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Issue date | Title | From | To | |
---|---|---|---|---|
NRC Generic Letter 1988-05 | 17 March 1988 | NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants | Miraglia F Office of Nuclear Reactor Regulation | |
NRC Generic Letter 1988-07 | 7 April 1988 | NRC Generic Letter 1988-007: Modified Enforcement Policy Relating to 10 CFR 50.49 Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants. | Miraglia F Office of Nuclear Reactor Regulation | |
NRC Generic Letter 1988-12, Removal of Fire Protection Requirements from Technical Specification | 2 August 1988 | NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical Specifications | Miraglia F Office of Nuclear Reactor Regulation | |
NRC Generic Letter 1991-17 | 17 October 1991 | NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants. | Partlow J Office of Nuclear Reactor Regulation | |
ML20059C673 | 19 August 1993 | Intervenor Exhibit I-MFP-84,consisting of 930202 Rept DC2-91-MM-N069 D14, CVCS Unidentified Leakage | AFFILIATION NOT ASSIGNED | |
IR 05000275/1992016 | 24 August 1993 | Intervenor Exhibit I-MFP-137,consisting of Insp Rept Re Dockets 50-275/92-16 & 50-323/92-16,dtd 920707 | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) Johnson P | |
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. | Grimes B Office of Nuclear Reactor Regulation | |
Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | 5 January 1995 | Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. | Grimes B K Office of Nuclear Reactor Regulation | |
DCL-02-033, Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | 1 April 2002 | Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | Pacific Gas & Electric Womack L | Office of Nuclear Reactor Regulation Document Control Desk |
DCL-02-063, Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | 17 May 2002 | Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity | Pacific Gas & Electric Womack L | Office of Nuclear Reactor Regulation Document Control Desk |
IR 05000275/2002003 | 1 August 2002 | IR 05000275-02-003, IR 05000323-02-003, on 04/07/2002 to 07/06/2002, Pacific Gas and Electric. Co., Diablo Canyon Units 1 & 2, Postmaintenance Test, Access to Rad Sig Areas | William Jones NRC/RGN-IV/DRP/RPB-E | Pacific Gas & Electric Rueger G |
ML023240494 | 20 November 2002 | /20/02, RAI, Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity | Shukla G NRC/NRR/DLPM/LPD4 | Pacific Gas & Electric Rueger G |
DCL-03-008, Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | 31 January 2003 | Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. | Pacific Gas & Electric Oatley D | Office of Nuclear Reactor Regulation Document Control Desk |
DCL-03-151, 90-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity | 18 November 2003 | 90-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity | Pacific Gas & Electric Womack L | Office of Nuclear Reactor Regulation Document Control Desk |
DCL-04-095, 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors | 27 July 2004 | 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors | Pacific Gas & Electric Womack L | Office of Nuclear Reactor Regulation Document Control Desk |
ML103190325 | 27 October 2010 | Lr - FW: Regional Inspection Spreadsheet | NRC Region 4 Greg Pick | |
IR 05000275/2010008 | 17 November 2010 | IR 05000275-10-008, 05000323-10-008, on 08/16/2010 - 09/16/2010; Diablo Canyon Power Plant, Scoping of Nonsafety-Related Affecting Safety-Related Systems, and Review of License Renewal Aging Management Programs | O'Keefe N NRC/RGN-IV/DRS/EB2 | Pacific Gas & Electric Conway J |
DCL-12-117, 2011 Annual Commitment Change Summary Report | 20 November 2012 | 2011 Annual Commitment Change Summary Report | Pacific Gas & Electric Allen B | Office of Nuclear Reactor Regulation Document Control Desk |
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of Operations | 31 December 2016 | Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of Operations | 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 |
ML17206A053 | 31 December 2016 | Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of Operations | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML20268A369 | 30 June 2020 | 5 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations | 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 |
ML21305A102 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML21305A099 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML23241A633 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |
ML23241A546 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System | Pacific Gas & Electric | Office of Nuclear Reactor Regulation |