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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
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position27 September 2021Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML0210203629 April 2002Application for Amendment to Facility Operating License Re Revision of Safety Limits and Instrumentation Setpoints
ML02141028915 May 2002Transmittal of Ginna Station Emergency Action Level (EAL) Technical Basis, Rev. 028
ML03085003520 March 2003Revision to Emergency Plan Implementing Procedures
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML03276052122 September 20032 to EPIP-1-0, Revision 32 to EAL Technical Basis, Revision 56 to EPIP 1-5, Revision 6 to EPIP 2-8, and Revision 8 to EPIP 2-17
ML0406809071 March 2004R.E.Ginna - Application for Technical Specification Change Regarding Mode Change Limitations
ML04133014823 January 2004Issuance of Renewed Facility Operating License No. DPR-18 for R. E. Ginna Nuclear Power Plant, Technical Specification (Appendix a)
ML0422603596 August 2004Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process
ML04247011427 August 2004R. E. Ginna, Proposed Changes to the Previously Submitted Revision to Safety Limits and Instrumentation Setpoints
ML05077020414 March 2005R. E. Ginna, Replacement Pages Associated with the Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process
ML0512601815 May 2005R. E. Ginna Nuclear Power Plant, Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process
ML0806704197 March 2008CDBI Findings
ML09210030210 November 2008Updated Final Safety Analysis Report, Rev. 21, Chapter 7, Instrumentation and Controls Through Chapter 10, Steam and Power Conversion System
ML12037A11621 December 2011R. E. Ginna - Emergency Action Level Changes
ML13141A27215 May 2013R. E. Ginna Nuclear Power Plant - Resolution Path and Schedule for Generic Safety Issue (GSI) - 191 Closure
ML14191A25510 July 2014Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
ML15166A0754 June 2015Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
ML16180A1605 May 2016Revision 26 to the Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
ML16209A21826 July 2016Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML16280A4026 October 2016License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing.
ML17138A1233 May 2017Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3
ML17249A45128 December 1979Discussion of TMI Lessons Learned Short-Term Requirements.
ML17250A3612 July 1980Comments on NRC Requirement Re Installation of Reactor Vessel Water Level Instrument at Facility.Requirement Is Unreasonable Due to Amount of Development Work Necessary to Implement Reliable Vessel Level Instrument
ML17250A70622 October 1980Forwards Comments on Selected Topics in Preliminary Clarification of TMI Action Plan Requirements
ML17250A82715 December 1980Forwards Responses to NRC 801031 Ltr Re Clarification of TMI Action Plan Requirements.Util Intends to Comply W/Nrc Requirements & Implementation Dates.Exceptions Are Discussed in Encl.Deviations Will Be Communicated
ML17251A91918 December 1986Rev 0 to Implementation Rept EWR 2799, Reactor Vessel Level Monitoring Sys.
ML17254A21621 February 1985Proposed Tech Specs Re Operability & Surveillance Requirements for NUREG-0737 Required Equipment (Generic Ltr 83-37)
ML17254A9067 August 1984Forwards Response to 840604 Request for Addl Info Re NUREG-0737,Item II.F.2 Concerning Inadequate Core Cooling Instrumentation
ML17254A94414 September 1984Proposed Tech Specs Re Operability & Surveillance Requirements for Certain NUREG-0737 Required Equipment
ML17254B03630 November 1984NUREG-0737,Suppl 1,SPDS Safety Analysis.
ML17255A48331 October 1983Safety Evaluation Report Related to a Full-Term Operating License for the R.E. Ginna Nuclear Power Plant.Docket No. 50-244.(Rochester Gas and Electric Company)
ML17255A56029 November 1983Discusses Proposals Received to Fulfill Regulatory Requirement Re Installation of Reactor Vessel Water Level Sys,In Response to Generic Ltr 83-12, Inadequate Core Cooling Instrumentation Sys.
ML17256A55010 March 1983Advises That Util Plans to Install Reactor Vessel Water Level Sys & Upgrade Core Exit Thermocouples for Inadequate Core Cooling Instrumentation Sys,Per Generic Ltr 82-12. Regulatory Commitment Schedules Under re-evaluation
ML17256A63815 April 1983Responds to Generic Ltr 82-33 (NUREG-0737,Suppl 1) Re Safety Parameter Display Sys,Detailed Control Room Design Reviews & Emergency Response Facilities.Proposed Response Schedule Encl
ML17258A47919 January 1982Forwards Status of NUREG-0737 Items W/Jan 1982 Schedular Commitment Dates
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