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EPID:L-2018-LLA-0082, Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 (Approved, Closed) |
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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 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 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 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 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. 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. 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
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Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-3110 Richard L. Anderson ANO Site Vice President 10 CFR 50.90 0CAN031801 March 29, 2018 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
License Amendment Request Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Arkansas Nuclear One, Unit 1 and Unit 2 Docket Nos. 50-313, 50-368 and 72-13 License Nos. DPR-51 and NPF-6
Reference:
NRC letter "U.S. Nuclear Regulatory Commission Review and Endorsement of NEI 99-01, Revision 6, Dated November, 2012 (TAC No. D92368),"
March 28, 2013 (ML12346A463)
Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy), hereby requests an amendment to the license for Arkansas Nuclear One, Units 1 and 2 (collectively referred to as ANO).
Specifically, the proposed change involves revising the Emergency Plan for ANO to adopt the Nuclear Energy Institute's (NEI's) revised Emergency Action Level (EAL) scheme described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, which has been endorsed by the Nuclear Regulatory Commission (NRC) as documented in the referenced letter. ANO currently uses an EAL scheme based on NEI 99-01, Revision 5. The proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and no significant environmental impacts are associated with the proposed changes.
10 CFR Part 50, Appendix E, Section IV.B.2, stipulates that a licensee desiring to change its entire EAL scheme shall submit an application for an amendment to its license and receive NRC approval before implementing the change. In its endorsement of the guidance, the NRC notes that NEI 99-01, Revision 6, is considered a significant change to the EAL scheme development methodology, and licensees seeking to use this guidance in the development of EAL schemes must adhere to the requirements of 10 CFR Part 50, Appendix E, Section IV.B.2. Therefore, pursuant to 10 CFR 50.90, Entergy requests NRC review and approval of a revision to the Emergency Plan EALs for ANO.
0CAN031801 Page 2 of 3 provides an evaluation of the proposed changes. Enclosure 2 provides the NEI 99-01, Revision 6, EAL Technical Basis marked to illustrate the proposed changes. provides the revised (clean) EAL Technical Basis document. provides a deviation-difference document comparing NEI 99-01, Revision 6, with the proposed changes to the ANO EAL schemes. Enclosure 5 includes an EAL matrix chart and review table (for information only), which is a quick-reference tool developed to support timely Emergency Response Organization personnel EAL determinations. Finally, Enclosure 6 provides specific reference documents or excerpts which support related ANO Emergency Plan proposed changes.
Approval of the proposed amendment is requested by April 1, 2019. Once approved, the amendment shall be implemented by October 30, 2019.
No new regulatory commitments are included in this amendment request.
The proposed Initiating Conditions and EALs have been reviewed by the ANO Onsite Safety Review Committee. In addition, the proposed changes associated with adoption of NEI 99-01, Revision 6, were discussed with state and county officials on December 5, 2017, during a meeting conducted at the Pope County Courthouse. Representatives from the Arkansas Department of Health, Conway County, Johnson County, Logan County, Pope County, and Yell County were present. In accordance with 10 CFR 50.91, Entergy is notifying the State of Arkansas of this amendment request by transmitting a copy of this letter and enclosure to the designated State Official.
If there are any questions or if additional information is needed, please contact Stephenie Pyle at 479-858-4704.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 29, 2018.
Sincerely, ORIGINAL SIGNED BY RICHARD L. ANDERSON RLA/dbb
Enclosures:
- 1. Evaluation of Proposed Changes
- 2. Proposed EAL Technical Basis Document (Markup)
- 3. Proposed EAL Technical Basis Document (Clean)
- 4. NEI 99-01, Rev. 6, Deviations and Differences, ANO Units 1 and 2
- 5. Proposed EAL Matrix Chart and Review Table (for information only)
- 6. Supporting Referenced Document Pages
0CAN031801 Page 3 of 3 cc: Mr. Kriss Kennedy Regional Administrator U. S. Nuclear Regulatory Commission RGN-IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205
Enclosure 1 to 0CAN031801 Evaluation of the Proposed Changes to 0CAN031801 Page 1 of 8 EVALUATION OF THE PROPOSED CHANGEs 1.0
SUMMARY
DESCRIPTION Entergy Operations, Inc. (Entergy) proposes to revise the Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2, collectively referred to as ANO) currently approved Emergency Plan (EP)
Emergency Action Level (EAL) scheme, which is based on the Nuclear Energy Institute's (NEI's) guidance established in NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels" (Reference 1). Entergy is proposing to adopt the EAL schemes based on the guidance provided in NEI 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors," which has been endorsed by the NRC (Reference 2) 2.0 DETAILED DESCRIPTION The proposed changes involve revising ANOs EAL scheme, which is currently based on NEI 99-01, Revision 5, to a scheme based on NEI 99-01, Revision 6. Enhancements provided by Revision 6 of the guidance include:
Clarification of numerous EALs that have been typically misinterpreted by the industry in the development of their site-specific EAL scheme, Clarification of the intent of EALs that have been historically misclassified, Providing additional guidance for the development of EALs for current non-passive reactor designs as well as possible future reactor designs that are non-passive, Incorporating lessons learned from industry events (i.e., Fukushima and others) and NUREG/CR-7154, Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels - A Pilot Study of Peach Bottom, Surry and Sequoyah, and A detailed review of the guidance to re-validate that the EALs are appropriate and are at the necessary emergency classification level based upon 32 years of industry and NRC experience with EAL scheme development and implementation.
2.1 Proposed Initiating Conditions (ICs) and EALs , Proposed EAL Technical Basis Document (Markup), provides a markup of the current ANO EAL scheme basis illustrating changes incorporating the guidance of NEI 99-01, Revision 6. Enclosure 3 provides a clean copy of ANO EAL Technical Basis document.
2.2 Deviations and Differences contains a matrix that provides a comparison of the ICs and EALs in NEI 99-01 to the ICs and EALs proposed for ANO. The comparison evaluates differences and deviations consistent with the similar exercise performed during the ANO EP upgrade to NEI 99-01, Revision 5 (Reference 3). The NRC approved ANOs EP upgrade to NEI 99-01, Revision 5, on November 9, 2012 (Reference 4).
to 0CAN031801 Page 2 of 8 A difference is an EAL change where the basis scheme guidance differs in wording, but agrees in meaning and intent, such that classification of an event would be the same, whether using the basis scheme guidance or the site-specific proposed EAL. Examples of differences include the use of site-specific terminology or administrative re-formatting of site-specific EALs.
A deviation is an EAL change where the basis scheme guidance differs in wording and is altered in meaning or intent, such that classification of the event could be different between the basis scheme guidance and the site-specific proposed EAL. Examples of deviations include the use of altered mode applicability, altering key words or time limits, or changing words of physical reference (protected area, safety-related equipment, etc.).
A number of differences are the result of adding plant-specific information to the EALs. In these cases, Enclosure 4 may refer the reader to an associated document in Enclosure 6, Supporting Referenced Document Pages, which provides the technical basis for plant-specific information.
2.3 Generic Differences The differences below apply throughout the set of EALs and are not specifically identified in each instance in the comparison matrix as a difference.
NEI 99-01, Rev 6 EALs ANO Station EALs References BWRs Deleted BWR references as appropriate Uses E-HU for ISFSI ICs Uses EU for ISFSI ICs Designates ICs and EALs as Designates ICs and EALs as Example: (IC)HU1 EAL 2 Example: HU1.2 Emergency Classification ICs are presented Emergency Classification ICs are presented together by Emergency Classification level by Emergency Classification family (A1, (all NOUEs grouped together, then all A2, A3, etc.) for each category, in Alerts, etc.) for each category (A, C, H, ascending order (UE - GE) etc.), in ascending order (UE - GE) to 0CAN031801 Page 3 of 8 2.4 Operational Modes Mode applicability of the proposed ICs and EALs is consistent with the NEI 99-01, Revision 6.
The following tables provide the operating modes for both ANO units as defined by the respective Technical Specifications (TSs).
ANO-1
% RATED AVERAGE REACTIVITY MODE TITLE THERMAL REACTOR COOLANT CONDITION (Keff)
POWER (a) TEMPERATURE (°F) 1 Power Operation 0.99 >5 NA 2 Startup 0.99 5 NA 3 Hot Standby < 0.99 NA 280 4 Hot Shutdown (b) < 0.99 NA 280 > Tavg > 200 5 Cold Shutdown (b) < 0.99 NA 200 6 Refueling (c) NA NA NA (a) Excluding decay heat.
(b) All reactor vessel head closure bolts fully tensioned.
(c) One or more reactor vessel head closure bolts less than fully tensioned.
ANO-2 REACTIVITY %RATED AVERAGE COOLANT MODE CONDITION, Keff THERMAL POWER* TEMPERATURE
- 1. POWER OPERATION 0.99 > 5% 300 °F
- 2. STARTUP 0.99 5% 300 °F
- 3. HOT STANDBY < 0.99 0 300 °F
- 4. HOT SHUTDOWN < 0.99 0 300 °F > Tavg > 200 °F
- 5. COLD SHUTDOWN < 0.99 0 200 °F
- 6. REFUELING** 0.95 0 140 °F
- Reactor vessel head unbolted or removed and fuel in the vessel.
to 0CAN031801 Page 4 of 8 In addition to the TS defined operational modes, NEI 99-01, Revision 6, defines the following additional mode:
Defueled: All reactor fuel removed from the reactor vessel (i.e., full core off load during refueling or extended outage).
ANO procedures recognize and are consistent with the definition of a defueled condition.
2.5 Instrumentation Used for EALs ANO has verified that the specified values used as EAL setpoints are within the calibrated range of the referenced instrumentation.
2.6 Background Technical Information provides the existing EAL Technical Basis document marked to illustrate the proposed changes. Enclosure 3 provides the revised (clean) EAL Technical Basis document. provides a deviation-difference document comparing NEI 99-01, Revision 6, with the proposed changes to the ANO EAL schemes. Enclosure 5 includes an EAL matrix chart and review table (for information only), which is a quick-reference tool developed to support timely Emergency Response Organization personnel EAL determinations. Enclosure 6 provides specific reference documents or excerpts which support related ANO Emergency Plan proposed changes.
3.0 TECHNICAL EVALUATION
Entergy has evaluated the proposed changes to determine whether applicable regulations and requirements have been met. NEI 99-01 guidance methodology includes many years of development, along with use and implementation. The guidance has been subject to NRC reviews and approval. The ANO EAL scheme currently in place is based on the methodology in NEI 99-01, Revision 5. NEI 99-01, Revision 6, is the latest version endorsed by the NRC and provides guidance to nuclear power plant operators for the development of a site-specific emergency action level scheme.
10 CFR 50.47(b)(4) requires that emergency plans include a standard emergency classification and action level scheme. This scheme is a fundamental component of an EP in that it provides the defined thresholds that will allow site personnel to rapidly implement a range of pre-planned emergency response measures. An emergency classification scheme also facilitates timely decision-making by an offsite response organization concerning the implementation of precautionary or protective actions for the public NEI 99-01, Revision 6, contains a generic set of ICs, EALs, and fission product barrier status thresholds. The guidance also includes supporting technical basis information, developer notes, and recommended classification instructions for users. The methodology described in this document is consistent with NRC requirements and guidance. In particular, this methodology was specifically endorsed by the NRC in a March 28, 2013, letter from NRC to NEI (Reference 2) and determined to provide an acceptable approach in meeting requirements of 10 CFR 50.47(b)(4), applicable requirements of 10 CFR 50, Appendix E, and the associated to 0CAN031801 Page 5 of 8 planning standard evaluation elements contained in NUREG-0654/FEMA-REP-1, Revision 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, November 1980.
10 CFR 50, Appendix E, Section IV.B.2, requires that a licensee desiring to change its entire EAL scheme shall submit an application for an amendment to its license and receive NRC approval before implementing the change. The proposed change to the ANO EAL scheme from NEI 99-01, Revision 5, to NEI 99-01, Revision 6, guidance does not reduce the capability to meet the applicable emergency planning standards and requirements in 10 CFR 50.47(b) and 10 CFR 50, Appendix E. Accordingly, pursuant to the requirements of 10 CFR 50, Appendix E, Section IV.B.2, Entergy requests NRC review and approval of the proposed changes to the EAL scheme as a license amendment request in accordance with 10 CFR 50.90.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria The regulations in 10 CFR 50.54(q) provide direction to licensees seeking to revise emergency plans. The requirements related to nuclear power plant emergency plans are contained in the standards in 10 CFR 50.47, Emergency Plans, and the requirements of Appendix E, Emergency Planning and Preparedness for Production and Utilization Facilities.
Paragraph 10 CFR 50.47(a)(1) states that no operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
Section 50.47(b) contains standards that onsite and offsite emergency response plans must meet for the NRC staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
One of these standards, 10 CFR 50.47(b)(4), requires that emergency plans include a standard emergency classification and action level scheme.
10 CFR 50, Appendix E, Section IV.B, Assessment Actions, requires that emergency plans include emergency action levels (EALs) that are to be used as criteria for determining the need for notification and participation of local and state agencies, and for determining when and what type of protective measures should be considered to protect the health and safety of individuals both onsite and offsite. EALs are to be based on plant conditions and instrumentation, as well as onsite and offsite radiological monitoring.Section IV.B provides that initial EALs shall be discussed and agreed on by the applicant and state and local authorities, be approved by the NRC, and reviewed annually thereafter with state and local authorities. Therefore, a revision to EALs will require NRC approval prior to implementation, if it involves (1) changing from one EAL scheme to another (e.g., NEI 99-01, Revision 4 to NEI 99-01, Revision 6), (2) proposing an alternate method to comply with the regulations, or (3) the EAL revision proposed by the licensee decreases the effectiveness of the emergency plan.
NRC Regulatory Issue Summary (RIS) 2005-02, Revision 1, Clarifying the Process for Making Emergency Plan Changes, issued April 19, 2011, says that a change in an EAL scheme to incorporate the improvements provided in NUMARC/NESP-007 or NEI 99-01 would not decrease the overall effectiveness of the emergency plan, but due to the potential safety significance of the change, the change needs prior NRC review and approval.
to 0CAN031801 Page 6 of 8 The proposed changes meet the above regulatory requirements.
4.2 Precedent The following commercial nuclear power plants have received license amendments that approved EALs based on NEI 99-01, Revision 6:
Callaway - Amendment 212 (Reference 5)
Fermi 2 - Amendment 202 (Reference 6)
South Texas - Amendments 206 and 194 (Reference 7)
Summer 1 - Amendment 200 (Reference 8) 4.3 No Significant Hazards Consideration Analysis Entergy Operations, Inc. (Entergy) proposes to revise the currently approved Emergency Plan (EP) Emergency Action Level (EAL) scheme for Arkansas Nuclear One, Units 1 and 2 (collectively referred to as ANO), which is based on the Nuclear Energy Institute's (NEI's) guidance established in NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels." Entergy is proposing to adopt the EAL schemes based on the guidance provided in NEI 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors," which has been endorsed by the NRC.
Entergy 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 CFR 50.92, Issuance of Amendment. As required by 10 CFR 50.91(a), Entergy analysis of the issue of no significant hazards consideration is presented below.
- 1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed changes to the ANO EALs do not involve any physical changes to plant equipment or systems and do not alter the assumptions of any accident analyses. The proposed changes do not adversely affect accident initiators or precursors and do not alter design assumptions, plant configuration, or the manner in which the plant is operated and maintained. The proposed changes do not adversely affect the ability of structures, systems or components (SSCs) to perform intended safety functions in mitigating the consequences of an initiating event within the assumed acceptance limits.
Therefore, the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
to 0CAN031801 Page 7 of 8
- 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No No new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of the proposed changes. The changes do not challenge the integrity or performance of any safety-related systems. No plant equipment is installed or removed, and the changes do not alter the design, physical configuration, or method of operation of any plant SSC. Because EALs are not accident initiators and no physical changes are made to the plant, no new causal mechanisms are introduced.
Therefore, the changes do not create the possibility of a new or different kind of accident from an accident previously evaluated.
- 3. Do the proposed changes involve a significant reduction in a margin of safety?
Response: No Margin of safety is associated with the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed changes do not impact operation of the plant and no accident analyses are affected by the proposed changes. The changes do not affect the Technical Specifications or the method of operating the plant. Additionally, the proposed changes will not relax any criteria used to establish safety limits and will not relax any safety system settings. The safety analysis acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation in a configuration outside the design basis. The proposed changes do not adversely affect systems that respond to safely shut down the plant and to maintain the plant in a safe shutdown condition.
Therefore, the changes do not involve a significant reduction in a margin of safety.
Based upon the reasoning presented above, Entergy concludes that the requested change involves no significant hazards consideration, as set forth in 10 CFR 50.92(c), Issuance of Amendment.
4.4 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
to 0CAN031801 Page 8 of 8
5.0 ENVIRONMENTAL CONSIDERATION
The proposed changes are applicable to emergency planning requirements involving the proposed adoption of the NRC-endorsed EAL guidance as described in NEI 99-01, Revision 6, and do not reduce the capability to meet the emergency planning standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E. The proposed changes do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed changes meet 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 changes.
6.0 REFERENCES
- 1. NEI 99-01, Revision 5, "Methodology for Development of Emergency Action Levels" February 2008 (ML080450149)
- 2. NRC letter "U.S. Nuclear Regulatory Commission Review and Endorsement of NEI 99-01, Revision 6, Dated November, 2012 (TAC No. D92368)," March 28, 2013 (ML12346A463)
- 3. Entergy letter dated December 1, 2011, "Proposed Emergency Action Levels Using NEI 99-01, Revision 5 Scheme," (ML113350317) (0CAN121102)
- 4. NRC Safety Evaluation dated November 9, 2012, Arkansas Nuclear One, Units 1 and 2 -
Approval of Conversion of the Emergency Action Level Scheme to a Scheme Based on Nuclear Energy Institute (NEI) 99-01, Revision 5, (TAC Nos. ME7661 and ME7662)
(ML12269A455) (0CNA111201)
- 5. NRC letter Callaway Plant, Unit 1 - Issuance of Amendment Re: Upgrade to Emergency Action Level Scheme (CAC No. MF4945), October 7, 2015 (ML15251A493)
- 6. NRC letter Fermi 2 - Issuance of Amendment to Revise the Emergency Action Level Scheme for the FERMI 2 Emergency Plan (TAC No. MF5048), September 29, 2015 (ML15233A084)
- 7. NRC letter South Texas Project, Units 1 and 2 - Re: Upgrade to Emergency Action Level Scheme (TAC Nos. MF4195 and MF4196), August 20, 2015 (ML15201A195)
- 8. NRC letter Virgil C. Summer Nuclear Station, Unit 1 - Issuance of Amendment to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6 (TAC No. MF3927), (ML15063A55)
- 9. NRC letter Seabrook Station, Unit No. 1 - Issuance of Amendment RE: Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6 (CAC No. MF7439),
February 10, 2017 (ML16358A411)