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 Issue dateTitleFromTo
NRC Generic Letter 1988-0517 March 1988NRC Generic Letter 1988-005: Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR PlantsMiraglia F
Office of Nuclear Reactor Regulation
NRC Generic Letter 1988-077 April 1988NRC 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 Specification2 August 1988NRC Generic Letter 1988-012: Removal of Fire Protection Requirements from Technical SpecificationsMiraglia F
Office of Nuclear Reactor Regulation
NRC Generic Letter 1991-1717 October 1991NRC Generic Letter 1991-017: Generic Safety Issue 29, Bolting Degradation or Failure in Nuclear Power Plants.Partlow J
Office of Nuclear Reactor Regulation
ML20059C67319 August 1993Intervenor Exhibit I-MFP-84,consisting of 930202 Rept DC2-91-MM-N069 D14, CVCS Unidentified LeakageAFFILIATION NOT ASSIGNED
IR 05000275/199201624 August 1993Intervenor Exhibit I-MFP-137,consisting of Insp Rept Re Dockets 50-275/92-16 & 50-323/92-16,dtd 920707NRC 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 1995Degradation 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 1995Degradation 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 2002Diablo 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 Integrity17 May 2002Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary IntegrityPacific Gas & Electric
Womack L
Office of Nuclear Reactor Regulation
Document Control Desk
IR 05000275/20020031 August 2002IR 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 AreasWilliam Jones
NRC/RGN-IV/DRP/RPB-E
Pacific Gas & Electric
Rueger G
ML02324049420 November 2002/20/02, RAI, Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary IntegrityShukla 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 2003Response 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 Integrity18 November 200390-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary IntegrityPacific 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 Reactors27 July 200460-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 ReactorsPacific Gas & Electric
Womack L
Office of Nuclear Reactor Regulation
Document Control Desk
ML10319032527 October 2010Lr - FW: Regional Inspection SpreadsheetNRC Region 4
Greg Pick
IR 05000275/201000817 November 2010IR 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 ProgramsO'Keefe N
NRC/RGN-IV/DRS/EB2
Pacific Gas & Electric
Conway J
DCL-12-117, 2011 Annual Commitment Change Summary Report20 November 20122011 Annual Commitment Change Summary ReportPacific 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 Operations31 December 2016Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of OperationsPacific 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
ML17206A05331 December 2016Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of OperationsPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML20268A36930 June 20205 to Updated Final Safety Analysis Report, Chapter 13, Conduct of OperationsPacific 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
ML21305A10211 October 20216 to Updated Final Safety Analysis Report, Chapter 13, Conduct of OperationsPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML21305A09911 October 20216 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML23241A63325 May 20237 to Updated Final Safety Analysis Report, Chapter 13, Conduct of OperationsPacific Gas & ElectricOffice of Nuclear Reactor Regulation
ML23241A54625 May 20237 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant SystemPacific Gas & ElectricOffice of Nuclear Reactor Regulation