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| Issue date | Title | |
|---|---|---|
| IR 05000286/2020004 | 28 January 2021 | Integrated Inspection Report 05000286/2020004 |
| ML20112J404 | 12 May 2020 | Final ASP Analysis - Indian Point 2 (LER 247-99-015) |
| ML20100F635 | 8 April 2020 | Expert Team Final Report |
| NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 | 21 November 2019 | Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 |
| NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments | 26 September 2019 | 50.59(d)(2) Summary Report of Changes, Tests and Experiments |
| IR 05000247/2018003 | 8 November 2018 | Integrated Inspection Report 05000247/2018003 and 05000286/2018003 |
| IR 05000247/2016004 | 3 February 2017 | Integrated Inspection Report 05000247/2016004 and 05000286/2016004 |
| NL-16-116, Response to Integrated Inspection Report 05000247/2016002 and 05000286/2016002; Denial of Green Non-Cited Violation 05000286/2016002-02 | 29 September 2016 | Response to Integrated Inspection Report 05000247/2016002 and 05000286/2016002; Denial of Green Non-Cited Violation 05000286/2016002-02 |
| ML16280A190 | 19 September 2016 | Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 6, Engineered Safety Features |
| NL-16-109, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 6, Engineered Safety Features | 19 September 2016 | Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26 - Chapter 6, Engineered Safety Features |
| ML16243A245 | 30 August 2016 | Integrated Inspection Report 05000247/2016002 and 05000286/2016002, April 1, 2016, Through June 30, 2016 |
| ML16244A781 | 30 August 2016 | Integrated Inspection Report 050000247/2016002 and 05000286/2016002 for Second Quarter 2016 |
| ML16177A018 | 8 June 2016 | Lr Hearing - (External_Sender) Ucs Bolt Assessment of Operability |
| ML16163A106 | 8 June 2016 | Lr Hearing - FW: Ucs Bolt Assessment of Operability |
| IR 05000247/2015003 | 5 November 2015 | IR 05000247/2015003, 05000286/2015003; 07/01/2015 - 09/30/2015; Indian Point Nuclear Generating (Indian Point), Units 2 and 3; Flood Protection Measures, Operability Evaluations, and Identification and Resolution of Problems |
| ML16057A534 | 9 December 2014 | NYS Exhibit 1 Re Entergy December 9, 2014 Letter on Proposed License Amendment Re Extending Containment Type a Leak Rate Testing Frequency to 15 Years |
| NL-14-128, Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years | 9 December 2014 | Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years |
| NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features | 17 September 2014 | Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features |
| ML14287A325 | 17 September 2014 | Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 6 - Engineered Safety Features |
| NL-14-043, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. | 31 March 2014 | Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima. |
| NL-14-014, Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years | 4 February 2014 | Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years |
| ML13291A306 | 26 September 2013 | Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 6 - Engineered Safety Features |
| NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 6 - Engineered Safety Features | 26 September 2013 | Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 6 - Engineered Safety Features |
| IR 05000286/2012004 | 8 November 2012 | IR 05000286-12-004; Entergy Nuclear Northeast; 7/1/12-9/30/12; Indian Point Nuclear Generating (Indian Point) Unit 3, NRC Integrated Inspection Report |
| IR 05000247/2012004 | 8 November 2012 | IR 05000247-12-004; Entergy Nuclear Northeast (Entergy); 7/1/12-9/30/12; Indian Point Nuclear Generating (Indian Point) Unit 2; Operability Determinations and Functionality Assessments |
| NL-12-117, Response to Request for Additional Information on Relief Request IP3-1SIRR-05 for Fourth Ten-Year Inservice Inspection Interval | 16 August 2012 | Response to Request for Additional Information on Relief Request IP3-1SIRR-05 for Fourth Ten-Year Inservice Inspection Interval |
| ML12200A056 | 19 July 2012 | Request for Additional Information Regarding Relief Request lP3-lSl-RR-05 |
| ML12339A477 | 30 March 2012 | Official Exhibit - NRC000045-00-BD01 - Donald (Donnie) Gene Harrison Cv |
| ML12090A686 | 30 March 2012 | NRC Pre-Filed Evidentiary Hearing Exhibit NRC000045 - Donald (Donnie) Gene Harrison Cv |
| ML12339A572 | 31 January 2012 | Official Exhibit - ENT000457-00-BD01 - NUREG/CR-7110, Vol. 2, State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 2) |
| ML12090A797 | 31 January 2012 | Entergy Pre-Filed Hearing Exhibit ENT000457, NUREG/CR-7110, Vol. 2, State-of-the-Art Reactor Consequence Analyses Project: Surry Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 2) |
| NL-12-028, Relief Request IP3-ISI-RR-05 for Fourth Ten-Year Inservice Inspection Interval | 30 January 2012 | Relief Request IP3-ISI-RR-05 for Fourth Ten-Year Inservice Inspection Interval |
| ML12334A797 | 21 December 2011 | Official Exhibit - NYS000281-00-BD01 - Environmental Report, Arkansas Nuclear One - Unit 2, Excerpted: Attachment E - Severe Accident Mitigation Analysis (Arkansas Er) |
| ML11355A237 | 21 December 2011 | New York State (NYS) Pre-Filed Evidentiary Hearing Exhibit NYS000281, Attachment E - Severe Accident Mitigation Alternatives Analysis, Arkansas Environmental Report |
| ML112710033 | 28 September 2011 | ROP Tabletop Examples and Results |
| IR 05000286/2011002 | 12 May 2011 | IR 05000286-11-002, on January 1, 2011 Through March 31, 2011, Indian Point Unit 3, Inservice Inspection and Operability Evaluations |
| ML12338A477 | 29 April 2011 | Official Exhibit - ENT000112-00-BD01 - Inspectable Area: Maintenance Effectiveness |
| ML12088A484 | 29 April 2011 | Entergy Pre-Filed Hearing Exhibit ENT000112, Inspectable Area: Maintenance Effectiveness |
| IR 05000247/2010005 | 11 February 2011 | IR 05000247-10-005; 10/01/2010-12/31/2010; Indian Point Nuclear Generating Unit 2; Post-Maintenance Testing; Occupational ALARA Planning and Controls; Identification and Resolution of Problems; Event Follow-up; and Other Activities |
| NL-10-109, CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/2010 | 12 October 2010 | CFR 50.59(d) Report Listing and Summary Report of the Changes, Tests and Experiments Implemented Between 04/20/2008 and 04/12/2010 |
| NL-10-107, (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22 | 6 October 2010 | (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22 |
| NL-10-074, Response to Request for Additional Information Regarding Generic Letter 2004-02 | 27 July 2010 | Response to Request for Additional Information Regarding Generic Letter 2004-02 |
| NL-10-001, Supplement to Proposed Exigent License Amendment Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time | 4 January 2010 | Supplement to Proposed Exigent License Amendment Regarding One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time |
| NL-09-167, Proposed Exigent License Amendment Re One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time | 15 December 2009 | Proposed Exigent License Amendment Re One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time |
| NL-09-138, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. | 19 November 2009 | Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. |
| NL-09-135, 10 CFR 50.59(d) Report for Indian Point Unit No. 3, of Changes, Tests and Experiments Implemented Between March 31, 2007 and April 15, 2009 or Utilized in Support of the UFSAR Update | 15 October 2009 | 10 CFR 50.59(d) Report for Indian Point Unit No. 3, of Changes, Tests and Experiments Implemented Between March 31, 2007 and April 15, 2009 or Utilized in Support of the UFSAR Update |
| ML092640061 | 24 September 2009 | Summary of Conference Call with Entergy on Proposed Response to a Request for Additional Information on Generic Letter 2004-02 |
| NL-09-099, Request for Extension of Completion Dates for Indian Point, Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, 'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-W | 29 July 2009 | Request for Extension of Completion Dates for Indian Point, Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, 'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wa |
| NL-08-153, Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wat | 17 October 2008 | Request for Extension of Completion Dates for Indian Point Units 2 and 3 Corrective Actions Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate |
| NL-08-101, Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance | 9 July 2008 | Proposed Changes to Technical Specifications Regarding Diesel Generator Endurance Test Surveillance |