Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
ML21145A072 | 10 May 2021 | Rev. 22 to IP-EP-AD-13, Emergency Action Level Technical Bases |
ML20157A127 | 12 May 2020 | IP-EP-AD13, Revision 21, Emergency Action Level Technical Bases |
ML19284A801 | 8 October 2019 | IPEC IP-EP-AD13, Rev. 20, Emergency Action Level Technical Bases. |
ML18212A190 | 17 September 2018 | Renewed Facility Operating License DPR-64, Technical Specifications, Appendix a |
ML18177A401 | 25 June 2018 | LTR-18-0261 Paul Blanch, Energy Consultant, Letter Safety Study of Algonquin Natural Gas Pipelines, Westchester County, New York |
ML18163A138 | 24 May 2018 | Revision 19 to IP-EP-AD13, Emergency Action Level Technical Bases |
ML14287A300 | 17 September 2014 | Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections |
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections | 17 September 2014 | Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections |
ML14122A303 | 7 July 2014 | Issuance of Amendments Technical Specification Task Force Traveler (TSTF) 432, Change in Technical Specifications End States (WCAP-16294) |
ML15222B139 | 9 September 2013 | ENT000706 - NRC Enforcement Manual, Rev. 9 (Sept. 9, 2013) |
NL-12-025, Supplement to Response to Request for Additional Information Regarding Emergency Action Level Changes | 16 March 2012 | Supplement to Response to Request for Additional Information Regarding Emergency Action Level Changes |
ML12339A569 | 31 January 2012 | Official Exhibit - ENT000455-00-BD01 - NUREG-1935, State-of-the-Art Reactor Consequence Analyses (Soarca) Report, Draft Report for Public Comment (Jan. 2012) (Draft NUREG-1935) |
ML12339A559 | 31 January 2012 | Official Exhibit - ENT000456-00-BD01 - NUREG/CR-7110, Vol. 1, State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 1) |
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) |
ML12090A794 | 31 January 2012 | Entergy Pre-Filed Hearing Exhibit ENT000455, NUREG-1935, State-of-the-Art Reactor Consequence Analyses (Soarca) Report, Draft Report for Public Comment (Jan. 2012) (Draft NUREG-1935) |
ML12090A784 | 31 January 2012 | Entergy Pre-Filed Hearing Exhibit ENT000456, NUREG/CR-7110, Vol. 1, State-of-the-Art Reactor Consequence Analyses Project: Peach Bottom Integrated Analysis (Jan. 2012) (NUREG/CR-7110, Vol. 1) |
NL-12-031, Response to Request for Additional Information Regarding Emergency Action Level Changes | 26 January 2012 | Response to Request for Additional Information Regarding Emergency Action Level Changes |
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases | 6 October 2010 | Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases |
ML11280A133 | 6 October 2010 | Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases |
ML080670419 | 7 March 2008 | CDBI Findings |
ML052720273 | 11 July 2007 | Current Facility Operating License DPR-64, Technical Specifications, Revised 12/27/2017 |
ML052370231 | 8 August 2005 | Technical Specification Bases |
ML051080042 | 14 April 2005 | Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors |
ML051090380 | 31 March 2005 | Technical Specification Bases |
NL-04-134, Proposed Change to Technical Specifications Regarding Elimination of Hydrogen Recombiner Requirements, and Relaxation of Hydrogen Monitor Requirements (TSTF-447) | 22 October 2004 | Proposed Change to Technical Specifications Regarding Elimination of Hydrogen Recombiner Requirements, and Relaxation of Hydrogen Monitor Requirements (TSTF-447) |
ML033210262 | 21 November 2003 | Technical Specifications Bases Pages for Indian Point Nuclear Generating Unit No. 2, License Amendment, Issuance of Amendment, Conversion to Improved Technical Specifications |
NL-03-137, to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications | 11 September 2003 | to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications |
ML032450180 | 29 August 2003 | Improved Technical Specification Pages |
ML021160638 | 25 April 2002 | Tech Spec Pages for Amendment 211 to Revise the Post Accident Monitoring Instrumentation Technical Specifications |
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
ML18041A029 | 6 July 1994 | Forwards Emergency Action Level Verification & Validation Rept. |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
ML17311A018 | 13 May 1994 | New York State EAL Upgrade Project Verification & Validation Rept. |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
ML20059C832 | 21 July 1993 | Summary of 398th ACRS Meeting on 930610-11 in Bethesda,Md Re SECY-93-113,public Comments on Advanced LWR Severe Accident Plant performance,SECY-93-067 & Reactor Operating Experience Related to Salem Unit 2 & Indian Point Unit 3 |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
ML20128D861 | 1 February 1993 | Forwards Changes to Data Point Library for ERDS |
ML20125D153 | 4 December 1992 | Forwards Revised Page from Original ERDS Communications Description & Revised Survey Questionnaire,Indicating Change to Plant Attribute Library.Preliminary Testing Proved That Satisfactory Communication Will Occur W/Suspend/Resume |
NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
ML20101N162 | 30 June 1992 | Forwards Completed Survey for ERDS Communications & Description of Erds.Data Point Library Also Encl |