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Issue date | Title | From | To | |
---|---|---|---|---|
ML17254A993 | 17 October 1984 | Forwards 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 Resolved | Rochester Gas and Electric Kober R | Office of Nuclear Reactor Regulation Paulson W |
ML17261A676 | 31 October 1987 | Rev 1 to Steam Generator Hydraulic Snubber Replacement Program. | Rochester Gas and Electric | |
ML17251B094 | 8 May 1988 | Rev 2 to Steam Generator Hydraulic Snubber Replacement Program. | Rochester Gas and Electric | |
ML17251A253 | 15 August 1988 | Rev 3 to Steam Generator Hydraulic Snubber Replacement Program. | Rochester Gas and Electric | |
NRC Generic Letter 1989-21 | 19 October 1989 | NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements | Partlow J Office of Nuclear Reactor Regulation | |
ML17250B077 | 27 November 1989 | Provides Info Re Status of USI Requirements,Per Generic Ltr 89-21.Status of Issues Encl | Rochester Gas and Electric Mecredy R | Office of Nuclear Reactor Regulation Andrea Johnson Office of Information Resources Management |
ML17263A287 | 13 May 1993 | Informs 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 84-04 | Rochester Gas and Electric Mecredy R | Office of Nuclear Reactor Regulation Andrea Johnson Office of Information Resources Management |
ML17309A550 | 15 July 1994 | Application 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-1431 | Rochester Gas and Electric Mecredy R | Office of Nuclear Reactor Regulation Andrea Johnson Office of Information Resources Management |
ML17263A748 | 2 August 1994 | Documents 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 Ltr | Rochester Gas and Electric Mecredy R | Office of Nuclear Reactor Regulation Andrea Johnson Office of Information Resources Management |
ML17265A694 | 28 June 1999 | Proposed 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 Piping | Rochester Gas and Electric | |
ML041330148 | 23 January 2004 | Issuance 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 |
ML061280549 | 1 May 2006 | License Amendment Request: Technical Specification Improvement Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process | Ginna Exelon Holm D | 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 |
ML092100440 | 10 November 2008 | Updated Final Safety Analysis Report, Rev. 21, Cover Through Chapter 3, Design of Structures, Components, Equipment, and Systems, Section 3.8.1.4.4.2 | Ginna Exelon | Office of Nuclear Reactor Regulation |
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) | Exelon James Barstow | Office of Nuclear Reactor Regulation Document Control Desk |
ML16034A139 | 3 February 2016 | Response 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 |
ML16180A140 | 5 May 2016 | Revision 26 to the Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems | 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 |
ML16180A156 | 5 May 2016 | Revision 26 to the Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems | Exelon | Office of Nuclear Reactor Regulation |
ML19150A511 | 10 May 2019 | Revision 90 to Technical Specification Bases | Exelon | Office of Nuclear Reactor Regulation |
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 |
ML19150A465 | 10 May 2019 | Revision 28 to Updated Final Safety Analysis Report, Chapter 5, Sections 5.1 Thru 5.8 | Exelon | Office of Nuclear Reactor Regulation |
ML19150A444 | 10 May 2019 | Revision 28 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems | Exelon | Office of Nuclear Reactor Regulation |
ML20339A221 | 20 November 2020 | Technical Specifications Bases, Rev 101 | 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 |
ML20339A020 | 20 November 2020 | 9 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.1 Through 3.7 | Exelon | Office of Nuclear Reactor Regulation |
ML20339A013 | 20 November 2020 | 9 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems, Section 5.1 Thru 5.8 | Exelon | Office of Nuclear Reactor Regulation |