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| Issue date | Title | |
|---|---|---|
| ML17261A608 | 10 July 1987 | Rev 3 to EWR 2799, Implementation Rept Reactor Vessel Level Monitoring Sys Ginna Station. |
| ML17261A815 | 4 January 1989 | Responds to Generic Ltr 88-17, Loss of Dhr. Util Will Comply W/Seven Applicable Expeditious Actions & Will Implement Procedures & Administrative Controls Prior to Next Planned Refueling Shutdown.Related Info Encl |
| ML17263A833 | 11 October 1994 | Rev 1 to Re Ginna EALs Technical Bases. |
| ML17263A835 | 7 November 1994 | Rev 1 to Fission Product Barrier Evaluation. |
| 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 |
| ML17264A471 | 8 May 1996 | Proposed Tech Specs,Correcting Typos |
| 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 |
| 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.... |
| ML17311A018 | 13 May 1994 | New York State EAL Upgrade Project Verification & Validation Rept. |
| ML18033A734 | 26 January 2018 | EP-AA-1012, Addendum 3, Revision 5, R. E. Ginna Nuclear Power Plant Emergency Action Levels. |
| ML18041A029 | 6 July 1994 | Forwards Emergency Action Level Verification & Validation Rept. |
| 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 |
| 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 |
| 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 |
| ML22234A169 | 22 August 2022 | R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) |
| 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 |