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| Issue date | Title | |
|---|---|---|
| ML22234A169 | 22 August 2022 | R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) |
| ML22118B143 | 28 April 2022 | Supplemental Information No. 2 for R.E. Ginna Nuclear Power Plant to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b |
| 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 |
| ML20339A027 | 20 November 2020 | 9 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls, Sections 7.1 Through 7.7 |
| ML20339A221 | 20 November 2020 | Technical Specifications Bases, Rev 101 |
| ML19150A471 | 10 May 2019 | Revision 28 to Updated Final Safety Analysis Report, Chapter 7, Sections 7.1 Thru 7.7 |
| ML19150A511 | 10 May 2019 | Revision 90 to Technical Specification Bases |
| ML18033A734 | 26 January 2018 | EP-AA-1012, Addendum 3, Revision 5, R. E. Ginna Nuclear Power Plant Emergency Action Levels. |
| 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 |
| 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. |
| 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. |
| ML16180A160 | 5 May 2016 | Revision 26 to the Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls |
| 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) |
| 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 |
| ML13141A272 | 15 May 2013 | R. E. Ginna Nuclear Power Plant - Resolution Path and Schedule for Generic Safety Issue (GSI) - 191 Closure |
| ML12037A116 | 21 December 2011 | R. E. Ginna - Emergency Action Level Changes |
| ML092100302 | 10 November 2008 | Updated Final Safety Analysis Report, Rev. 21, Chapter 7, Instrumentation and Controls Through Chapter 10, Steam and Power Conversion System |
| ML080670419 | 7 March 2008 | CDBI Findings |
| 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 |
| 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 |
| ML042470114 | 27 August 2004 | R. E. Ginna, Proposed Changes to the Previously Submitted Revision to Safety Limits and Instrumentation Setpoints |
| 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 |
| 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) |
| 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 |
| ML030850035 | 20 March 2003 | Revision to Emergency Plan Implementing Procedures |
| ML021410289 | 15 May 2002 | Transmittal of Ginna Station Emergency Action Level (EAL) Technical Basis, Rev. 028 |
| ML021020362 | 9 April 2002 | Application for Amendment to Facility Operating License Re Revision of Safety Limits and Instrumentation Setpoints |
| 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 |
| 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 |
| 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 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 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 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| 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 |
| ML17264A471 | 8 May 1996 | Proposed Tech Specs,Correcting Typos |
| 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 |
| ML17263B059 | 8 May 1995 | LER 95-003-00:on 950407,inadvertent Automatic SI Actuation Occurred When Technician Unblocked SIAS Due to Misleading Procedural Direction.Pressurizer Pressure Channel P-431 Bistable Proving Switch reinstated.W/950508 Ltr |
| ML17309A559 | 7 November 1994 | Forwards Response to NRC 940901 RAI Re Eals,Eals Annotated Classification Criteria Based on Response to NRC Rais,Rev 1 to OSSI-92-402A-4-REG, Re Ginna EALs Technical Bases & Rev 1 to Ossi 92-402A-2-REG, Fission Product Barrier.... |
| ML17263A835 | 7 November 1994 | Rev 1 to Fission Product Barrier Evaluation. |
| ML17263A833 | 11 October 1994 | Rev 1 to Re Ginna EALs Technical Bases. |
| 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 |
| ML18041A029 | 6 July 1994 | Forwards Emergency Action Level Verification & Validation Rept. |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML17311A018 | 13 May 1994 | New York State EAL Upgrade Project Verification & Validation Rept. |
| 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 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
| Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
| 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) |
| ML17309A474 | 28 February 1992 | Forwards Emergency Response Data Sys (ERDS) Data Point Library Sheets.Requests That NRC Provide Computer Modem for PPCS No Later than 920501,in Order to Meet Scheduled Installation Date for Hardware |