Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
IR 05000275/2023002 | 14 August 2023 | Quarterly Integrated Inspection Report 05000275/2023002 and 05000323/2023002- August 7, 2023 |
ML23241A546 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System |
ML23241A586 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems |
ML23241A659 | 25 May 2023 | 7 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management |
DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update | 23 March 2023 | Independent Spent Fuel Storage Installation, Emergency Plan Update |
ML23012A217 | 9 February 2023 | Issuance of Amendment Nos. 244 and 245 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition |
IR 05000275/2022010 | 27 January 2023 | Biennial Problem Identification and Resolution Inspection Report 05000275/2022010 and 05000323/2022010 |
DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions | 26 July 2022 | License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions |
DCL-22-052, Emergency Plan Update | 6 July 2022 | Emergency Plan Update |
ML21305A103 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management |
ML21305A099 | 11 October 2021 | 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System |
DCL-20-092, License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition | 3 December 2020 | License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition |
DCL-20-076, Technical Specification Bases | 10 September 2020 | Technical Specification Bases |
ML20268A367 | 30 June 2020 | 5 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System |
ML20106E463 | 6 March 2020 | 2020-02-DRAFT Operating Test |
ML20097A446 | 6 March 2020 | 2020-02-FINAL Operating Test |
DCL-18-077, Independent Spent Fuel Storage Installation - Appendix D, Revision 5.00, Emergency Action Level Technical Basis Manual | 4 October 2018 | Independent Spent Fuel Storage Installation - Appendix D, Revision 5.00, Emergency Action Level Technical Basis Manual |
ML18276A249 | 26 September 2018 | Enclosure 1 - Diablo Canyon Power Plant Emergency Plan Revision Numbers for Emergency Plan Sections and Appendices |
DCL-18-070, Technical Specification Bases, Revision 11 | 11 September 2018 | Technical Specification Bases, Revision 11 |
ML17179A019 | 21 June 2017 | PG&E Response to NRC Request for Additional Information Regarding License Amendment Request 16-04, Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, 'Development of Emergency Action Levels for Non-Passive .. |
ML17206A059 | 31 December 2016 | Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 3, Design of Structures, Components, Equipment, and Systems |
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 11, Radioactive Waste Management | 31 December 2016 | Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 11, Radioactive Waste Management |
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 |
ML17206A050 | 31 December 2016 | Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 11, Radioactive Waste Management |
ML17206A061 | 31 December 2016 | Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System |
DCL-16-126, Revision 10 to Technical Specification Bases | 30 December 2016 | Revision 10 to Technical Specification Bases |
ML16321A243 | 20 October 2016 | 2016-10 Final Written Exam |
ML16336A573 | 20 October 2016 | Diablo-2016-10 Draft Written Examination |
ML16145A325 | 25 April 2016 | 2016-04 - Final Operating Test |
ML15204A222 | 27 August 2015 | Issuance of Amendment Nos. 219 and 221, Adopt Technical Specifications Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) |
DCL-15-087, Revision to TS 3.4.15 for License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) | 6 August 2015 | Revision to TS 3.4.15 for License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) |
DCL-15-059, Technical Specification Bases, Revision 9 | 5 May 2015 | Technical Specification Bases, Revision 9 |
ML14251A041 | 11 August 2014 | 08 Final Operating Test |
DCL-14-058, License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294) | 28 July 2014 | License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294) |
ML14209B079 | 28 July 2014 | License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294). Part 2 |
ML14209B075 | 28 July 2014 | License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294). Part 1 |
ML14279A079 | 20 June 2014 | 08 Draft Operating Test |
DCL-13-092, Technical Specification Bases, Revision 8 | 16 September 2013 | Technical Specification Bases, Revision 8 |
ML102010084 | 24 January 2011 | Issuance of Amendment Nos. 209 and 211, Revise Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions |
DCL-10-036, Response to NRC RAI Regarding License Amendment Request 09-02, Revision to Technical Specification 3.4.15, 'Rcs Leakage Detection Instrumentation,' Operability Requirements and Actions for Rcs. | 9 April 2010 | Response to NRC RAI Regarding License Amendment Request 09-02, Revision to Technical Specification 3.4.15, 'Rcs Leakage Detection Instrumentation,' Operability Requirements and Actions for Rcs. |
ML100500536 | 8 February 2010 | Inservice Inspection Report for Fifteenth Refueling Outage |
ML091960177 | 3 July 2009 | License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for RCS Leakage Detection Instrumentation |
DCL-09-046, Submittal of Fifteenth Refueling Outage Inservice Inspection Report | 22 June 2009 | Submittal of Fifteenth Refueling Outage Inservice Inspection Report |
DCL-09-020, Updated Emergency Plan Implementing Procedures | 30 March 2009 | Updated Emergency Plan Implementing Procedures |
IR 05000275/2008004 | 3 November 2008 | IR 05000275-08-004, 05000323-08-004; 7/1/08 - 9/30/08; Diablo Canyon Power Plant Units 1 and 2; Equipment Alignment, Fire Protection, and Operability Evaluations |
IR 05000275/2008002 | 1 May 2008 | IR 05000275-08-002; 05000323-08-002; on 1/1 - 3/31/08; Diablo Canyon Power Plant, Units 1 and 2; Fire Protection, Maintenance Effectiveness, and Occupational Radiation Safety |
ML081220464 | 1 May 2008 | IR 05000275-08-002; 05000323-08-002; on 1/1 - 3/31/08; Diablo Canyon Power Plant, Units 1 and 2; Fire Protection, Maintenance Effectiveness, and Occupational Radiation Safety |
NOC-AE-07002231, Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) | 7 November 2007 | Request for Relaxation of Requirements from Revision 1 of Order EA-03-009 Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head Penetrations (Relief Request RR-ENG-2-46) |
DCL-07-097, License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b) | 15 October 2007 | License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b) |
IR 05000275/2007003 | 1 August 2007 | IR 05000275-07-003, 05000323-07-003, on 04/01/2007 - 06/30/2007, Diablo Canyon Power Plant Units 1 and 2; Maintenance Effectiveness |
ML070440494 | 21 March 2007 | Tech Spec Pages for Amendments 194 and 195 Regarding Steam Generator Tube Integrity Technical Specifications |
ML070190214 | 19 January 2007 | Units, 1 and 2 - Tech Spec Pages for Amendments 192 and 193 Technical Specification 1.1 Definitions and Technical Specification 3.4.16 Reactor Coolant System Specific Activity |
DCL-06-130, Response to NRC Request for Additional Information Regarding License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) | 22 November 2006 | Response to NRC Request for Additional Information Regarding License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) |
DCL-06-061, License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) | 30 May 2006 | License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449) |
DCL-06-008, License Amendment Request 06-01 Revision to Technical Specification 1.1, Definitions, and Technical Specification 3.4.16, RCS Specific Activity. | 25 January 2006 | License Amendment Request 06-01 Revision to Technical Specification 1.1, Definitions, and Technical Specification 3.4.16, RCS Specific Activity. |
ML052580510 | 14 September 2005 | 9/14/05 Diablo Canyon Pp, Unit 2 - Response to NRC Bulletin 2003-02,Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity (Tac. MC0535) |
DCL-05-067, Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 27 May 2005 | Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
ML051030399 | 5 April 2005 | Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity |
DCL-05-008, Day Response to NRC BL-03-002, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used | 8 February 2005 | Day Response to NRC BL-03-002, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used |
ML060940697 | 7 February 2005 | 02-2005-Draft Operating Exam |
ML060940698 | 7 February 2005 | 02-2005-Final Operating Exam |
DCL-04-141, Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. 'Steam Generator (SG) Tube Surveillance Program.' & 5.6.10 | 28 December 2004 | Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. 'Steam Generator (SG) Tube Surveillance Program.' & 5.6.10 |
DCL-04-146, Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors | 26 October 2004 | Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors |
DCL-04-089, Response to June 14 and July 6, 2004, NRC Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, 'Steam Generator (SG) Tube Surveillance Program,' & 5.6.10. | 30 July 2004 | Response to June 14 and July 6, 2004, NRC Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, 'Steam Generator (SG) Tube Surveillance Program,' & 5.6.10. |
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 |
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 |
ML030520331 | 20 February 2003 | Technical Specification |
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. |
ML023240494 | 20 November 2002 | /20/02, RAI, Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity |
ML023020065 | 28 October 2002 | Tech Spec Pages for Amendments 155 and 155, Revision of TS 3.9.4 Containment Penetrations |
ML023010434 | 21 October 2002 | Technical Specification Re Containment Penetrations |
DCL-02-109, Day Response to NRC Bulletins 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs. | 12 September 2002 | Day Response to NRC Bulletins 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs. |
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 |
ML20205B230 | 25 March 1999 | Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990125-28 |
ML20155C070 | 23 October 1998 | Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Converting to ITS |
Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality | 20 April 1998 | Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality |
NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation |
ML17083C404 | 16 March 1992 | Forwards Nonproprietary WCAP-13038 & Proprietary WCAP-13039, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis For.... Proprietary WCAP-13039 Withheld (Ref 10CFR2.790) |
ML16341G487 | 30 November 1991 | Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. |
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 |
NRC Generic Letter 1990-06 | 25 June 1990 | NRC Generic Letter 1990-006: Resolution of Generic Issue, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-Temp. Overpressure Protection for Light-Water Reactors, Pursuant to 10 CFR 50354 (F) |
ML20148D949 | 15 March 1988 | Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls |
ML20215E291 | 11 June 1985 | Requests NRR Assume Lead Responsibility for Technical Evaluation of Applicability of Subsection IWV-3427 of ASME Code,Section XI Re Leak Rate Tests of RCS Pressure Isolation Valves |
ML20112C891 | 17 December 1984 | Draft Tech Specs for Diablo Canyon Units 1 & 2 |
ML20049J002 | 11 February 1982 | Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EP OP-15 Re Loss of Feedwater Flow,Ep OP-20 Re Excessive RCS Leakage & EP OP-32 Re Rod Ejection.Revised Table of Contents Encl |
ML20005C063 | 4 November 1981 | Response to Applicant 811015 Third Set of Interrogatories. Pressurizer Heating Sys Components,Including Power Operated Relief & Block Valves & Compliance W/Acceptance Criteria Discussed.Certificate of Svc Encl.Related Correspondence |
ML20005C067 | 4 November 1981 | Response to NRC 811014 Interrogatories.Pressurizer Heater Sys Component Compliance w/safety-grade Design Criteria Discussed.Joint Intervenors 811030 Affidavit Encl.Related Correspondence |
ML20040A972 | 11 April 1980 | Emergency Operating Procedure OP-20,Revision 1, Excessive RCS Leakage. Related Correspondence |
ML20236B440 | 16 October 1974 | Safety Evaluation Supporting Util 730710 Application for OL |