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Issue date | Title | From | To | |
---|---|---|---|---|
NRC Generic Letter 1990-05 | 15 June 1990 | NRC Generic Letter 1990-005: Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping | Partlow J Office of Nuclear Reactor Regulation | |
ML20044B184 | 10 July 1990 | Requests Approval of Temporary non-code Repair & Augmented Insp of Svc Water Piping,Per 900626 Telcon | FirstEnergy Shelton D | Office of Information Resources Management |
IR 05000346/1990013 | 10 August 1990 | Insp Rept 50-346/90-13 on 900605-0709.Noncited Violation Noted.Major Areas Inspected:Lers,Plant Operations,Refueling, Radiological Controls,Maint/Surveillance,Emergency Preparedness,Security,Engineering & Technical Support | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) Jackiw I | |
ML20056B272 | 20 August 1990 | Safety Evaluation Granting Relief from ASME Code Repair Requirements for ASME Code 3 Piping | Office of Nuclear Reactor Regulation | |
ML20059M592 | 26 September 1990 | Notice of Violation from Insp on 900417-0717.Violation Noted:Licensee Transferred Reactor Core Support Assembly from Temporary Storage & Installed in Reactor Vessel | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) Davis A | |
ML20066A401 | 21 December 1990 | Responds to Generic Ltr 90-06, Resolution of Generic Issue 70, 'Power-Operated Relief Valve & Block Valve Reliability' & Generic Issue 94, 'Addl Low-Temp Overpressure Protection for Lwrs,' Per 10CFR50.54(f) | FirstEnergy Shelton D | Office of Information Resources Management |
ML20077M172 | 7 August 1991 | Clarifies & Expands on Info Provided by Util Re Request for Relief to Allow Temporary non-code Repairs of Svc Water Piping in Accordance W/Nrc Generic Ltr 90-05 | FirstEnergy Shelton D | Office of Information Resources Management |
ML031140549 | 7 November 1991 | Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability | Partlow J Office of Nuclear Reactor Regulation | |
ML20099B050 | 20 July 1992 | Requests NRC Approval of Temporary non-code Repair of through-wall Leak Discovered in Svc Water Sys Piping at Unit 1,per Generic Ltr 90-05.W/one Oversize Drawing | Entergy INC. Shelton D | Office of Information Resources Management |
L-16-355, Proposed Alternative to Use ASME Code Case N-513-4 | 11 August 2017 | Proposed Alternative to Use ASME Code Case N-513-4 | FirstEnergy Harden P | Office of Nuclear Reactor Regulation Document Control Desk |