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Issue date | Title | |
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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) |
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 |
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 |
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-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 |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC 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 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
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) |
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 |
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 Identified | 9 January 1986 | 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 Identified |