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Category:Letter type:
MONTHYEAR2CAN072401, Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02)2024-07-19019 July 2024 Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) 0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply 0CAN062403, Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels2024-06-25025 June 2024 Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels 0CAN062402, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-06-0606 June 2024 Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 0CAN052401, – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 20232024-05-13013 May 2024 – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 2023 1CAN052401, Cycle 32 Core Operating Limits Report2024-05-0404 May 2024 Cycle 32 Core Operating Limits Report 2CAN042403, Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C2024-04-24024 April 2024 Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C 0CAN042402, Annual Occupational Radiation Exposure Report for 20232024-04-23023 April 2024 Annual Occupational Radiation Exposure Report for 2023 0CAN042401, Radioactive Effluent Release Report for the 2023 Calendar Year2024-04-15015 April 2024 Radioactive Effluent Release Report for the 2023 Calendar Year 2CAN042402, Special Report of Non-functional Main Steam Line Radiation Monitor2024-04-11011 April 2024 Special Report of Non-functional Main Steam Line Radiation Monitor 2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications2024-04-0404 April 2024 Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications 2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2024-07-08
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement 1CAN102101, SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2021-10-0606 October 2021 SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN092101, License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2021-09-30030 September 2021 License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections 2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2021-05-26026 May 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2021-05-26026 May 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 1CAN022102, Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2021-02-22022 February 2021 Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 0CAN022102, Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping2021-02-0808 February 2021 Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping 2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)2020-11-17017 November 2020 License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP) 2CAN092003, License Amendment Request, Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2020-09-24024 September 2020 License Amendment Request, Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions 1CAN072001, Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2020-07-21021 July 2020 Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 1CAN022001, License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2020-02-24024 February 2020 License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 1CAN012002, License Amendment Request: Revise Loss of Voltage Relay Allowable Values2020-01-24024 January 2020 License Amendment Request: Revise Loss of Voltage Relay Allowable Values 2CAN121903, License Amendment Request, Revise Control Element Assembly Drop Time2019-12-18018 December 2019 License Amendment Request, Revise Control Element Assembly Drop Time 2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations2019-12-16016 December 2019 License Amendment Request Technical Specification Deletions, Additions, and Relocations 1CAN101903, Supplement to License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2019-10-23023 October 2019 Supplement to License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 0CAN091901, Unit 2: License Amendment Request - Change in Implementation Date for Amendments 263 and 3142019-09-0505 September 2019 Unit 2: License Amendment Request - Change in Implementation Date for Amendments 263 and 314 2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-14322019-08-29029 August 2019 License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432 1CAN051901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2019-05-29029 May 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. 0CAN041904, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis2019-04-29029 April 2019 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis 1CAN031901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2019-03-25025 March 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 1CAN121801, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2018-12-19019 December 2018 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 2CAN121801, License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump2018-12-19019 December 2018 License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump 2CAN051801, License Renewal Pressurizer Surge Line and Safety Injection Nozzle Inspection2018-05-24024 May 2018 License Renewal Pressurizer Surge Line and Safety Injection Nozzle Inspection ML18094A1552018-03-29029 March 2018 Enclosures 2 - 6: Proposed EAL Technical Basis Document, NEI 99-01. Rev. 6., Proposed EAL Matrix Chart/Review Table and Supporting Referenced Document Pages 0CAN031801, Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62018-03-29029 March 2018 Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 1CAN031801, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-03-12012 March 2018 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) 2CAN121702, License Amendment Request Post-Accident Instrumentation Technical Specification Revision2017-12-14014 December 2017 License Amendment Request Post-Accident Instrumentation Technical Specification Revision 2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits2017-11-20020 November 2017 License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits 1CAN101701, License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves2017-10-0202 October 2017 License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML17268A2132017-09-21021 September 2017 ISFSI, River Bend Station Unit 1 & ISFSI, Waterford 3 Steam Electric Station & ISFSI, Grand Gulf Nuclear Station & ISFSI, Application for Order Approving Transfers of Licenses and Conforming License Amendments 2CAN081701, Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability.2017-08-14014 August 2017 Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability. 1CAN081701, Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability.2017-08-14014 August 2017 Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability. 2CAN071701, License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-14322017-07-17017 July 2017 License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432 1CAN071701, License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process2017-07-17017 July 2017 License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process 1CAN061701, Amendment 27 of the SAR, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2017-06-0707 June 2017 Amendment 27 of the SAR, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN041702, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line.2017-04-24024 April 2017 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line. 2CAN041702, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2017-04-24024 April 2017 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. 2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications2016-10-27027 October 2016 License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications 1CAN051602, Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-8052016-05-19019 May 2016 Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-805 2CAN031602, 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, and to Request an Alternative to the Asme..2016-03-25025 March 2016 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, and to Request an Alternative to the Asme.. 2023-07-27
[Table view] Category:Technical Specification
MONTHYEAR2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications2024-04-0404 April 2024 Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement 1CAN102101, SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2021-10-0606 October 2021 SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections 1CAN012002, License Amendment Request: Revise Loss of Voltage Relay Allowable Values2020-01-24024 January 2020 License Amendment Request: Revise Loss of Voltage Relay Allowable Values 2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations2019-12-16016 December 2019 License Amendment Request Technical Specification Deletions, Additions, and Relocations 1CAN061902, Supplemental Change Related to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2019-06-18018 June 2019 Supplemental Change Related to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 1CAN031901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2019-03-25025 March 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. 1CAN111802, ANO Unit 1 SAR Amendment 28, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2018-11-12012 November 2018 ANO Unit 1 SAR Amendment 28, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 2CAN121705, Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 262017-12-28028 December 2017 Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26 2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits2017-11-20020 November 2017 License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits 1CAN031604, Arkansas, Unit 1 - 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, and to Request an Alternative to the ASME Co2016-03-25025 March 2016 Arkansas, Unit 1 - 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, and to Request an Alternative to the ASME Code 2CAN031602, 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, and to Request an Alternative to the Asme..2016-03-25025 March 2016 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, and to Request an Alternative to the Asme.. 2CAN121502, Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process2015-12-22022 December 2015 Application to Revise Technical Specifications to Adopt TSTF-426, Revise or Add Actions to Preclude Entry Into LCO 3.0.3 - RITSTF Initiatives 6b & 6c, Using the Consolidated Line Item Improvement Process 1CAN121403, License Amendment Request Supplemental ANO-1 Adoption of TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441).2014-12-0505 December 2014 License Amendment Request Supplemental ANO-1 Adoption of TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441). 2CAN101401, Arkansas, Unit 2 - License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)2014-10-22022 October 2014 Arkansas, Unit 2 - License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186) 1CAN011406, Amendment 25 of the ANO Unit 1 Safety Analysis Report2014-01-29029 January 2014 Amendment 25 of the ANO Unit 1 Safety Analysis Report 1CAN121301, Clarification of Proposed Change to Technical Specification 2.1.1.1 Reactor Core Safety Limits2013-12-11011 December 2013 Clarification of Proposed Change to Technical Specification 2.1.1.1 Reactor Core Safety Limits 2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712013-06-18018 June 2013 License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)2013-03-26026 March 2013 License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441) 2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712012-07-0909 July 2012 License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712012-04-0404 April 2012 License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 1CAN041102, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-29029 April 2011 License Amendment Request, Adoption of Technical Specification Task Force (TSTF)513, Revision 3, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation. 1CAN081001, License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves2010-08-24024 August 2010 License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves 2CAN081009, Emergency License Amendment Request Extension of ANO-2 Emergency Diesel Generator Allowed Outage Time2010-08-19019 August 2010 Emergency License Amendment Request Extension of ANO-2 Emergency Diesel Generator Allowed Outage Time 1CAN081002, License Amendment Request, Changes to Technical Specification 3.9.3, Technical Change Traveler - TSTF-312, Rev. 12010-08-10010 August 2010 License Amendment Request, Changes to Technical Specification 3.9.3, Technical Change Traveler - TSTF-312, Rev. 1 ML1016803802010-06-17017 June 2010 License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years 2CAN061003, Arkansas Nuclear One, Unit 2 - License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years2010-06-17017 June 2010 Arkansas Nuclear One, Unit 2 - License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN021004, Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.2010-02-28028 February 2010 Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. 2CAN060903, License Amendment Request, Technical Specification Changes to Relocate Pressurizer Heater Requirements to Technical Requirements Manual2009-06-18018 June 2009 License Amendment Request, Technical Specification Changes to Relocate Pressurizer Heater Requirements to Technical Requirements Manual 2CAN050902, License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report2009-05-15015 May 2009 License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report 2CAN050901, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-05-13013 May 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions 1CAN030901, License Amendment Request on Technical Specification Change to Delete Low Pressurizer Level Limit2009-03-10010 March 2009 License Amendment Request on Technical Specification Change to Delete Low Pressurizer Level Limit 2CAN030902, License Amendment Request, Technical Specification Change to Delete COLR References2009-03-10010 March 2009 License Amendment Request, Technical Specification Change to Delete COLR References 2CAN120801, License Amendment Request Supplemental Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM2008-12-11011 December 2008 License Amendment Request Supplemental Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM 2CAN070801, Supplement to License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-3592008-07-0808 July 2008 Supplement to License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-359 2CAN030806, Supplemental to License Amendment Request, Technical Specification 3.1.1.4, Moderator Temperature Coefficient2008-03-27027 March 2008 Supplemental to License Amendment Request, Technical Specification 3.1.1.4, Moderator Temperature Coefficient 1CAN100703, License Amendment Request - Technical Specification Changes and Analyses Relating to Use of Alternate Source Term2007-10-22022 October 2007 License Amendment Request - Technical Specification Changes and Analyses Relating to Use of Alternate Source Term 2CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process2007-10-22022 October 2007 License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process 2CAN100703, Unit 2 License Amendment Request for Technical Specification Change Associated with Replacement of Containment Sump Buffer2007-10-0505 October 2007 Unit 2 License Amendment Request for Technical Specification Change Associated with Replacement of Containment Sump Buffer ML0726300862007-09-28028 September 2007 License and Technical Specification Pages - Amendment No. 273 Revisions to TS to Support Partial Re-Rack and Revised Loading Patterns in the Spent Fuel Pool 2024-04-04
[Table view] Category:Amendment
MONTHYEAR2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications2024-04-0404 April 2024 Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections 1CAN012002, License Amendment Request: Revise Loss of Voltage Relay Allowable Values2020-01-24024 January 2020 License Amendment Request: Revise Loss of Voltage Relay Allowable Values 1CAN061902, Supplemental Change Related to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2019-06-18018 June 2019 Supplemental Change Related to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 2CAN121705, Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 262017-12-28028 December 2017 Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26 2CAN101401, Arkansas, Unit 2 - License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)2014-10-22022 October 2014 Arkansas, Unit 2 - License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186) 1CAN121301, Clarification of Proposed Change to Technical Specification 2.1.1.1 Reactor Core Safety Limits2013-12-11011 December 2013 Clarification of Proposed Change to Technical Specification 2.1.1.1 Reactor Core Safety Limits 2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712012-07-0909 July 2012 License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712012-04-0404 April 2012 License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 ML1016803802010-06-17017 June 2010 License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years 2CAN061003, Arkansas Nuclear One, Unit 2 - License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years2010-06-17017 June 2010 Arkansas Nuclear One, Unit 2 - License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years 2CAN050902, License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report2009-05-15015 May 2009 License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report 2CAN050901, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit2009-05-13013 May 2009 License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions2009-04-27027 April 2009 Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions 2CAN030806, Supplemental to License Amendment Request, Technical Specification 3.1.1.4, Moderator Temperature Coefficient2008-03-27027 March 2008 Supplemental to License Amendment Request, Technical Specification 3.1.1.4, Moderator Temperature Coefficient 2CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process2007-10-22022 October 2007 License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process 2CAN100703, Unit 2 License Amendment Request for Technical Specification Change Associated with Replacement of Containment Sump Buffer2007-10-0505 October 2007 Unit 2 License Amendment Request for Technical Specification Change Associated with Replacement of Containment Sump Buffer ML0726300862007-09-28028 September 2007 License and Technical Specification Pages - Amendment No. 273 Revisions to TS to Support Partial Re-Rack and Revised Loading Patterns in the Spent Fuel Pool 2CAN050702, License Amendment Requesting, Technical Specification 3.1.1.4, Moderator Temperature Coefficient2007-05-0808 May 2007 License Amendment Requesting, Technical Specification 3.1.1.4, Moderator Temperature Coefficient ML0704400422007-02-26026 February 2007 Corrected Tech Spec Pgs - Correction to Amendment No. 228 for the Use of Metamic Poison Insert Assemblies in the Spent Fuel Pool 1CAN080601, License Amendment Request Regarding the Relocation of Inverter Y-28 and Panel C-540 Requirements from TSs to TRM2006-08-31031 August 2006 License Amendment Request Regarding the Relocation of Inverter Y-28 and Panel C-540 Requirements from TSs to TRM 1CAN070603, License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool2006-07-27027 July 2006 License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool 2CAN020601, License Amendment Request to Modify Technical Specification Surveillance Requirement 4.6.1.1.a2006-02-14014 February 2006 License Amendment Request to Modify Technical Specification Surveillance Requirement 4.6.1.1.a 2CAN090504, Arkansas, Unit 2 - License Amendment Request to Modify Technical Specification 3.1.1.5, Minimum Temperature for Criticality2005-09-19019 September 2005 Arkansas, Unit 2 - License Amendment Request to Modify Technical Specification 3.1.1.5, Minimum Temperature for Criticality 2CAN090502, Arkansas, Unit 2 - License Amendment Request to Allow One-Time Extension of Containment Spray System Allowable Outage Time2005-09-19019 September 2005 Arkansas, Unit 2 - License Amendment Request to Allow One-Time Extension of Containment Spray System Allowable Outage Time 2CAN070503, Arkansas, Unit 2 - License Amendment Request to Add Cask Loading Restrictions2005-07-21021 July 2005 Arkansas, Unit 2 - License Amendment Request to Add Cask Loading Restrictions ML0513700652005-05-13013 May 2005 ANO, Unit 2 -Technical Specification Pages Elimination of Requirements to Provide Monthly Operating Reports ML0509000042005-03-23023 March 2005 ANO Unit 2, Technical Specification.Pages Request to Support Cycle 18 Core Reload ML0414105232004-05-12012 May 2004 Arkansas, Unit 2, License Amendment Request to Support Cycle 18 Core Reload 1CAN120301, ANO, Unit 1 - Supplement to Amendment Request to Add a New Control Room Emergency Ventilation System Surveillance Requirement2003-12-16016 December 2003 ANO, Unit 1 - Supplement to Amendment Request to Add a New Control Room Emergency Ventilation System Surveillance Requirement ML0325906772003-09-11011 September 2003 Amendment 251 to License Re. Emergency Core Cooling Systems Technical Specification Pages ML0323104992003-08-12012 August 2003 Supplement to Amendment Request to Revise the Spent Fuel Pool Loading Pattern ML0322304332003-08-0808 August 2003 Amendment No. 249, Technical Specifications, Re. Emergency Diesel Generator Allowable Outage Time ML0318907712003-06-30030 June 2003 License Amendment Request, to Revise Spent Fuel Pool Loading Pattern 2CAN050304, Arkansas, Unit 2, License Amendment Request to Change Containment Spray System Surveillance2003-05-0101 May 2003 Arkansas, Unit 2, License Amendment Request to Change Containment Spray System Surveillance 2CAN090202, Arkansas Unit 2, Application for Amendment to License NPF-6 to Amend Technical Specifications to Extend Allowable Outage Time (AOT) for Emergency Diesel Generators (Edgs) from 72 Hours to Maximum of 14 Days2002-09-19019 September 2002 Arkansas Unit 2, Application for Amendment to License NPF-6 to Amend Technical Specifications to Extend Allowable Outage Time (AOT) for Emergency Diesel Generators (Edgs) from 72 Hours to Maximum of 14 Days 2024-04-04
[Table view] |
Text
A nEntergy Operations, Inc.
- Intergy, 1448 S.R. 333 Russeliville, AR 72802 Tel 479-858-4888 Jeffery S. Forbes Vice President Operations ANO 2CAN020601 February 14, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Amendment Request To Modify Technical Specification Surveillance Requirement 4.6.1.1.a Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests the following amendment to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs).
The proposed change will modify the ANC-2 TS Surveillance Requirement (SR) 4.6.1.1.a.
Specifically, the proposed change will eliminate the requirement to verify containment isolation valves that are maintained locked, sealed, or otherwise secured closed from the monthly position verification. The proposed change will result in reducing radiological exposure to Operations, Health Physics, and Security personnel.
The proposed change will reflect the wording that is included in NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1, SR 3.6.3.3 and SR 3.6.3.4 with consideration for the difference in TS format. NUREG-1432 reflects Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler No. 45 (TSTF-45-A) which was approved by the NRC on July 26, 1999.
The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that this change involves no significant hazards consideration. The bases for these determinations are included in the attached submittal.
The proposed change does not include new commitments.
Entergy requests approval of the proposed amendment by December 31, 2006. Once approved, the amendment shall be implemented within 60 days. Although this request is neither exigent nor emergency, your prompt review is requested.
4A00i
2CAN020601 Page 2 of 2 If you have any questions or require additional information, please contact Dana Millar at 601-368-5445.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 006.
Sincerely, JSF/DM Attachments:
- 1. Analysis of Proposed Technical Specification Change
- 2. Proposed Technical Specification Changes (mark-up) cc: Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland MS O-7D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205
Attachment I 2CAN020601 Analysis of Proposed Technical Specification Change to 2CAN'D20601 Page 1 of 6
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2).
The proposed change will revise the Operating License to modify the ANO-2 Technical Specification (TS) Surveillance Requirement (SR) 4.6.1.1.a. Performance of the SR ensures the manual valves, blind flanges, or deactivated automatic valves located in containment penetrations that are required to be closed during an accident condition are secured in their closed positions. The SR is performed at least every 31 days. The SR is modified by a note
(*) that allows excluding verification of the valves located inside containment that are locked, sealed, or otherwise secured in the closed position and includes a SR to perform a check of the inside containment isolation valve positions prior to entering Mode 4 from Mode 5 if not performed in the previous 92 days. The proposed change will modify SR 4.6.1.1.a to specifically exclude locked, sealed, or otherwise secured closed valves that are located outside containment from the monthly verification. A new SR (SR 4.6.1.1.d) will be added that will reflect the surveillance requirement for similar devices located inside containment. In addition a new note will be included that will allow verification of the valves and blind flanges that are located in high radiation areas by use of administrative means.
The proposed change reflects the wording that is included in NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3.1, SR 3.6.3.3 and SR 3.6.3.4 with consideration for the difference in TS format. NUREG-1432 reflects Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler No. 45 (TSTF-45-A) which was approved by the NRC on July 26, 1999.
Approval of the proposed change is requested by December 31, 2006.
2.0 PROPOSED CHANGE
The proposed change revises ANO-2 TS SR 4.6.1.1 a, which currently states:
"At least once per 31 days by verifying that all penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1."
The
- note states the following:
"*Exdept valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed prior to entering Mode 4 from Mode 5, except that such verification need not be performed more often than once per 92 days."
The proposed change is as follows and is consistent with the wording in NUREG-1432, Standard Technical Specifications Combustion Engineering Plants (SRs 3.6.3.3 and 3.6.3.4),
with consideration of the different TS format:
to 2CAN02060 1 Page :2 of 6 "At least once per 31 days by verifying that each containment isolation manual valve and blind flange (Note 1) that is located outside containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative control as permitted by Specification 3.6.3.1.'
The proposed change will delete the current
- note and incorporate the exception and requirements contained in the
"Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days by verifying each containment isolation manual valve and blind flange (Note 1) that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls as permitted by Specification 3.6.3.1."
A new note will be added as follows:
"Note 1: Valves and blind flanges in high radiation areas may be verified by use of administrative means."
In summary, a change is proposed to clarify the existing SR and
- note. The proposed change will specifically exclude verification of the normally locked, sealed, or otherwise secured closed valves, blind flanges, and the deactivated automatic valves. A new Mode 5 to 4 SR will be added to replace the existing
- note since the note contains a requirement to perform the surveillance for those valves located inside containment. The change also allows an alternate means for performing valve verification when the valve is located in a high radiation area. The change will result in reducing radiological exposure to Operations, Health Physics, and Security personnel.
3.0 BACKGROUND
The AINO-2 TS 3.6.1.1 requires that containment integrity be maintained in Modes 1, 2, 3, and 4. ANO-2 TS 1.8 provides the following definition of containment integrity:
"CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident conditions are either:
- a. Capable of being closed by an OPERABLE containment automatic isolation valve system, or
- b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1.
1.8.2 All equipment hatches are closed and sealed, 1.8.3 Each airlock is OPERABLE pursuant to Specification 3.6.1.3,
4 Attachment 1 to 2CAN020601 Page 3 of 6 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g., welds, bellows or O-rings) is OPERABLE.
Surveillance Requirement 4.6.1.1 provides the requirements that must be met to ensure containment integrity is demonstrated. Containment integrity ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
SR 4.6.1.1.a specifically addresses verification of all containment penetrations that are required to be closed during accident conditions to ensure they are closed or capable of being closed. The proposed change to SR 4.6.1.1 .a will eliminate the current requirement to verify the position of deactivated automatic valves and normally locked valves that are located outside containment since these valves are already in the required accident position.
When an automatic valve is deactivated it is treated like a manual valve. If there is a valve handwheel on an automatic valve that will be deactivated, the handwheel is locked in the closed position. In addition, the breaker or air supply to the valve is placed in the appropriate position to ensure the valve is closed and movement is prohibited.
The A1NO-2 containment isolation valve program/procedure ensures containment integrity is maintained through the establishment of configuration control for the containment isolation valves. The program/procedure was based on the guidance contained in Generic Letter (GL) 91-08, Removal of Component Lists from Technical Specifications. The following administrative controls, which are included in the ANO-2 TS Bases (TS 3/4.6.3) and in the procedure, were required by GL 91-08: "The opening of locked or sealed closed manual and deactivated automatic containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing an operator, who is in constant communication with the control room, at the valve controls, (2) instructing the operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment." These administrative controls in conjunction with procedural requirements to track any valve manipulations until the valve is restored to its closed position, which includes an independent verification that the valve is locked closed, provide assurance that the manual containment isolation valves are locked closed or controlled until they are locked closed.
Technical Specification 3.6.3.1 requires the operability of each containment isolation valve.
The Specification ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
ANO-2 Safety Analysis Report (SAR) Table 6.2-26 provides a list of containment penetrations, i.e., fluid system piping, instrument lines, electrical equipment, and personnel access; and identifies the type of leak testing to be performed in accordance with 10 CFR 50, Appendix J.
'4 Attachment 1 to 2CAN020601 Page 4 of 6
4.0 TECHNICAL ANALYSIS
The containment isolation system consists of manual valves, remote manual valves, blind flanges, deactivated automatic valves, automatic valves, equipment hatches, airlocks, and sealing mechanisms on each penetration. The components of the containment isolation system provide the means of ensuring containment integrity exists when required during accident conditions.
Containment integrity is verified each month by performing SR 4.6.1.1.a. The outside containment isolation valves are located in the containment penetration rooms and many times in overhead areas that require protective clothing to access. The annual dose associated with performing the SR has been estimated to be 80 mRem. Therefore, the proposed elimination of the need to check those valves that are locked, sealed, or otherwise secured closed will result in reducing overall radiological exposure.
Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler No. 45 (TSTF-45-A) was approved by the NRC on July 26, 1999. The TSTF stated that the proposed change was consistent with the valve position verification requirement for valves that have a function during an accident in other system TSs.
Consistent with the logic of the TSTF, ANO-2 TS SR 4.5.2.b requires that each Emergency Core Cooling System (ECCS) subsystem be demonstrated operable, in part, by performance of a valve alignment of each valve that is ii the flow path that is NOT locked, sealed or otherwise secured valves. The Emergency Feedwater system (EFW) and the Service Water (SW) system are also demonstrated to be operable, in part, by verifying that each valve in the flow path of the system that is NOT locked, sealed, or otherwise secured in position, is in its correct position (SR 4.7.1 .2.a. 1 and SR 4.7.3.1 .a, respectively). The proposed change is therefore consistent with other ANO-2 TS SRs and the NRC approved traveler (TSTF-45-A).
Manual containment isolation valves may be opened intermittently under strict administrative controls which are contained in a plant procedure. As stated in the Background section, NRC GL 91-08, Removal of Component Lists from Technical Specifications, provided the guidance for the administrative requirements associated with opening manual containment isolation valves intermittently. Anytime a manual containment isolation valve is opened the procedure requires tracking of the valve configuration until the valve is restored to its locked closed position. The configuration tracking includes an independent verification of the locked closed position of the valve. These steps provide assurance that the valves are locked closed after being manipulated and therefore performance of the monthly surveillance to verify the valves are closed and locked is redundant to the controls that are in place.
The addition of the note that allows an alternate means of verifying valves that are located in high radiation areas is acceptable since access to these areas is restricted in accordance with the requirements of ANO-2 TS 6.7, High Radiation Area. It is very unlikely that valves located in high radiation areas will be misaligned after they have been verified to be locked closed.
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Attachment 1 to 2CAN 020601 Page 5 of 6
5.0 REGULATORY ANALYSIS
5.1 Applicable Regulatorv Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and does not affect conformance with any General Design Criterion (GDC) differently than described in the Arkansas Nuclear One, Unit 2 (ANO-2) Safety Analysis Report (SAR.)
The containment isolation systems are designed in accordance with 10 CFR 50 Appendix A, GDC 54, 55, 56 and 57, and meet the leak testing criteria of 10 CFR 50, Appendix J. The applicable criterion for each penetration is shown in ANO-2 SAR Table 6.2-26. The containment isolation systems are also designed to withstand the design basis earthquake and the credible failure of any single active or passive component without loss of isolating capability. Because no design changes are proposed these requirements remain satisfied.
5.2 No Significant Hazards Consideration A change is proposed to the Arkansas Nuclear One, Unit 2 (ANO-2) surveillance requirements (SRs) associated with ANO-2 Technical Specification (TS) 3.6.1.1, Primary Containment - Containment Integrity. The proposed change will clarify the existing SR 4.6.1.1.a and associated
- note. The proposed change to SR 4.6.1.1.a, which provides a check of those valves located outside containment, will specifically exclude verification of the normally locked, sealed, or otherwise secured closed valves, blind flanges, and the deactivated automatic valves. A new Mode 5 to 4 SR (proposed SR 4.6.1.1 .d) will be added to replace the existing
- note since the note contains a requirement to perform a surveillance of the valves located inside containment. The proposed change also allows an alternate means for performing valve verification when the valve is located in a high radiation area.
The change will result in reducing radiological exposure to Operations, Health Physics, and Security personnel. Taking into account the format difference between the ANO-2 TSs and Revision 3.1 of NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, the proposed change is consistent with Technical Specification Task Force (TSTF)
Improved Standard Technical Specification Change Traveler No. 45 (TSTF-45-A), which was approved by the NRC on July 26, 1999.
Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFIR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The accident mitigation features of the plant for previously evaluated accidents are not affected by the proposed change. No changes are proposed to the physical components or to the containment isolation function.
A Attachment 1 to 2CAN 020601 Page 6 of 6 Repositioning of manual containment isolation valves is procedurally controlled and governed by the note that is contained in TS 3.6.3.1, Containment Isolation Valves, which allows opening locked or sealed closed valves on an intermittent basis. The valve position is tracked until it is restored to its original position (locked or deactivated position, as appropriate). While the valve remains open, an individual, in constant communication with the control room staff, is stationed at the valve. If an accident were to occur, the control room staff would direct the individual stationed at the valve to close the valve thereby precluding the release of radioactivity outside containment.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not change the design, method of operation, or configuration of the plant. The procedural controls that establish the ANO-2 containment valve program controls and include the administrative controls that are associated with the note in TS 3.6.3.1, ensure containment integrity is appropriately established such that no new or different types of accidents are created.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change does not change the design basis for any equipment in the plant. The proposed change will exclude verification of the normally locked, sealed, or otherwise secured closed valves, blind flanges, and the deactivated automatic valves; however, the administrative controls applied to these components ensure that containment integrity is maintained.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
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Attachment 2 2CAN020601 Proposed Technical Specification Changes (mark-up)
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
- a. At least once per 31 days by verifying that all penetrations* not capable of being closed by OPERABLE cach containment autematicGisolation manual valves and blind flange (Note 1)that is located outside containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions aFe-is closed by valves, blind flanges, or -dectivated automatic valves secured in; their positions, except for containment isolation valves that are open under administrative control as permitted by Specification 3.6.3.1.
- b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
- c. After each closing of the equipment hatch, by leak rate testing the equipment hatch seals in accordance with the Containment Leakage Rate Testing Program.
- d. Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days by verifying each containment isolation manual valve and blind flange (Note 1)that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls as permitted by Specification 3.6.3.1.
- Exce t valves, blind flanges, and deactivaited automatic valves which are located inside the Gentainrient and are orcked, sealed, or otherw;se secured in the Glosed position ThERA penetrations shall be verified closed prior to entering Mode 4 from Mode 6, except that Buch veuification need not be performed more often than once per 92 days.
Note 1: Valves and blind flanges in high radiation areas may be verified by use of administrative means.
ARKANSAS - UNIT 2 3/4t6-1 Amendment No. 4-4,476,244,