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 | |
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 | |
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 | |
ML17206A062 | 31 December 2016 | Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted) | Pacific Gas & Electric | Office 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 2016 | Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 6, Engineered Safety Features (Redacted) | Pacific Gas & Electric | Office 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 System | 31 December 2016 | Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML17206A061 | 31 December 2016 | Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML20268A367 | 30 June 2020 | 5 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML20268A362 | 30 June 2020 | 5 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML20268A365 | 30 June 2020 | 5 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
IR 05000275/2021011 | 10 September 2021 | Design Basis Assurance Inspection (Programs) Report 05000275/2021011 and 05000323/2021011 | Vincent Gaddy Region 4 Engineering Branch 1 | Pacific Gas & Electric Welsch J |
ML21305A099 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML21305A096 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML21305A092 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
IR 05000275/2022011 | 9 August 2022 | Design Basis Assurance Inspection (Teams) Inspection Report 05000275/2022011 and 05000323/2022011 | Vincent Gaddy NRC/RGN-IV/DORS | Pacific Gas & Electric Gerfen P |
ML23241A546 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML23241A400 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML23241A149 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |