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 Issue dateTitleFromTo
ML17254A99317 October 1984Forwards Request for Exemption from Considering Large RCS Primary Loop Pipe Breaks in Structural Design Basis (GDC-4), in Response to Generic Ltr 84-04.Generic Issue A-2, Asymmetric Blowdown Loads on PWR Primary Sys ResolvedRochester Gas and Electric
Kober R
Office of Nuclear Reactor Regulation
Paulson W
ML17261A67631 October 1987Rev 1 to Steam Generator Hydraulic Snubber Replacement Program.Rochester Gas and Electric
ML17251B0948 May 1988Rev 2 to Steam Generator Hydraulic Snubber Replacement Program.Rochester Gas and Electric
ML17251A25315 August 1988Rev 3 to Steam Generator Hydraulic Snubber Replacement Program.Rochester Gas and Electric
NRC Generic Letter 1989-2119 October 1989NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) RequirementsPartlow J
Office of Nuclear Reactor Regulation
ML17250B07727 November 1989Provides Info Re Status of USI Requirements,Per Generic Ltr 89-21.Status of Issues EnclRochester Gas and Electric
Mecredy R
Office of Nuclear Reactor Regulation
Andrea Johnson
Office of Information Resources Management
ML17263A28713 May 1993Informs That Util in Process of Procuring Replacement SGs for Plant in Ref to NRC Ltr Re 10CFR50 Mod of GDC-4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Ruptures & GL 84-04Rochester Gas and Electric
Mecredy R
Office of Nuclear Reactor Regulation
Andrea Johnson
Office of Information Resources Management
ML17309A55015 July 1994Application for Amend to License DPR-18,proposing TS 3.5, Providing NRC W/Opportunity to Communicate at Early Stage Any Concerns W/Respect to Differences from NUREG-1431Rochester Gas and Electric
Mecredy R
Office of Nuclear Reactor Regulation
Andrea Johnson
Office of Information Resources Management
ML17263A7482 August 1994Documents Conversation Between J Tsao of NRC & G Wrobel of Rg&E Re Reduction in RCS Tavg.Requests NRC Concurrence by 940901 W/Info Discussed in LtrRochester Gas and Electric
Mecredy R
Office of Nuclear Reactor Regulation
Andrea Johnson
Office of Information Resources Management
ML17265A69428 June 1999Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR PipingRochester Gas and Electric
ML04133014823 January 2004Issuance of Renewed Facility Operating License No. DPR-18 for R. E. Ginna Nuclear Power Plant, Technical Specification (Appendix a)Rajender Auluck
NRC/NRR/DRIP/RLEP
Rochester Gas & Electric Corp
Mecredy R
ML0612805491 May 2006License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement ProcessGinna
Exelon
Holm D
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
ML09210044010 November 2008Updated Final Safety Analysis Report, Rev. 21, Cover Through Chapter 3, Design of Structures, Components, Equipment, and Systems, Section 3.8.1.4.4.2Ginna
Exelon
Office of Nuclear Reactor Regulation
ML15166A0754 June 2015Application 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)Exelon
James Barstow
Office of Nuclear Reactor Regulation
Document Control Desk
ML16034A1393 February 2016Response to Request for Additional Information - Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program..Exelon
David Gudger
Office of Nuclear Reactor Regulation
Document Control Desk
ML16180A1405 May 2016Revision 26 to the Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and SystemsExelonOffice of Nuclear Reactor Regulation
ML16180A1585 May 2016Revision 26 to the Updated Final Safety Analysis Report, Chapter 6, Engineered Safety FeaturesExelonOffice of Nuclear Reactor Regulation
ML16180A1565 May 2016Revision 26 to the Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected SystemsExelonOffice of Nuclear Reactor Regulation
ML19150A51110 May 2019Revision 90 to Technical Specification BasesExelonOffice of Nuclear Reactor Regulation
ML19150A46810 May 2019Revision 28 to Updated Final Safety Analysis Report, Chapter 6, Sections 6.1 Thru 6.6ExelonOffice of Nuclear Reactor Regulation
ML19150A46510 May 2019Revision 28 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 Thru 5.8ExelonOffice of Nuclear Reactor Regulation
ML19150A44410 May 2019Revision 28 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and SystemsExelonOffice of Nuclear Reactor Regulation
ML20339A22120 November 2020Technical Specifications Bases, Rev 101ExelonOffice 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
ML20339A02020 November 20209 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.1 Through 3.7ExelonOffice of Nuclear Reactor Regulation
ML20339A01320 November 20209 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Section 5.1 Thru 5.8ExelonOffice of Nuclear Reactor Regulation