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 Issue dateTitle
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)
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
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
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-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
NRC Generic Letter 1985-0217 April 1985NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity
NRC Generic Letter 1985-0531 January 1985NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1985-0923 May 1985NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3
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)
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
NRC-86-3095, Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified9 January 1986Part 21 Rept Re Nonupper Head Injection Analog Versions of Reactor Vessel Water Level Instrumentation Sys.Initially Reported on 860109.Changes to Upgrade Steam Density Compensation Circuit Identified