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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: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. MD5156 - MD5162) ML0803200712008-02-21021 February 2008 Technical Specifications, Issuance of Amendments Regarding Use of Fiber-Reinforced Polymer (FRP) ML0735506292007-12-19019 December 2007 Tech Spec Pages for Amendments 359, 361 & 360, Regarding Removal of the Gaseous Radioactive Monitor from the Technical Specifications ML0732503892007-11-14014 November 2007 Technical Specifications for Oconee, Units 1, 2, and 3, Issuance of Amendments Regarding the Flood Protection Measures for the Auxiliary Building ML0709303722007-04-0202 April 2007 Technical Specifications, Issuance of Amendments Regarding Steam Generator Tube Integrity ML0630601812006-10-26026 October 2006 Technical Specifications, Correction to Amendment 350, 352, & 351 ML0628404622006-10-0303 October 2006 Tech Spec Pages for Amendments 354, 356 and 355 Regarding AC Sources-Operating ML0627201112006-09-27027 September 2006 License Amendment Request Applicable to Technical Specification 3.8.1, AC Sources - Operating, License Amendment Request (LAR) 2006-16 ML0619205882006-07-11011 July 2006 Technical Specifications, Issuance of Amendments Regarding Eliminate Out-Of-Date Requirements for Keowee Hydro Units, MC7318, MC7319, MC7320 ML0617103042006-06-15015 June 2006 Tech Spec Pages for Amendments 351, 353 and 352 Regarding Criticality Requirements for Loading and Unloading Dry Spent Fuel Storage Canisters in the Spent Fuel Pool ML0611600142006-05-0404 May 2006 Tech Spec Pages for Amendment 350 Replacement of Reactor Building Emergency Sump Suction Inlet Trash Racks and Screens with Strainers ML0610805002006-04-11011 April 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity and Other Administrative Changes ML0610804092006-04-11011 April 2006 Application for Technical Specification Change to Add/Revise LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0607303802006-03-15015 March 2006 License Page 8, Revised Design Basis Threat ML0607200302006-03-0101 March 2006 License Amendment Request to Reconcile 10 CFR 50 and 10 CFR 72 Criticality Requirements for Loading and Unloading Dry Spent Fuel Storage Canisters in the Spent Fuel Pool, License Amendment Request No. 2006-009 2024-07-29
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RONALD A JONES
_Duke Vice President Mkwftwere Oconee Nuclear Site Duke Power ONOIVP / 7800 Rochester Hwy.
Seneca, SC 29672 864 885 3158 864 885 3564 fax August 21, 2005 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Duke Energy Corporation Oconee Nuclear Station Units 1, 2, and 3 Docket Nos. 50-269, 270, and 287 License Amendment Request Applicable to Technical Specification 3.8.1, AC Sources - Operating Technical Specification Change (TSC) 2005-07 In accordance with the provisions of 10 CFR 50.90, Duke Energy Corporation (Duke) is submitting a License Amendment Request (LAR) for the Facility Operating Licenses and Technical Specifications (TS) for Oconee Nuclear Station. The proposed amendment requests that the Completion Time (CT) of Technical Specification (TS) 3.8.1, AC Sources - Operating, Required Action (RA) C.2.1 be extended to allow for a total completion time of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. This is a one time change that will expire at 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br /> on August 27, 2005.
Technical Specification Limiting Condition for Operation (LCO) 3.8.1, Condition C.2.1, was entered for all three Oconee Units beginning on Saturday, August 20, 2005 at 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br />. The condition was initially entered for Keowee Hydro Unit 2 (KHU #2) testing. Shortly thereafter, KHU #2 experienced an emergency lockout condition. While logged into LCO 3.8.1, required action (RA) C.1 commenced that verified, within the required completion time (CT), the operability of the remaining KHU Unit 1 and underground power path.
Pursuant to LCO 3.8.1, RA C.2.1, if the inoperable KHU Unit is not restored by 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br /> on Tuesday, August 23, 2005, Condition M applies and all three Oconee Units must be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 5 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />. This proposed change seeks additional time to extend the CT for RA C.2.1 in order to continue troubleshooting efforts, perform repairs, and to return the unit to service.
Attachment 1 provides the retyped TS. Attachment 2 provides the existing TS page marked up to show the proposed change. Attachment 3 provides the technical justification of the change.
Attachments 4 and 5 provide the No Significant Hazards Consideration and the Environmental Impact Analysis, respectively.
Implementation of this proposed TS change to the TS will not require revision to the Oconee Updated Final Safety Analysis Reports (UFSAR). Duke is requesting NRC review and approval of this LAR by close of business August 22, 2005 with implementation to occur immediately.
www.dukepower.com rnO
U. S. Nuclear Regulatory Commission August 21, 2005 Page 2 In accordance with Duke administrative procedures and the Quality Assurance Program Topical Report, the changes contained in this proposed amendment have been reviewed and approved by the Oconee Plant Operations Review Committee. This proposed amendment has also been reviewed and approved by the Duke Nuclear Safety Review Board.
Pursuant to 10 CFR 50.91, a copy of this amendment request is being sent to the designated official of the State of South Carolina.
Inquiries on this matter should be directed to Stephen C. Newman at 864-885-4388.
Very truurs, R. Jones, Vice President Oconee Nuclear Site
U. S. Nuclear Regulatory Commission August 21, 2005 Page 3 xc Nv/Attachments:
W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 L. N. Olshan (Addressee Only)
NRC Senior Project Manager (ONS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 S. Peters NRC Project Manager U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 M. E. Shannon Senior Resident Inspector (ONS)
U. S. Nuclear Regulatory Commission Oconee Nuclear Site Henry Porter Division of Radioactive Waste Management South Carolina Bureau of Land and Waste Management 2600 Bull Street Columbia, SC 29201
U. S. Nuclear Regulatory Commission August 21, 2005 Page 4 R. A. Jones, affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
R. A. Jnes, ice resident Subscribed and sworn to me: 4 1
,; - rIDate Notary Public My commission expires:'1 Ž. ( OI Date SEAL
U. S. Nuclear Regulatory Commission August 21, 2005 Page 5 bxc w/Attachments:
R. L. Gill L. A. Keller C. J. Thomas T. P. Gillespie S. L. Batson T. A. Ledford D. J. Herrick M. J. Barrett NRIA File/ELL Oconee Master File - ON03DM (File OS 801.01)
ATTACHMENT 1 REVISED TECHNICAL SPECIFICATIONS Remove Page Insert Page 3.8.1-3 3.8.1-3
AC Sources - Operating 3.8.1 ACTIONS (continued)
CONDITION I REQUIRED ACTION COMPLETION TIME C. KHU or its required C.1 Perform SR 3.8.1.3 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if not performed in overhead emergency OPERABLE KHU. previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> power path inoperable due to reasons other AND than Condition A.
Once per 7 days thereafter AND C.2.1 Restore the KHU and ------------ NOTE-------------
its required overhead An additional 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> emergency power path can be added to the to OPERABLE status. following completion times. This expires on August 27, 2005 @1058 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from discovery OR of inoperable KHU C.2.2.1 Energize both standby 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> buses from LCT via isolated power path. AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from subsequent discovery of deenergized standby bus AND C.2.2.2 Suspend KHU 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> generation to grid except for testing.
AND (continued)
OCONEE UNITS 1, 2, & 3 3.8.1 -3 Amendment Nos. xxx, xxx, & xxx I
ATTACHMENT 2 MARKUP OF TECHNICAL SPECIFICATIONS
AC Sources - Operating 3.8.1 ACTIONS (continued)
CONDITION I REQUIRED ACTION J COMPLETION TIME C. KHU or its required C.1 Perform SR 3.8.1.3 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if not performed in overhead emergency OPERABLE KHU. previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> power path inoperable due to reasons other AND than Condition A.
Once per 7 days thereafter 2.1 Restore the KHU and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> its required overhead emergency power path AND eAn a 4c&+tc4 heq.r I to OPERABLE status.
(cc~k He- X4,t *-e- . 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from discovery of inoperable KHU
- -- 1 -
OR C.2.2.1 Energize both standby 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> buses from LCT via isolated power path. AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from subsequent discovery of deenergized standby bus AND C.2.2.2 Suspend KHU 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> generation to grid except for testing.
AND (continued)
OCONEE UNITS 1, 2, & 3 3.8.1 -3 Amendment Nos. 300,300, & 300 -?
K x,4, XtYV f mW
ATTACHMENT 3 TECHNICAL JUSTIFICATION August 21, 2005 Page 2 ATTACHMENT 3 TECHNICAL JUSTIFICATION PURPOSE This purpose of this LAR is to obtain one-time NRC approval to extend the CT for TS 3.8.1 Condition C.2.1 in order to avoid an unplanned forced shutdown of all three Oconee Units and the potential safety consequences and operational risks associated with that action. Conservative risk analysis fully supports the requested additional time. Due to the emergency nature of this LAR, an expedited one-time TS extension is being requested.
The PRA analysis has been conducted by assuming the Keowee unit aligned to the overhead path is failed. Two cases are considered. First, the Keowee unit aligned to the underground path is assumed to not be affected by a similar component failure and its failure probability is the normal random failure probability. Second, the Keowee unit aligned to the underground path is assumed to be potentially affected by a similar component failure. A common cause multiplier of 0.1 is assumed as the failure probability of the underground unit.
In both cases the risk results support a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> extension of the completion time.
BACKGROUND Technical Specification Limiting Condition for Operation (LCO) 3.8.1, Condition C.2.1, was entered for all three Oconee Units beginning on Saturday, August 20, 2005 at 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br />. The condition was initially entered for Keowee Hydro Unit 2 (KHU #2) testing. Shortly thereafter, KHU #2 experienced an emergency lockout condition. While logged into LCO 3.8.1, required action (RA) C. 1 commenced that verified, within the required completion time (CT), the operability of the remaining KHU Unit 1 and underground power path.
Pursuant to LCO 3.8.1, RA C.2.1, if the inoperable KHU Unit is not restored by 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br /> on Tuesday, August 23, 2005, Condition M applies and all three Oconee Units must be in MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 5 within 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />. This proposed change seeks additional time to extend the CT for RA C.2.1 in order to continue troubleshooting efforts, perform repairs, and to return the unit to service. At the time of this submittal, the root cause of the condition has not been determined; however, a unit threat team has been formed and is working around the clock to determine the cause and subsequent repairs to prevent recurrence.
A similar event occurred to KHU # 2 on August 10, 2005. During a normal start on that day, an emergency lockout signal was received. LCO 3.8.1 RA C.2.1 was entered at time of lockout.
Exhaustive troubleshooting singled out a Bus Differential Relay as the most probable cause of the event. This relay was replaced with a refurbished and tested (at the manufacturer's facility in Coral Gables, Florida) spare, and post-maintenance testing was determined to be acceptable. At August 21, 2005 Page 3 that time, there was reasonable assurance that this relay had caused the lockout condition.
Approximately 10 start cycles of KHU # 2 have taken place since that time with no further lockout indications until the August 20, 2005 event.
DESCRIPTION OF PROPOSED CHANGE The proposed amendment requests that the CT for TS LCO 3.8.1, "AC Sources - Operating,"
required action (RA) C.2.1 be extended 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to provide additional time to effect repairs on KHU Q2. This CT will be revised to restore the KHU, along with its required overhead emergency power path, to OPERABLE status within 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> from the time of initial TS LCO 3.8.1 entry. A "Note" will also be added to document that this is a one-time change expiring on August 27, 2005 at 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br />.
JUSTIFICATION Revision 3 of the Oconee Probabilistic Risk Assessment fault tree and databases were used to perform a risk evaluation to justify the extension from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. This evaluation was documented in Duke Calculation OSC-8813, "NOED Risk Assessment for the Keowee Unit 2 Lockout on 8/10/2005," created by the Corporate PRA Group. The intent of this original calculation was to support a NOED request for a similar lockout event that occurred on KHU #2 August 10, 2005 as described previously. OSC-8813 was approved and issued during the week of August 15. The NOED was not required since KHU #2 was restored to operable status prior to expiration of the CT. Since the August 20, 2005 lockout event is essentially identical to the previous event, assumptions and limitations are the same and the conclusions of this calculation remain valid to justify this TS change request.
Results and conclusions:
The ICCDP and ICLERP are estimated on a per day basis.
The upper bound ICCDP is (3.6E 3.5E-05)/0.9/365 = 3.OE-09/day.
The upper bound ICLERP is (2.OE 2.OE-06)/0.9/365 = 0/day.
From the NRC Inspection Manual Part 9900, the guidance is for the ICCDP and ICLERP to be less than 5E-07 and 5E-08 respectively.
Using the upper bound estimates the ICCDP is limiting and would justify an extension of approximately 166 days.
For the common cause case:
The upper bound ICCDP is (5.9E 3.5E-05)/0.9/365 = 7.3E-08/day.
The upper bound ICLERP is (2.3E 2.OE-06)/0.9/365 = 9.lE-10/day.
August 21, 2005 Page 4 Therefore, assuming common cause effects, using the upper bound estimates the ICCDP is limiting and would justify an extension of approximately 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />. For purposes of this TS revision, an extension of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> is being requested.
In summary, the requested 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> extension request would result in an ICCDP increase of 2.92E-07 and an ICLERP increase of 3.64E-09. For reference, although not a permanent change request, these values are well below the required ICCDP and ICLERF acceptance thresholds described in RG 1.174.
Bases for the extension:
The ICCDP and ICLERP have been conservatively evaluated to be 3.OE-09/day and 0/day.
respectively. These values would justify an additional 166 days of operation to restore Keowee Unit 2. If the impacts of common cause are considered, the ICCDP and ICLERP have been conservatively evaluated to be 7.3E-08/day and 9.lE-10/day respectively. These values would justify a total of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of operation to restore Keowee Unit 2. The core damage result is limiting. This result is judged to be conservative as many new cutsets containing previously unanalyzed combinations of human errors are present in the results. The human error probability is assumed to be 1.0 for those human actions not included in the dependency analysis, that is, complete dependency is assumed for the additional human actions in the cutset.
The dominant contributors to the CDF risk are Loss of Offsite Power (LOOP) initiated sequences. With Keowee Unit 2 unavailable, a station blackout results if Keowee Unit 1 and LCT also fail. Subsequent failure of the SSF leads to a seal LOCA with no injection capability available and results in core damage.
Additional risk reduction actions will be taken during the extension period.
The following items are not credited in the PRA evaluation but will be performed as additional risk reduction measures:
I. Pre-stage Operators at the SSF. To improve the reliability of the SSF which can maintain the plant in a safe condition completely independent of emergency power. This measure has not been included in the quantitative evaluation. However, an improvement in the operator response for manning the SSF would reduce the estimated CDF.
II. No high risk electrical work that could cause an Oconee trip. No planned high risk maintenance activities, that could cause a trip or render safety systems with mitigation functions unavailable, will be undertaken during the extension period.
III. Start a second LCT and maintain in hot idle conditions. During the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> extension period, a Lee Combustion Turbine (LCT) will be energizing the standby bus via an isolated power path. A second LCT is operating in standby. The third remaining LCT is also available and can be started and used to supply both standby buses should the August 21, 2005 Page 5 running LCT fail. To enhance unit availability, no major preventative maintenance work will be performed on the third LCT.
With a conservative assumption concerning common cause, a seven (7) day extension to the completion time can be supported.
External events are accounted for in the PRA model with the exception of the seismic events.
The seismic sequences typically involve failure of the switchyard power insulators and would not be sensitive to the unavailability of Keowee Unit 2. Seismic events that are important to the core damage frequency are of such magnitude that the switchyard and offsite power are lost. As such the overhead path, to which the unavailable Keowee unit is aligned, is also failed. This reduces the importance of the unit aligned to the overhead path. Additionally, the seismic results are rarely sensitive to the unavailability of a single component. The seismic contribution to the change in CDF is judged to be negligible compared to the results from the other initiating events.
ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION August 21, 2005 Page 2 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:
Response: No The request for enforcement discretion involves a one-time extension of the Completion Time for Required Action C.2.1 associated with restoring compliance with TS LCO 3.8.1.
The probability of an event occurring during the extended Completion Time of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> are the same as those that would occur during the existing 72-hour Completion Time; therefore, the probability of an accident previously evaluated is not significantly increased.
The consequences associated with extending the Completion Time to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> have been evaluated and results show only a minimal increase for a previously evaluated accident. In addition, the additional time to effect repairs to the KHU will permit Duke to avoid an unplanned forced shutdown of all three Oconee Units and the potential safety consequences and operational risks associated with that action.
There are no adverse impacts on containment integrity, radiological release pathways, fuel design, filtration systems, main steam relief valve set points, or radwaste systems. No new radiological release pathways are created.
As additional conservative measures, a Lee Combustion Turbine (LCT) will be energizing the standby bus via an isolated power path. A second LCT is operating in standby. The third remaining LCT is also available and can be started and used to supply both standby buses should the running LCT fail. Also, several risk reduction actions will be implemented to further reduce the risk impact during the extension period.
August 21, 2005 Page 3 (2) Create the possibility of a new or different kind of accident from any kind of accident previously evaluated:
Response: No The request for this one-time TS change involves an extension of the Completion Time for TS LCO 3.8.1, RA C.2.1, associated with restoring compliance with the LCO. The proposed change will not physically alter the present plant configuration nor adversely effect how the plant is currently operated. Also, measures previously specified in this submittal are in-place as additional risk minimizing actions; Consequently, this request 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.
Response: No Since the proposed change will not physically alter the present plant configuration nor adversely effect how the plant is currently operated, the proposed change does not adversely affect any plant safety limits, setpoints, or design parameters. The change also does not adversely affect the fuel, fuel cladding, Reactor Coolant System, or containment integrity. Also, measures previously specified in this submittal are in-place as additional risk minimizing actions. Therefore, the proposed change does not involve a reduction in a margin of safety.
Duke has concluded that, based on the above responses, that there are no significant hazards considerations involved in this amendment request.
ATTACHMENT 5 ENVIRONMENTAL ASSESSMENT August 21, 2005 Page 2 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.
The consequences of an event occurring during the extended Completion Time of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> are the same as those that would occur during the existing 72-hour Completion Time. Therefore, the probability or consequences of an accident previously evaluated is not significantly increased.
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 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.