Semantic search
Jump to navigation
Jump to search
Issue date | Title | From | To | |
---|---|---|---|---|
NRC Generic Letter 1995-07 | 17 August 1995 | NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves | Crutchfield D Office of Nuclear Reactor Regulation | |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | Crutchfield D Office of Nuclear Reactor Regulation | |
Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve | 5 February 1996 | Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve | Crutchfield D Office of Nuclear Reactor Regulation | |
ML20132D030 | 18 June 1996 | Station,10CFR50.59 Summary Rept 940619-960618 | Exelon | |
Information Notice 1996-49, Thermally Induced Pressurization of Nuclear Power Facility Piping | 20 August 1996 | Thermally Induced Pressurization of Nuclear Power Facility Piping | Martin T Office of Nuclear Reactor Regulation | |
ML20133A929 | 12 December 1996 | Informs of Completed Evaluations & Design Change for Valves in Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power-Operated Gate Valves | Exelon Stanley H | Office of Information Resources Management |
Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections | 6 March 1997 | Problems Identified During Generic Letter 89-10 Closeout Inspections | Martin T Office of Nuclear Reactor Regulation | |
IR 05000456/1997012 | 17 October 1997 | Insp Repts 50-456/97-12 & 50-457/97-12 on 970414-0815. Violations Noted.Major Areas Inspected:Maint & Engineering | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | |
ML20198A015 | 18 June 1998 | 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept | Exelon | |
ML20210J895 | 29 July 1999 | Submits Other Actions,As Described,To Be Taken for Valves to Resolve Potential Pressure Locking Concerns,In Light of Extended Period for Valve Bonnet Natural Depressurization,In Response to GL 95-07, Pressure Locking & Thermal.. | Exelon Rod Krich | Office of Information Resources Management |
ML20210K986 | 30 July 1999 | Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs | NRC (Affiliation Not Assigned) | |
ML111790042 | 21 June 2011 | Mur Technical Evaluation, (Non-Proprietary Version), Attachment 7 to Braidwood Station, Units 1 & 2, Byron Station, Unit 1 & 2, Request for License Amendment Regarding Measurement Uncertainty Recapture (Mur) Power Uprate | Exelon | Office of Nuclear Reactor Regulation |
ML14045A002 | 31 January 2014 | NRR E-mail Capture - Braidwood/Byron Mur Package for Proprietary and Factual Error Review - Part 5 of 5 | Division of Operating Reactor Licensing Joel Wiebe | Exelon Holden L |
ML14045A006 | 31 January 2014 | NRR E-mail Capture - Braidwood/Byron Mur Package for Proprietary and Factual Error Review - Part 5 of 5 | Exelon Holden L | Division of Operating Reactor Licensing Joel Wiebe |
ML13281A000 | 7 February 2014 | Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate | Division of Operating Reactor Licensing Marilyn Evans | Exelon Pacilio M |
ML19170A012 | 19 June 2019 | Redacted Braidwood Station, Units 1 and 2 and Byron Station, Units 1 and 2 - Revision 17 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features | Mahesh Chawla Plant Licensing Branch III | Exelon Bryan Hanson |
ML20183A391 | 1 July 2020 | Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000456/2020012 and 05000457/2020012 | NRC/RGN-III/DRS/EB2 Santiago E | Exelon Bryan Hanson |
ML21137A238 | 17 May 2021 | Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features-Redacted | Haskell R Plant Licensing Branch III | Exelon Rhoades D |