Semantic search

Jump to navigation Jump to search
 Issue dateTitleFromTo
NRC Generic Letter 1998-0414 July 1998NRC 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 iRoe J
Office of Nuclear Reactor Regulation
ML17265A4721 December 1998Forwards 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
ML02221053730 July 2002R. E. Ginna Nuclear Power Plant Application for Renewed Operating License, Volume 2, Section 4.0, Page 4-1 - Appendix D, Page D-1Rochester Gas & Electric Corp
Mecredy R
Jack Cushing
Office of Nuclear Reactor Regulation
Document Control Desk
ML03153020323 May 2003Supplemental 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 05000244/200301211 December 2003IR 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-upLanning W
Division of Reactor Safety I
Rochester Gas & Electric Corp
Mecredy R
ML05094002530 March 2005Request for Approval of a Common Quality Assurance Program for Constellation Generation Group, LLCConstellation Generation Group
Heffley J
Office of Nuclear Reactor Regulation
Document Control Desk
ML05364008022 December 2005Response to Request for Additional Information Regarding Topics Described by Letter Dated November 10, 2005Exelon
Korsnick M G
Office of Nuclear Reactor Regulation
Document Control Desk
ML06138024911 July 2006Table of Contents, Safety Evaluation Related to Extended Power Uprate at R. E. Ginna Nuclear Power PlantMilano P
NRC/NRR/ADRO/DORL/LPLA
Ginna
Korsnick M
ML08071004129 February 2008R.E. Ginna, Supplement Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water ReactorsGinna
John Carlin
Office of Nuclear Reactor Regulation
Document Control Desk
ML09210030110 November 2008Updated Final Safety Analysis Report, Rev. 21, Chapter 4, Reactor Through Chapter 6, Engineered Safety FeaturesGinna
Exelon
Office of Nuclear Reactor Regulation
ML16180A1585 May 2016Revision 26 to the Updated Final Safety Analysis Report, Chapter 6, Engineered Safety FeaturesExelonOffice of Nuclear Reactor Regulation
ML19045A28215 February 2019R. 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 FrequenciesExelon
James Barstow
Office of Nuclear Reactor Regulation
Document Control Desk
ML19150A46810 May 2019Revision 28 to Updated Final Safety Analysis Report, Chapter 6, Sections 6.1 Thru 6.6ExelonOffice of Nuclear Reactor Regulation
ML20339A06520 November 20209 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features, Sections 6.1 Through 6.6ExelonOffice of Nuclear Reactor Regulation