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IR 05000275/202300214 August 2023Quarterly Integrated Inspection Report 05000275/2023002 and 05000323/2023002- August 7, 2023
ML23241A54625 May 20237 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System
ML23241A58625 May 20237 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems
ML23241A65925 May 20237 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management
DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update23 March 2023Independent Spent Fuel Storage Installation, Emergency Plan Update
ML23012A2179 February 2023Issuance of Amendment Nos. 244 and 245 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition
IR 05000275/202201027 January 2023Biennial 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 Definitions26 July 2022License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
DCL-22-052, Emergency Plan Update6 July 2022Emergency Plan Update
ML21305A10311 October 20216 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management
ML21305A09911 October 20216 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 Condition3 December 2020License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
DCL-20-076, Technical Specification Bases10 September 2020Technical Specification Bases
ML20268A36730 June 20205 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System
ML20106E4636 March 20202020-02-DRAFT Operating Test
ML20097A4466 March 20202020-02-FINAL Operating Test
DCL-18-077, Independent Spent Fuel Storage Installation - Appendix D, Revision 5.00, Emergency Action Level Technical Basis Manual4 October 2018Independent Spent Fuel Storage Installation - Appendix D, Revision 5.00, Emergency Action Level Technical Basis Manual
ML18276A24926 September 2018Enclosure 1 - Diablo Canyon Power Plant Emergency Plan Revision Numbers for Emergency Plan Sections and Appendices
DCL-18-070, Technical Specification Bases, Revision 1111 September 2018Technical Specification Bases, Revision 11
ML17179A01921 June 2017PG&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 ..
ML17206A05931 December 2016Diablo 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 Management31 December 2016Diablo 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 System31 December 2016Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
ML17206A05031 December 2016Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 11, Radioactive Waste Management
ML17206A06131 December 2016Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
DCL-16-126, Revision 10 to Technical Specification Bases30 December 2016Revision 10 to Technical Specification Bases
ML16321A24320 October 20162016-10 Final Written Exam
ML16336A57320 October 2016Diablo-2016-10 Draft Written Examination
ML16145A32525 April 20162016-04 - Final Operating Test
ML15204A22227 August 2015Issuance 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 2015Revision 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 95 May 2015Technical Specification Bases, Revision 9
ML14251A04111 August 201408 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 2014License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294)
ML14209B07928 July 2014License 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
ML14209B07528 July 2014License 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
ML14279A07920 June 201408 Draft Operating Test
DCL-13-092, Technical Specification Bases, Revision 816 September 2013Technical Specification Bases, Revision 8
ML10201008424 January 2011Issuance 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 2010Response 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.
ML1005005368 February 2010Inservice Inspection Report for Fifteenth Refueling Outage
ML0919601773 July 2009License 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 Report22 June 2009Submittal of Fifteenth Refueling Outage Inservice Inspection Report
DCL-09-020, Updated Emergency Plan Implementing Procedures30 March 2009Updated Emergency Plan Implementing Procedures
IR 05000275/20080043 November 2008IR 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 05000275/20080021 May 2008IR 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
ML0812204641 May 2008IR 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 2007Request 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 2007License 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 05000275/20070031 August 2007IR 05000275-07-003, 05000323-07-003, on 04/01/2007 - 06/30/2007, Diablo Canyon Power Plant Units 1 and 2; Maintenance Effectiveness
ML07044049421 March 2007Tech Spec Pages for Amendments 194 and 195 Regarding Steam Generator Tube Integrity Technical Specifications
ML07019021419 January 2007Units, 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 2006Response 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 2006License 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 2006License Amendment Request 06-01 Revision to Technical Specification 1.1, Definitions, and Technical Specification 3.4.16, RCS Specific Activity.
ML05258051014 September 20059/14/05 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 Reactors27 May 2005Relaxation Request for NRC Issuance of First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
ML0510303995 April 2005Response 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 Used8 February 2005Day 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
ML0609406977 February 200502-2005-Draft Operating Exam
ML0609406987 February 200502-2005-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.' & 5.6.1028 December 2004Response 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 Reactors26 October 2004Relaxation 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 2004Response 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 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 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 Integrity18 November 200390-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
ML03052033120 February 2003Technical 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 2003Response to NRC Request for Additional Information Regarding NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
ML02324049420 November 2002/20/02, RAI, Bulletin 2002-01 Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity
ML02302006528 October 2002Tech Spec Pages for Amendments 155 and 155, Revision of TS 3.9.4 Containment Penetrations
ML02301043421 October 2002Technical 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 2002Day 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 Integrity17 May 2002Submittal of 60-day Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
ML20205B23025 March 1999Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990125-28
ML20155C07023 October 1998Proposed 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 Criticality20 April 1998Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality
NRC Generic Letter 1995-1015 December 1995NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
ML17083C40416 March 1992Forwards 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)
ML16341G48730 November 1991Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants.
ML0311405497 November 1991Withdrawn 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 1990-0625 June 1990NRC 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)
ML20148D94915 March 1988Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls
ML20215E29111 June 1985Requests 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
ML20112C89117 December 1984Draft Tech Specs for Diablo Canyon Units 1 & 2
ML20049J00211 February 1982Public 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
ML20005C0634 November 1981Response 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
ML20005C0674 November 1981Response to NRC 811014 Interrogatories.Pressurizer Heater Sys Component Compliance w/safety-grade Design Criteria Discussed.Joint Intervenors 811030 Affidavit Encl.Related Correspondence
ML20040A97211 April 1980Emergency Operating Procedure OP-20,Revision 1, Excessive RCS Leakage. Related Correspondence
ML20236B44016 October 1974Safety Evaluation Supporting Util 730710 Application for OL