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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
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
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
ML17206A06231 December 2016Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted)Pacific Gas & ElectricOffice of Nuclear Reactor Regulation
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted)31 December 2016Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted)Pacific Gas & ElectricOffice of Nuclear Reactor Regulation
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System31 December 2016Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML17206A06131 December 2016Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML20268A36730 June 20205 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML20268A36230 June 20205 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety FeaturesPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML20268A36530 June 20205 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary SystemsPacific Gas & ElectricOffice of Nuclear Reactor Regulation
IR 05000275/202101110 September 2021Design Basis Assurance Inspection (Programs) Report 05000275/2021011 and 05000323/2021011Vincent Gaddy
Region 4 Engineering Branch 1
Pacific Gas & Electric
Welsch J
ML21305A09911 October 20216 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML21305A09611 October 20216 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary SystemsPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML21305A09211 October 20216 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety FeaturesPacific Gas & ElectricOffice of Nuclear Reactor Regulation
IR 05000275/20220119 August 2022Design Basis Assurance Inspection (Teams) Inspection Report 05000275/2022011 and 05000323/2022011Vincent Gaddy
NRC/RGN-IV/DORS
Pacific Gas & Electric
Gerfen P
ML23241A54625 May 20237 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML23241A40025 May 20237 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary SystemsPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML23241A14925 May 20237 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety FeaturesPacific Gas & ElectricOffice of Nuclear Reactor Regulation