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Issue date | Title | From | To | |
---|---|---|---|---|
NRC Generic Letter 1998-04 | 14 July 1998 | NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i | Roe J Office of Nuclear Reactor Regulation | |
ML17265A472 | 1 December 1998 | Forwards Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment. | Rochester Gas and Electric Mecredy R | NRC (Affiliation Not Assigned) Vissing G Office of Information Resources Management |
ML022210537 | 30 July 2002 | R. E. Ginna Nuclear Power Plant Application for Renewed Operating License, Volume 2, Section 4.0, Page 4-1 - Appendix D, Page D-1 | Rochester Gas & Electric Corp Mecredy R | Jack Cushing Office of Nuclear Reactor Regulation Document Control Desk |
ML031530203 | 23 May 2003 | Supplemental Response to LRA Request for Additional Information (RAI) | Rochester Gas & Electric Corp Mecredy R | Arrighi R Office of Nuclear Reactor Regulation Document Control Desk |
IR 05000244/2003012 | 11 December 2003 | IR 05000244-03-012; on 10/07/03 - 10/28/03; R. E. Ginna Nuclear Power Plant; Special Inspection of a Containment Sump Screen Bypass Issue; Event Follow-up | Lanning W Division of Reactor Safety I | Rochester Gas & Electric Corp Mecredy R |
ML050940025 | 30 March 2005 | Request for Approval of a Common Quality Assurance Program for Constellation Generation Group, LLC | Constellation Generation Group Heffley J | Office of Nuclear Reactor Regulation Document Control Desk |
ML053640080 | 22 December 2005 | Response to Request for Additional Information Regarding Topics Described by Letter Dated November 10, 2005 | Exelon Korsnick M G | Office of Nuclear Reactor Regulation Document Control Desk |
ML061380249 | 11 July 2006 | Table of Contents, Safety Evaluation Related to Extended Power Uprate at R. E. Ginna Nuclear Power Plant | Milano P NRC/NRR/ADRO/DORL/LPLA | Ginna Korsnick M |
ML080710041 | 29 February 2008 | R.E. Ginna, Supplement Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors | Ginna John Carlin | Office of Nuclear Reactor Regulation Document Control Desk |
ML092100301 | 10 November 2008 | Updated Final Safety Analysis Report, Rev. 21, Chapter 4, Reactor Through Chapter 6, Engineered Safety Features | Ginna Exelon | Office of Nuclear Reactor Regulation |
ML16180A158 | 5 May 2016 | Revision 26 to the Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features | Exelon | Office of Nuclear Reactor Regulation |
ML19045A282 | 15 February 2019 | R. E. Ginna Nuclear Power Plant - License Amendment Request (LAR) to Revise Technical Specification (TS) 5.5.15, Containment Leakage Rate Testing Program, for Permanent Extension of Type a Leak Rate Test Frequencies | Exelon James Barstow | Office of Nuclear Reactor Regulation Document Control Desk |
ML19150A468 | 10 May 2019 | Revision 28 to Updated Final Safety Analysis Report, Chapter 6, Sections 6.1 Thru 6.6 | Exelon | Office of Nuclear Reactor Regulation |
ML20339A065 | 20 November 2020 | 9 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features, Sections 6.1 Through 6.6 | Exelon | Office of Nuclear Reactor Regulation |