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Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
JPN-87-051, Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl28 September 1987Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl
ML02116063825 April 2002Tech Spec Pages for Amendment 211 to Revise the Post Accident Monitoring Instrumentation Technical Specifications
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML03245018029 August 2003Improved Technical Specification Pages
ML03321026221 November 2003Technical Specifications Bases Pages for Indian Point Nuclear Generating Unit No. 2, License Amendment, Issuance of Amendment, Conversion to Improved Technical Specifications
ML05108004214 April 2005Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors
ML05109038031 March 2005Technical Specification Bases
ML0523702318 August 2005Technical Specification Bases
ML05272027311 July 2007Current Facility Operating License DPR-64, Technical Specifications, Revised 12/27/2017
ML0806704197 March 2008CDBI Findings
ML11280A1336 October 2010Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
ML12090A78431 January 2012Entergy 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)
ML12090A79431 January 2012Entergy 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)
ML12090A79731 January 2012Entergy 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)
ML12339A55931 January 2012Official 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)
ML12339A56931 January 2012Official 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)
ML12339A57231 January 2012Official 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)
ML14122A3037 July 2014Issuance of Amendments Technical Specification Task Force Traveler (TSTF) 432, Change in Technical Specifications End States (WCAP-16294)
ML14287A30017 September 2014Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
ML15222B1399 September 2013ENT000706 - NRC Enforcement Manual, Rev. 9 (Sept. 9, 2013)
ML17311A01813 May 1994New York State EAL Upgrade Project Verification & Validation Rept.
ML18041A0296 July 1994Forwards Emergency Action Level Verification & Validation Rept.
ML18163A13824 May 2018Revision 19 to IP-EP-AD13, Emergency Action Level Technical Bases
ML18177A40125 June 2018LTR-18-0261 Paul Blanch, Energy Consultant, Letter Safety Study of Algonquin Natural Gas Pipelines, Westchester County, New York
ML18212A19017 September 2018Renewed Facility Operating License DPR-64, Technical Specifications, Appendix a
ML19284A8018 October 2019IPEC IP-EP-AD13, Rev. 20, Emergency Action Level Technical Bases.
ML20010H1505 January 1981Util Response to 801211 Notice of Proposed Imposition of Civil Penalty
ML20059C83221 July 1993Summary 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
ML20100K21820 March 1985Revised Emergency Plan Implementing Procedures,Including Rev 6 to IP-1001 Re Determining Magnitude of Release,Rev 5 to IP-1003 Re Obtaining Meterological Data & Rev 4 to IP-1004 Re Midas Computer Sys
ML20101N16230 June 1992Forwards Completed Survey for ERDS Communications & Description of Erds.Data Point Library Also Encl
ML20125D1534 December 1992Forwards 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
ML20128D8611 February 1993Forwards Changes to Data Point Library for ERDS
ML20157A12712 May 2020IP-EP-AD13, Revision 21, Emergency Action Level Technical Bases
ML20207S28413 March 1987Revised Emergency Plan Implementing Procedures,Including Rev 3 to IP-1028, Core Damage Assessment, Rev 6 to IP-1041, Personnel Monitoring for Eof,Tsc.Osc & Control Room Personnel & Rev 12 to IP-1050, Accountability
ML21145A07210 May 2021Rev. 22 to IP-EP-AD-13, Emergency Action Level Technical Bases
NL-03-137, to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications11 September 2003to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
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