. 6) and include the following for MSRVs:
- a. Visual examination;
- b. Seat tightness determination;
- c. Setpoint pressure determination (lift setting);
- d. Compliance with owner's seat tightness criteria; and
- e. Verification of the balancing device integrity on balanced valves.
The ANSI/ASME Standard requires the testing of all valves every 5 years, with a minimum of 20% of the valves tested every 24 months.
This SR is modified by a Note that states the surveillance is only required to be performed in MODES 1 and 2. This note allows entry into and operation in MODE 3 prior to performing the SR, provided there is no evidence that the equipment is otherwise believed to be incapable of performing its function. Also, the guidance in the TS Bases for SR 3.0.1 states that equipment may be considered OPERABLE following maintenance provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This allows operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
For example, the mode change provisions described above specifically applies to scenarios where maintenance on MSRVs is performed below the mode of applicability for LCO 3.7.1, testing has been satisfactorily completed to the extent possible, and the equipment is believed capable of performing its function. The mode change provisions permit entry into Mode 3 in order to test and adjust the set pressure, as necessary, to satisfy SR 3.7.1.1 prior to entry into Mode 2.
The MSRVs may be either bench tested or tested in situ at hot conditions using an assist device to simulate lift pressure. If the MSRVs are not tested at hot conditions, the lift setting pressure must be corrected to ambient conditions of the valve at operating temperature and pressure.
OCONEE UNITS 1, 2, & 3 B] 3.7.1-3 BASES REVISION DATED 08/08/12 I
MSRVs B 3.7.1 BASES (continued)
REFERENCES 1. UFSAR, Section 10.3.
- 2. ASME, Boiler and Pressure Vessel Code,Section III, Article NC-7000, Class 2 Components.
- 3. UFSAR, Chapter 15.
- 4. UFSAR, Section 10.3.3.
- 5. 10 CFR 50.36.
- 6. ANSI/ASME Boiler And Pressure Vessel Code, Section Xl.
OCONEE UNITS 1, 2, & 3 B 3.7.1-4 BASES REVISION DATED 08/08/12 I
Attachment #2 Markup of current TSB
MSRVs B 3.7.1 B 3.7 PLANT SYSTEMS B 3.7.1 Main Steam Relief Valves (MSRVs)
BASES BACKGROUND The primary purpose of the MSRVs is to provide overpressure protection for the secondary system. The MSRVs also provide protection against overpressurizing the reactor coolant pressure boundary (RCPB) by providing a heat sink for removal of energy from the Reactor Coolant System (RCS) if the preferred heat sink, provided by the Condenser and Circulating Water System, is not available.
Eight MSRVs are located on each main steam header, outside containment as described in the UFSAR, Section 10.3 (Ref. 1). The MSRV rated capacity passes the full steam flow at 114% RTP with the valves full open.
This meets the requirements of the ASME Code,Section III (Ref. 2). The MSRV design includes staggered setpoints, (Ref. 1) so that only the needed number of valves will actuate. Staggered setpoints reduce the potential for valve chattering because of insufficient steam pressure to fully open the valves.
APPLICABLE The design basis of the MSRVs (Ref. 2) is to limit secondary system SAFETY ANALYSES pressure to < 110% of design pressure when passing 105% of design steam flow. This design basis is sufficient to cope with any anticipated transient or accident considered in the accident and transient analysis.
The events that challenge the relieving capacity of the MSRVs, and thus RCS pressure, are those characterized as decreased heat removal or increased heat addition events. MSRV relief capacity is utilized in the UFSAR (Ref. 3 and Ref. 4) for mitigation of the following events:
- a. Loss of main feedwater;
- b. Steam line break;
- c. Steam generator tube rupture;
- d. Rod withdrawal at rated power; and
- e. Loss of Electric Load.
OCONEE UNITS 1, 2, & 3 B 3.7.1-1 BASES REVISION DAT xIxx/xx
MSRVs B 3.7.1 BASES APPLICABLE The MSRVs satisfy Criterion 3 of 10 CFR 50.36, (Ref. 5).
SAFETY ANALYSIS (continued)
LCO The MSRVs are provided to prevent overpressurization as discussed in the Applicable Safety Analysis section of these Bases. The LCO requires sixteen MSRVs, eight on each main steam line, to be OPERABLE to ensure compliance with the ASME Code following accidents and transients initiated at full power. Operation with less than a full complement of MSRVs is not permitted. To be OPERABLE, lift setpoints must remain within limits, specified in the UFSAR.
The safety function of the MSRVs is to open, relieve steam generator overpressure, and reseat when pressure has been reduced.
OPERABILITY of the MSRVs requires periodic surveillance testing in accordance with the Inservice Testing Program.
The lift settings correspond to ambient conditions of the valve at nominal operating temperature and pressure.
This LCO provides assurance that the MSRVs will perform the design safety function.
APPLICABILITY In MODES 1, 2, and 3, the MSRVs must be OPERABLE to prevent overpressurization of the main steam system.
In MODES 4 and 5, there is no credible transient requiring the MSRVs.
The steam generators are not normally used for heat removal in MODES 5 and 6, and thus cannot be overpressurized. There is no requirement for the MSRVs to be OPERABLE in these MODES.
ACTIONS A.1 and A.2 With one or more MSRVs inoperable, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and in MODE 4 within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
OCONEE UNITS 1, 2, & 3 B 3.7.1-2 BASES REVISION DA D 102/20
.xx~xx
MSRVs B 3.7.1 BASES (continued)
SURVEILLANCE SR 3.7.1.1 REQUIREMENTS This SR verifies the OPERABILITY of the MSRVs by the verification of MSRV lift setpoints in accordance with the Inservice Testing Program. The safety and relief valve tests are performed in accordance with ANSI/ASME Code (Ref. 6) and include the following for MSRVs:
- a. Visual examination;
- b. Seat tightness determination;
- c. Setpoint pressure determination (lift setting);
- d. Compliance with owner's seat tightness criteria; and
- e. Verification of the balancing device integrity on balanced valves.
The ANSI/ASME Standard requires the testing of all valves every 5 years, SInsert A -ýih inimum of 20% of the valves tested every 24 months.
This SR is rneii* blnlt' tlhatl a-ll,^ow eRt{'f i*÷,' ,-Rd,- ,Grp -,*÷;-tiG MODE 3 ...... .............. .... The MSRVs may be either bench tested or tested in situ at hot conditions using an assist device to simulate lift pressure. If the MSRVs are not tested at hot conditions, the lift setting pressure must be corrected to ambient conditions of the valve at operating temperature and pressure.
REFERENCES 1. UFSAR, Section 10.3.
- 2. ASME, Boiler and Pressure Vessel Code,Section III, Article NC-7000, Class 2 Components.
- 3. UFSAR, Chapter 15.
- 4. UFSAR, Section 10.3.3.
- 5. 10 CFR 50.36.
- 6. ANSI/ASME Boiler And Pressure Vessel Code,Section XI.
OCONEE UNITS 1, 2, & 3 B 3.7.1-3 BASES REVISION D I 4 1 . .
INSERT A:
This SR is modified by a Note that states the surveillance is only required to be performed in MODES 1 and 2. This note allows entry into and operation in MODE 3 prior to performing the SR, provided there is no evidence that the equipment is otherwise believed to be incapable of performing its function. Also, the guidance in the TS Bases for SR 3.0.1 states that equipment may be considered OPERABLE following maintenance provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed.
For example, the mode change provisions described above will specifically apply to scenarios where maintenance on MSRVs is performed below the mode of applicability for LCO 3.7.1, testing has been satisfactorily completed to the extent possible, and the equipment is believed capable of performing its function. The mode change provisions permit entry into Mode 3 in order to test and adjust the set pressure, as necessary, to satisfy SR 3.7.1.1 prior to entry into Mode 2.