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Issue date | Title | |
---|---|---|
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated 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 Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems 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 Shutdown | 11 December 1996 | Undetected 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 Shutdown | 5 December 1997 | Recent 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, & FitzPatrick | 5 May 1999 | Unanticipated 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 Position | 27 September 2021 | Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position |
ML021020362 | 9 April 2002 | Application for Amendment to Facility Operating License Re Revision of Safety Limits and Instrumentation Setpoints |
ML021410289 | 15 May 2002 | Transmittal of Ginna Station Emergency Action Level (EAL) Technical Basis, Rev. 028 |
ML030850035 | 20 March 2003 | Revision to Emergency Plan Implementing Procedures |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML032760521 | 22 September 2003 | 2 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 |
ML040680907 | 1 March 2004 | R.E.Ginna - Application for Technical Specification Change Regarding Mode Change Limitations |
ML041330148 | 23 January 2004 | Issuance of Renewed Facility Operating License No. DPR-18 for R. E. Ginna Nuclear Power Plant, Technical Specification (Appendix a) |
ML042260359 | 6 August 2004 | Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process |
ML042470114 | 27 August 2004 | R. E. Ginna, Proposed Changes to the Previously Submitted Revision to Safety Limits and Instrumentation Setpoints |
ML050770204 | 14 March 2005 | R. 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 |
ML051260181 | 5 May 2005 | R. E. Ginna Nuclear Power Plant, Technical Specifications, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process |
ML080670419 | 7 March 2008 | CDBI Findings |
ML092100302 | 10 November 2008 | Updated Final Safety Analysis Report, Rev. 21, Chapter 7, Instrumentation and Controls Through Chapter 10, Steam and Power Conversion System |
ML12037A116 | 21 December 2011 | R. E. Ginna - Emergency Action Level Changes |
ML13141A272 | 15 May 2013 | R. E. Ginna Nuclear Power Plant - Resolution Path and Schedule for Generic Safety Issue (GSI) - 191 Closure |
ML14191A255 | 10 July 2014 | Nine 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 |
ML15166A075 | 4 June 2015 | Application 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) |
ML16180A160 | 5 May 2016 | Revision 26 to the Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls |
ML16209A218 | 26 July 2016 | Application 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. |
ML16280A402 | 6 October 2016 | License 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. |
ML17138A123 | 3 May 2017 | Exelon Nuclear Radiological Emergency Plan Addendum Revisions, Including Revision 3 to EP-AA-1006, Addendum 3 and Revision 4 to EP-AA-1012, Addendum 3 |
ML17249A451 | 28 December 1979 | Discussion of TMI Lessons Learned Short-Term Requirements. |
ML17250A361 | 2 July 1980 | Comments 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 |
ML17250A706 | 22 October 1980 | Forwards Comments on Selected Topics in Preliminary Clarification of TMI Action Plan Requirements |
ML17250A827 | 15 December 1980 | Forwards 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 |
ML17251A919 | 18 December 1986 | Rev 0 to Implementation Rept EWR 2799, Reactor Vessel Level Monitoring Sys. |
ML17254A216 | 21 February 1985 | Proposed Tech Specs Re Operability & Surveillance Requirements for NUREG-0737 Required Equipment (Generic Ltr 83-37) |
ML17254A906 | 7 August 1984 | Forwards Response to 840604 Request for Addl Info Re NUREG-0737,Item II.F.2 Concerning Inadequate Core Cooling Instrumentation |
ML17254A944 | 14 September 1984 | Proposed Tech Specs Re Operability & Surveillance Requirements for Certain NUREG-0737 Required Equipment |
ML17254B036 | 30 November 1984 | NUREG-0737,Suppl 1,SPDS Safety Analysis. |
ML17255A483 | 31 October 1983 | Safety 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) |
ML17255A560 | 29 November 1983 | Discusses 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. |
ML17256A550 | 10 March 1983 | Advises 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 |
ML17256A638 | 15 April 1983 | Responds 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 |
ML17258A479 | 19 January 1982 | Forwards Status of NUREG-0737 Items W/Jan 1982 Schedular Commitment Dates |