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 Issue dateTitleFromTo
NRC Generic Letter 1995-0717 August 1995NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate ValvesCrutchfield D
Office of Nuclear Reactor Regulation
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor VesselCrutchfield D
Office of Nuclear Reactor Regulation
Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve5 February 1996Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate ValveCrutchfield D
Office of Nuclear Reactor Regulation
ML20132D03018 June 1996Station,10CFR50.59 Summary Rept 940619-960618Exelon
Information Notice 1996-49, Thermally Induced Pressurization of Nuclear Power Facility Piping20 August 1996Thermally Induced Pressurization of Nuclear Power Facility PipingMartin T
Office of Nuclear Reactor Regulation
ML20133A92912 December 1996Informs of Completed Evaluations & Design Change for Valves in Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power-Operated Gate ValvesExelon
Stanley H
Office of Information Resources Management
Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections6 March 1997Problems Identified During Generic Letter 89-10 Closeout InspectionsMartin T
Office of Nuclear Reactor Regulation
IR 05000456/199701217 October 1997Insp Repts 50-456/97-12 & 50-457/97-12 on 970414-0815. Violations Noted.Major Areas Inspected:Maint & EngineeringNRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
ML20198A01518 June 199810CFR50.59 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,ReptExelon
ML20210J89529 July 1999Submits 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
ML20210K98630 July 1999Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related MovsNRC (Affiliation Not Assigned)
ML11179004221 June 2011Mur 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 UprateExelonOffice of Nuclear Reactor Regulation
ML14045A00231 January 2014NRR E-mail Capture - Braidwood/Byron Mur Package for Proprietary and Factual Error Review - Part 5 of 5Division of Operating Reactor Licensing
Joel Wiebe
Exelon
Holden L
ML14045A00631 January 2014NRR E-mail Capture - Braidwood/Byron Mur Package for Proprietary and Factual Error Review - Part 5 of 5Exelon
Holden L
Division of Operating Reactor Licensing
Joel Wiebe
ML13281A0007 February 2014Issuance of Amendments Regarding Measurement Uncertainty Recapture Power UprateDivision of Operating Reactor Licensing
Marilyn Evans
Exelon
Pacilio M
ML19170A01219 June 2019Redacted 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 FeaturesMahesh Chawla
Plant Licensing Branch III
Exelon
Bryan Hanson
ML20183A3911 July 2020Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000456/2020012 and 05000457/2020012NRC/RGN-III/DRS/EB2
Santiago E
Exelon
Bryan Hanson
ML21137A23817 May 2021Byron/Braidwood Stations - Revision 18 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features-RedactedHaskell R
Plant Licensing Branch III
Exelon
Rhoades D