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 Issue dateTitle
ML21145A07210 May 2021Rev. 22 to IP-EP-AD-13, Emergency Action Level Technical Bases
ML20157A12712 May 2020IP-EP-AD13, Revision 21, Emergency Action Level Technical Bases
ML19284A8018 October 2019IPEC IP-EP-AD13, Rev. 20, Emergency Action Level Technical Bases.
ML18212A19017 September 2018Renewed Facility Operating License DPR-64, Technical Specifications, Appendix a
ML18177A40125 June 2018LTR-18-0261 Paul Blanch, Energy Consultant, Letter Safety Study of Algonquin Natural Gas Pipelines, Westchester County, New York
ML18163A13824 May 2018Revision 19 to IP-EP-AD13, Emergency Action Level Technical Bases
ML14287A30017 September 2014Updated 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 Sections17 September 2014Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
ML14122A3037 July 2014Issuance of Amendments Technical Specification Task Force Traveler (TSTF) 432, Change in Technical Specifications End States (WCAP-16294)
ML15222B1399 September 2013ENT000706 - NRC Enforcement Manual, Rev. 9 (Sept. 9, 2013)
NL-12-025, Supplement to Response to Request for Additional Information Regarding Emergency Action Level Changes16 March 2012Supplement to Response to Request for Additional Information Regarding Emergency Action Level Changes
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)
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)
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)
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)
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)
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)
NL-12-031, Response to Request for Additional Information Regarding Emergency Action Level Changes26 January 2012Response 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 Bases6 October 2010Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
ML11280A1336 October 2010Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
ML0806704197 March 2008CDBI Findings
ML05272027311 July 2007Current Facility Operating License DPR-64, Technical Specifications, Revised 12/27/2017
ML0523702318 August 2005Technical Specification Bases
ML05108004214 April 2005Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors
ML05109038031 March 2005Technical 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 2004Proposed Change to Technical Specifications Regarding Elimination of Hydrogen Recombiner Requirements, and Relaxation of Hydrogen Monitor Requirements (TSTF-447)
ML03321026221 November 2003Technical 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 Specifications11 September 2003to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
ML03245018029 August 2003Improved Technical Specification Pages
ML02116063825 April 2002Tech 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, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
NRC Generic Letter 1998-0228 May 1998NRC 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 Shutdown5 December 1997Recent 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 Shutdown11 December 1996Undetected 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 Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
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
ML18041A0296 July 1994Forwards Emergency Action Level Verification & Validation Rept.
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
ML17311A01813 May 1994New York State EAL Upgrade Project Verification & Validation Rept.
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
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
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
ML20128D8611 February 1993Forwards Changes to Data Point Library for ERDS
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
NRC Generic Letter 1992-0419 August 1992NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F)
ML20101N16230 June 1992Forwards Completed Survey for ERDS Communications & Description of Erds.Data Point Library Also Encl