Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element LML21028A782 |
Person / Time |
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Site: |
Palisades, Indian Point, Grand Gulf, Arkansas Nuclear, River Bend, Waterford |
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Issue date: |
01/28/2021 |
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From: |
Gaston R Entergy Operations |
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To: |
Document Control Desk, Office of Nuclear Reactor Regulation |
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References |
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CNRO-2021-00002, EA-17-132, EA-17-153 |
Download: ML21028A782 (9) |
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Category:Letter type:CNRO
MONTHYEARCNRO-2022-00015, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process2022-05-26026 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L CNRO-2020-00023, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary2020-12-17017 December 2020 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2020 Summary CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020 Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) CNRO-2020-00015, Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019)2020-06-0808 June 2020 Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) CNRO-2020-00009, Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 12020-02-26026 February 2020 Application to Revise Technical Specifications to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control, Revision 1 CNRO-2020-00006, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 22020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO, Revision 2 CNRO-2020-00008, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process2020-01-24024 January 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary CNRO-2019-00007, Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report2019-03-28028 March 2019 Grand Gulf Nuclear Station; and Waterford 3 Steam Electric Station - Decommissioning Funding Status Report CNRO-2019-00006, Stations - Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2018 - 10 CFR 50.82(a)(8)(vii) - Entergy Nuclear Operations, Inc2019-03-28028 March 2019 Stations - Status of Funding for Managing Irradiated Fuel for Year Ending December 31, 2018 - 10 CFR 50.82(a)(8)(vii) - Entergy Nuclear Operations, Inc CNRO-2019-00010, Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2019-03-28028 March 2019 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2019-00005, Stations - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc2019-03-28028 March 2019 Stations - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) - Entergy Nuclear Operations, Inc CNRO-2019-00013, Entergy Response to Confirmatory Order EA-17-132/EA-17-1532019-03-21021 March 2019 Entergy Response to Confirmatory Order EA-17-132/EA-17-153 CNRO-2019-00009, Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 22019-03-0707 March 2019 Stations - Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR, Revision 2 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 CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019 Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 CNRO-2018-00051, Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K2018-12-28028 December 2018 Grand Gulf Nuclear Station, Palisades Nuclear Plant, River Bend Station, Pilgrim Nuclear Station and Waterford 3 - Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K CNRO-2018-00039, Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J2018-09-27027 September 2018 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J CNRO-2018-00023, Request to Revise Quality Assurance Program Approval for Radioactive Material Packages No. 02402018-06-18018 June 2018 Request to Revise Quality Assurance Program Approval for Radioactive Material Packages No. 0240 CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station CNRO-2018-00012, Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v)2018-03-29029 March 2018 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table2018-03-19019 March 2018 Submittal of Joint Plant Access Shared Information Table CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017 Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1 CNRO-2017-00012, Request to Remove James A. FitzPatrick Nuclear Power Plant from Quality Assurance Program Approval for Radioactive Material Packages No. 02402017-06-14014 June 2017 Request to Remove James A. FitzPatrick Nuclear Power Plant from Quality Assurance Program Approval for Radioactive Material Packages No. 0240 CNRO-2017-00009, Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v)2017-03-31031 March 2017 Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) CNRO-2017-00010, Entergy Operations, Inc. - Decommissioning Funding Status Report2017-03-31031 March 2017 Entergy Operations, Inc. - Decommissioning Funding Status Report CNRO-2017-00007, Nuclear Property Damage Insurance (10 CFR 50.54(w)(3))2017-03-30030 March 2017 Nuclear Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2017-00005, and Isfsl - License Amendment Request for Administrative Change to Licensee Name2017-03-29029 March 2017 and Isfsl - License Amendment Request for Administrative Change to Licensee Name CNRO-2017-00004, Notice Regarding Third Proposed Amendment to Master Trust and Planned Distribution of Assets from FitzPatrick Unit Fund to Trust Established2017-01-20020 January 2017 Notice Regarding Third Proposed Amendment to Master Trust and Planned Distribution of Assets from FitzPatrick Unit Fund to Trust Established CNRO-2016-00023, Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities2016-12-0101 December 2016 Request EN-ISI-16-1: Use of Later Edition/Addenda of Amse Section XI Code for ISI Related Activities CNRO-2016-00020, Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning .2016-08-16016 August 2016 Application for Order to Transfer Master Decommissioning Trust from PASNY to ENO, Consenting to Amendments to Trust Agreement, and Approving Proposed License Amendments to Modify and Delete Decommissioning . CNRO-2016-00017, Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual2016-07-19019 July 2016 Entergy Nuclear Operations - Request for Approval of Change to the Quality Assurance Program Manual CNRO-2016-00016, Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated)2016-06-0202 June 2016 Entergy - Response to RAI Questions and Submittal of Relief Request EN-ISI-15-1 (Updated) CNRO-2016-00008, Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))2016-03-30030 March 2016 Entergy - Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) CNRO-2016-00010, Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report, Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v)2016-03-30030 March 2016 Entergy Nuclear Operations, Inc. - Decommissioning Funding Status Report, Per 10 CFR 50.75(f)(1) and 10 CFR 50.82(a)(8)(v) CNRO-2016-00009, Unit 3 - Supplement to Notice of Change in Corporate Form of Entergy Nuclear New York Investment Company I and Creditor Agreement2016-03-21021 March 2016 Unit 3 - Supplement to Notice of Change in Corporate Form of Entergy Nuclear New York Investment Company I and Creditor Agreement CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00006, Notice of Change in Corporate Form of Entergy Nuclear New York Investment Company I and Creditor Agreement2016-02-25025 February 2016 Notice of Change in Corporate Form of Entergy Nuclear New York Investment Company I and Creditor Agreement CNRO-2016-00004, Notice Regarding Acquisition of Title to Leased Interest2016-02-10010 February 2016 Notice Regarding Acquisition of Title to Leased Interest CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 CNRO-2015-00022, Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code2015-11-20020 November 2015 Entergy - Relief Request EN-ISI-15-1: Proposed Alternative to Maintain ISI-Related Activities to the 2001 Edition/2003 Addendum of ASME Section Xl Code CNRO-2015-00023, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM)2015-11-0606 November 2015 Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2015-00021, Confirmatory Order - Action H2015-11-0303 November 2015 Confirmatory Order - Action H CNRO-2015-00020, ISFSI and Waterford 3 Steam Electric Station and ISFSI Re Required Notification of Receipt of All Required Regulatory Approvals of the Proposed Transfer Actions and Documentary Evidence of Required Insurance2015-09-23023 September 2015 ISFSI and Waterford 3 Steam Electric Station and ISFSI Re Required Notification of Receipt of All Required Regulatory Approvals of the Proposed Transfer Actions and Documentary Evidence of Required Insurance CNRO-2015-00018, Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1.2015-08-20020 August 2015 Entergy - Relief Request Number RR EN-15-2 - Proposed Alternative to Use ASME Code Case N-786-1, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, Section XI, Division 1. CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015 Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division 2022-05-26
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and 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 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) 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 ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23103A2732023-04-25025 April 2023 Enclosuresponses to Q&A ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities 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 PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report 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 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme ML22308A2572022-11-0404 November 2022 Decommissioning International - Response to Request for Additional Information for the Proposed Amended IP2 Master Trust Agreement W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN052203, Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2022-05-18018 May 2022 Response to the Second Round of Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. ML22132A1692022-05-12012 May 2022 Response to Requests for Additional Information Related to Exemption Request and License Amendment Request to Revise the Facility'S Emergency Plan W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors PNP 2022-012, Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition2022-04-21021 April 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition 0CAN032201, Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2022-03-0909 March 2022 Response to the Request for Additional Information Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 0CAN022201, Response to the Second Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping2022-02-17017 February 2022 Response to the Second Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping ML22034A6032022-02-0303 February 2022 Response to Request for Additional Information - Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E for Low-level Radioactive Waste Shipments ML22034A7882022-02-0303 February 2022 Response to Requests for Additional Information - Related to Post Shutdown Decommissioning Activities Report ML22003A1932022-01-0303 January 2022 Response to Requests for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device 2CAN112104, Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)2021-11-12012 November 2021 Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP) 2CAN112105, Response to Request for Additional Information Concerning Relief Request ANO2-RR-21-002 Support the Repair of the Reactor Vessel Closure Head Penetration 462021-11-0707 November 2021 Response to Request for Additional Information Concerning Relief Request ANO2-RR-21-002 Support the Repair of the Reactor Vessel Closure Head Penetration 46 2CAN102103, Response to Request for Additional Information Concerning Relief Request ANO2-R&R-012 Support the Repair of the Reactor Vessel Closure Head Penetration 462021-10-12012 October 2021 Response to Request for Additional Information Concerning Relief Request ANO2-R&R-012 Support the Repair of the Reactor Vessel Closure Head Penetration 46 0CAN102101, Final Request for Additional Information Concerning Generic Letter 2004-022021-10-0404 October 2021 Final Request for Additional Information Concerning Generic Letter 2004-02 W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual 0CAN092102, Response to Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping2021-09-23023 September 2021 Response to Request for Additional Information License Amendment Request for One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping 0CAN092101, Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-09-14014 September 2021 Unit 2 - Revised Proprietary Demarcation in Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping 0CAN072102, Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-07-22022 July 2021 Response to Request for Additional Information (Follow-up) - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping W3F1-2021-0041, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System2021-06-0202 June 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System 2CAN052103, Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)2021-05-24024 May 2021 Response to Request for Additional Information Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP) NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary 0CAN042101, Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description2021-04-0505 April 2021 Response to Request for Additional Information Reduction of Commitment to the Entergy Operation'S Quality Assurance Program Manual Description ML21063A2442021-02-22022 February 2021 Enclosure 4 - Response to Request for Additional Information Related to Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of ECP Supply Piping in Accordance with 10 CFR 50.55a(z)(1) (Non-Proprietary) 0CAN022101, Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping2021-02-22022 February 2021 Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling Pond Supply Piping CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device W3F1-2020-0062, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62020-12-15015 December 2020 Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 1CAN122001, Responses to Request for Additional Information for the Request for Relief Related to American Society of Mechanical Engineers(Asme) Code Case N-770-5 Supplemental Examination Requirements - ANO1-ISI-0342020-12-10010 December 2020 Responses to Request for Additional Information for the Request for Relief Related to American Society of Mechanical Engineers(Asme) Code Case N-770-5 Supplemental Examination Requirements - ANO1-ISI-034 0CAN112001, Relief Request No. EN-20-RR-001, Revision 1 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in Class 2 and 3 Systems, Section XI, Div 12020-11-17017 November 2020 Relief Request No. EN-20-RR-001, Revision 1 - Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in Class 2 and 3 Systems, Section XI, Div 1 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device CNRO-2020-00021, Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-0192020-11-0909 November 2020 Response to Request for Additional Information Regarding Relief Requests GG-ISI-020 and RBS-ISI-019 1CAN102002, Additional Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values2020-10-0505 October 2020 Additional Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values 2024-01-12
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Entergy Operations, Inc.
Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Ron Gaston Director Nuclear Licensing 10 CFR 2.202 CNRO-2021-00002 January 28, 2021 NRC Region IV Administrator U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511
Subject:
Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 are Complete, Element L Arkansas Nuclear One, Units 1 & 2 Indian Point Energy Center, Units 2 & 3 Docket Nos. 50-313 & 50-368 Docket Nos. 50- 247 & 50-286 License Nos. DPR-51 & NPF-6 License Nos. DPR- 26 & DPR-64 Grand Gulf Nuclear Station, Unit 1 Palisades Nuclear Plant Docket No. 50-416 Docket 50-255 License No. NPF-29 License No. DPR-20 River Bend Station, Unit 1 Waterford 3 Steam Electric Station Docket No. 50-458 Docket No. 50-382 License No. NPF-47 License No. NPF-38
Reference:
U.S. Nuclear Regulatory Commission (NRC) letter to Entergy (Entergy Nuclear Operations, Inc. and Entergy Operations, Inc.), Confirmatory Order, NRC Inspection Report 05000416/2017014, and NRC Investigation Reports 4-2016-004 and 4-2017-021, dated March 12, 2018 (ACCESSION No.: ML18072A191)
Confirmatory Order EA-17-132/EA-17-153 modified the above operating licenses to include specific elements to address willful violations. As required by Section V, Element L, the enclosure provides Entergys basis for concluding the terms of this Confirmatory Order are complete. The other appropriate Regional Administrators are copied on this notification.
Should you have any questions or require additional information, please contact John Giddens, Senior Manager, Fleet Regulatory Assurance, at (601) 368-5756.
I declare under penalty of perjury; the foregoing is true and correct.
Executed on January 28, 2021.
Respectfully, Ron Gaston RWG/jjn/jas
CNRO-2021-00002 Page 2 of 2
Enclosure:
Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element L cc:
John Dinelli (ANO)
Riley Keele (ANO)
Robert Franssen (GGN)
Jeff Hardy (GGN)
Darrell Corbin (PLP)
Barbara Dotson (PLP)
Anthony Vitale (IP)
Mahvash Mirzai (IP)
Steve Vercelli (RBS)
Timothy Schenk (RBS)
John Ferrick (WF3)
Paul Wood (WF3)
NRC Region I Administrator NRC Project Manager (Indian Point)
NRC Senior Resident Inspector (Indian Point)
NRC Region Ill Administrator NRC Project Manager (Palisades)
NRC Senior Resident Inspector (Palisades)
NRC Region IV Administrator - addressee NRC Project Manager (Arkansas Nuclear One)
NRC Senior Resident Inspector (Arkansas Nuclear One)
NRC Project Manager (Grand Gulf)
NRC Senior Resident Inspector (Grand Gulf)
NRC Project Manager (River Bend)
NRC Senior Resident Inspector (River Bend)
NRC Project Manager (Waterford)
NRC Senior Resident Inspector (Waterford)
NRC Document Control Desk
Enclosure CNRO-2021-00002 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element L
Enclosure CNRO-2021-00002 Page 1 of 6 Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element L The Nuclear Regulatory Commission (NRC) issued Confirmatory Order EA-17-132/EA-17-153 to Entergy (Entergy Nuclear Operations, Inc., and Entergy Operations, Inc.) as a result of a successful alternate dispute resolution (Reference 1).Section V of the Confirmatory Order modified Entergy License Nos. DRP-51, NPF-6, NPF-29, DPR-26, DPR-64, DPR-20, DPR-35, NPF-47 and NPF-38 to include Elements A through L. This enclosure responds to Section V, Element L for License Nos. DRP-51, NPF-6, NPF-29, DPR-26, DPR-64, DPR-20, NPF-47 and NPF-38. 1 Notifications to the NRC when Actions Are Completed, Element L Upon completion, Entergy will submit in writing to the Region IV Administrator, its basis for concluding that the terms of the Confirmatory Order have been completed.
Entergy Response, Element L The following is a summary of Entergy's basis for concluding that the terms of the Confirmatory Order have been completed. 2 Communications with Site Workers, Element A Within 1 month of the issuance date of the Confirmatory Order, a licensee senior executive at each Entergy site and the corporate nuclear headquarters will communicate with workers the circumstances leading to this Confirmatory Order, that willful violations will not be tolerated, and, as a result, Entergy will be undertaking efforts to confirm whether others are engaging in such conduct at any of its sites. The communication will stress the importance of procedural adherence, ensuring that documents are complete and accurate, and of potential consequences for engaging in willful violations. This message will be balanced with the recognition that people do make mistakes and when that happens, it is Entergy's expectation that its employees and contractors will identify and document issues accordingly.
These communications were completed between March 3, 2018 and April 11, 2018. Entergy assessed these communications for content and assignment. The NRC inspected these communications and provided observations to improve documentation of receipt and acknowledgement in future communications (Reference 6). Entergy committed to document receipt and to conduct surveys associated with the communications (Reference 4). Entergy assessed the future communications discussed in Reference 6 and found the communications and commitments properly implemented. Element A communications were closed by the NRC in the NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report (Reference 7). 3 1 This enclosure does not include a response for DPR-35 based on the license transfer in August of 2019.
2 Previous year summary of actions taken are contained in Reference 3, Reference 5 and Reference 9.
3 NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report (Reference 7) applies to DPR-51, NPF-6, NPF-29, NPF-47, and NPF-38.
Enclosure CNRO-2021-00002 Page 2 of 6 Communications with Site Workers, Element B Within 6 months of the completion of Element A, Entergy will conduct semi-annual communications with workers in the Entergy fleet reemphasizing its intolerance of willful misconduct and updating the workforce on the status of compliance with this Confirmatory Order until December 31, 2019. Starting in 2020, Entergy will conduct annual training emphasizing its intolerance of willful misconduct.
The six-month communications were conducted in September/October 2018. The subsequent semi-annual communications were conducted in March/April 2019, and September/October 2019. Entergy assessed theses communications and the associated commitments made in Reference 4 and found the implementation acceptable. To address the Element B requirement for 2020 annual training, Entergy implemented a computer-based training (CBT) module in 2019. Entergy assessed this training in both 2019 and 2020 and found the implementation acceptable. Entergy Internal Audits conducted an audit of the 2020 training and found the implementation acceptable. The NRC concluded that Indian Point was complying with the requirements of the Confirmatory Order in 2018, 2019, and through September 2020 (References 10 and 11 ). Element B communications were closed in the NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report (Reference 7). The annual training component was left open pending NRC inspection of the calendar year 2020 training implementation.
Causal Evaluation of Previous Corrective Actions to Deter Willful Violations, Element C Within 6 months of the issuance date of the Confirmatory Order, Entergy will perform a causal evaluation, informed by site evaluations, to determine why prior fleet-wide corrective actions from Confirmatory Orders and other willful violations issued after January 1, 2009, were not fully successful in preventing or minimizing instances of willful misconduct across the fleet. The causal evaluation will include the following elements:
- 1. Problem identification;
- 2. Root cause, extent of condition (including an assessment of work groups that perform NRC regulated activities to determine whether those workers are engaging in willful misconduct),
and extent of cause evaluation;
- 3. Corrective actions, with time frame for their completion; and
- 4. Safety culture attributes.
Entergy performed five station-level root cause evaluations and two fleet-level root cause evaluations to accomplish the objectives set forth in the Confirmatory Order. The last approval of these evaluations occurred on August 28, 2018. Entergy assessed this element in 2019 and implemented actions to address identified gaps. Entergy assessed this element in 2020 and found the implementation acceptable. The NRC concluded that Indian Point was complying with the requirements of the Confirmatory Order in 2018, 2019, and through September 2020 (References 10 and 11 ). The NRC reviewed this information in January 2020 and found the cause evaluations acceptable (Reference 7). The NRC left Element C open pending additional NRC inspection of the use of the corrective action program to evaluate willful misconduct and completion of the associated effectiveness review. The 2020 effectiveness review found action implementation effective as discussed in Element D.
Enclosure CNRO-2021-00002 Page 3 of 6 Causal Evaluation of Previous Corrective Actions to Deter Willful Violations, Element D Entergy will identify specific criteria necessary to perform annual effectiveness reviews of the corrective actions. The annual effectiveness reviews will include insights from fleet and individual site performance. Entergy will perform annual effectiveness reviews for three years.
Entergy will modify its corrective actions, as needed, based on the results of the annual effectiveness reviews.
Entergy identified the specific criteria necessary to perform the annual effectiveness reviews of the corrective actions. The first effectiveness review using these criteria to assess 2018 and first quarter 2019 data was conducted in May 2019. The second effectiveness review assessing 2019 data was conducted in December 2019. Both effectiveness reviews found gaps and actions were initiated to correct these gaps. Entergy assessed this element in both 2019 and 2020 and found implementation acceptable. The NRC concluded that Indian Point was complying with the requirements of the Confirmatory Order in 2018, 2019, and through September 2020 (References 10 and 11 ). The NRC reviewed this information in January 2020 and found the effectiveness reviews completed at that time for the specified criteria to be acceptable (Reference 7). The NRC left Element D open pending NRC inspection of the completion of the remaining Confirmatory Order effectiveness review. The third effectiveness review assessing 2020 data was conducted in October 2020. This effectiveness review found the implementation of the actions to be effective.
Causal Evaluation of Previous Corrective Actions to Deter Willful Violations, Element E For the Grand Gulf Nuclear Station, the evaluation described in Element C will address the three violations that are the subject of this ADR mediation session (refer to the NRC's letter dated November 20, 2017).
The three violations that were the subject of the ADR mediation session were addressed in two Grand Gulf Root Cause Evaluations. Entergy assessed this element in 2019 and found implementation acceptable. The NRC reviewed this information in January 2020 and found the cause evaluations acceptable (Reference 7). The NRC closed Element E in the NRC Confirmatory Order (EA-17-132 and EA-17-153) in Reference 7.
Causal Evaluation of Previous Corrective Actions to Deter Willful Violations, Element F Corrective actions identified as a result of the above evaluations will be implemented within 18 months of completion of the evaluation unless they involve a plant modification.
The actions specified by the two fleet and five station root causes were completed within 18 months. The actions taken as a result of the 2019 effectiveness reviews were completed within 18 months of identification. Entergy assessed this element in 2019 and 2020 and found the implementation to be acceptable. The NRC reviewed this information in January 2020 and found the actions to date acceptable (Reference 7). The NRC left Element F open after this inspection pending NRC inspection of any actions specified from future effectiveness reviews.
The 2020 effectiveness review was acceptable, and no additional actions were needed.
Enclosure CNRO-2021-00002 Page 4 of 6 Organizational Health Survey, Elements G, H and I G - Within 12 months of the issuance date of the Confirmatory Order, the Grand Gulf Nuclear Station, as well as all Entergy fleet sites, will conduct an organizational health survey developed by a third-party and designed, in part, to identify safety culture concerns that could contribute to willful misconduct.
H - A second organizational health survey will be conducted within 18 months of completion of the survey in Element G.
I - If safety culture concerns are identified through the survey, Entergy will document and initiate corrective actions within 2 months of the concern identification to mitigate the likelihood of willful misconduct occurring.
Entergy conducted the two organizational health surveys as specified. Entergy assessed Elements G, H and I in 2019 and 2020 and found the implementation to be acceptable. The NRC concluded that Indian Point was complying with the requirements of the Confirmatory Order in 2018, 2019, and through September 2020 (References 10 and 11). The NRC reviewed this information in January 2020 and found the survey data acceptable. The NRC closed Elements G, Hand I in the NRC Confirmatory Order (EA-17-132 and EA-17-153) in Reference 7.
Notifications to the NRC When Actions Are Completed, Element J Within 1 month of completion of Element C, Entergy will submit written notification to the appropriate Regional Administrators.
Entergy provided the specified notification via Reference 2. Entergy assessed this element in 2019 and found it acceptable. The NRC reviewed the 2018 and 2019 notifications in January 2020 and found the 2018 and 2019 notifications acceptable. Refer to the NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report (Reference 7).
Notifications to the NRC When Actions Are Completed, Element K By December 31 of each calendar year from 2018 through 2020, Entergy will provide in writing to the appropriate Regional Administrators a summary of the actions implemented across the fleet as a result of this Confirmatory Order and the results of any effectiveness reviews performed.
Entergy provided the specified notifications for 2018 and 2019 via References 3 and 5. Entergy assessed this element in 2019 and 2020 and found it acceptable. The NRC reviewed the 2018 and 2019 notifications in January 2020 and found the 2018 and 2019 notifications acceptable.
Refer to the NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report (Reference 7). This element remains open pending NRC inspection of Entergy's 2020 notification. Entergy provided the 2020 notification via Reference 9.
Enclosure CNRO-2021-00002 Page 5 of 6 Notifications to the NRC when Actions Are Completed, Element L Upon completion, Entergy will submit in writing to the Region IV Regional Administrator its basis for concluding that the terms of the Confirmatory Order have been completed.
This notification provides the Element L basis for concluding the terms of the Confirmatory Order are complete.
References:
- 1) U.S. Nuclear Regulatory Commission (NRC) letter to Entergy (Entergy Nuclear Operations, Inc. and Entergy Operations, Inc.), "Confirmatory Order, NRC Inspection Report 05000416/2017014, and NRC Investigation Reports 4-2016-004 and 4-2017-021," dated March 12, 2018 (ACCESSION No.:
ML18072A191)
- 2) Entergy Nuclear Operations, Inc. and Entergy Operations, Inc. letter to the NRC, "Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element J," CNRO-2018-00039, dated September 27, 2018 (ACCESSION No.: ML18270A430)
- 3) Entergy Nuclear Operations, Inc. and Entergy Operations, Inc. letter to the NRC, "Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K," CNRO-2018-00051, dated December 28, 2018 (ACCESSION No.: ML18362A251)
- 4) Entergy Nuclear Operations, Inc. and Entergy Operations, Inc. letter to the NRC, "Entergy Response to Confirmatory Order EA-17-132/EA-17-153,"
CNRO-2019-00013, dated March 21, 2019 (ACCESSION No.:
ML19081A270)
- 5) Entergy Nuclear Operations, Inc. and Entergy Operations, Inc. letter to the NRC, "Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K," CNRO-2019-00030, dated December 30, 2019 (ACCESSION No.: ML19364A214)
- 6) NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report. NRC IR-ANO 05000313/2019014 AND 05000368/2019014, NRC IR- GGN 05000416/2019012, NRC IR- RBS 05000458/2019013, NRC IR-WF3 05000382/2019012, dated April 4, 2019 (ACCESSION No.:
ML 19098867)
- 7) NRC Confirmatory Order (EA-17-132 and EA-17-153) Follow-up Inspection Report. NRC IR-ANO 05000313/2020010 and 05000368/2020010, NRC IR
- GGN 05000416/2020011, NRC IR- RBS 05000458/2020010, and NRC IR-WF3 05000382/2020011, dated March 20, 2020 (ACCESSION No.:
ML20086J157)
Enclosure CNRO-2021-00002 Page 6 of 6
- 8) NRC letter to Entergy Operations, Inc., River Bend Station - NRC Inspection Report 05000458/2020012, Investigation Report 4-2019-013 and Notice of Violation, dated September 29, 2020 (ACCESSION No.: ML20273A235)
- 9) Entergy Nuclear Operations, Inc. and Entergy Operations, Inc. letter to the NRC, "Entergy Response to Confirmatory Order EA-17-132/EA-17-153, Element K," CNRO-2020-00023, dated December 17, 2020 (ACCESSION No.: ML20352A355)
- 10) Indian Point Entergy Center, Units 2 and 3 - Integrated Inspection Report, 05000247/2019004 and 05000286/2019004 dated February 10, 2020 (ACCESSION No.: ML20042E476)
- 11) Indian Point Entergy Center, Unit 3 - Integrated Inspection Report, 05000286/2020003 dated October 28, 2020 (ACCESSION No.:
ML20303A069)