Category:Letter type:DCL
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Pages in category "Letter type:DCL"
The following 200 pages are in this category, out of 1,253 total.
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- DCL-01-095, Response to NRC Request for Additional Information Re License Amendment Request 01-03, Expansion of Steam Generator Tube W* Alternate Repair Criteria for Indications in Westinghouse Explosive Tube Expansion (Wextex) Region.
- DCL-01-127, License Amendment Request 01-09, Revision to Diablo Canyon Power Plant Physical Security Program to Incorporate Diablo Canyon ISFSI & Associated Request for Exemption for Four 10CFR73.55 Requirements
- DCL-01-138, Special Report 00-01, Revision 1-90 Day Report, Results of Steam Generator Alternate Repair Criteria for Diablo Canyon Power Plant Unit 2 Ninth Refueling Outage
- DCL-02-004, Response to NRC Regulatory Issue Summary 2001-21
- DCL-02-014, Supplemental Information Regarding Implementation ASME Code Case N-597
- DCL-02-020, Supplement 1 to License Amendment Request 01-04 Revision to Technical Specifications 3.9.4 Containment Penetrations
- DCL-02-022, Response to NRC Request for Additional Information Re License Amendment Request 01-02
- DCL-02-023, Gregory M. Rueger, P G& E Co., Response to NRC Request for Additional Information Regarding Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented, Intersections in Steam Generator Tubing.
- DCL-02-028, Twenty-Day Answer to NRC Order for Interim Safeguards and Security Compensatory Measures
- DCL-02-033, Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
- DCL-02-038, License Amendment Request 02-02, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
- DCL-02-039, Emergency Plan Implementing Procedure Update
- DCL-02-041, Annual Technical Specification 5.6.1 Report for 2001
- DCL-02-042, Submittal of Proposed Changes to the DCPP Physical Security Program to Incorporate the Diablo Canyon ISFSI and Associated Request for Exemption to Four 10 CFR 73.55 Requirements
- DCL-02-044, License Amendment Request 02-03, Spent Fuel Cask Handling
- DCL-02-045, Response to Final NRC Request for Additional Information Re Supplement 3 to License Amendment Request 00-06, Alternate Repair Criteria for Axial PWSCC at Dented Intersections in Steam Generator Tubing.
- DCL-02-049, 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2000, Through December 31, 2001
- DCL-02-051, 2001 Annual Radiological Environmental Operating Report
- DCL-02-052, 2001 Annual Nonradiological Environmental Operating Report
- DCL-02-055, Clarification of the Twenty-Day Answer to NRC Order for Interim Safeguards and Security Compensatory Measures
- DCL-02-056, Revision 31 to EP G-1, Emergency Classification and Emergency Plan Activation.
- DCL-02-059, Comments Regarding April 17, 2002 End of Cycle Assessment Meeting
- DCL-02-061, Inservice Testing (IST) Program Plan, Revision 18
- DCL-02-062, Core Operating Limits Report, Cycle 12
- 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
- DCL-02-065, Special Report 02-01: Results of Steam Generator Tube Eddy Current Inspections During Tenth Refueling Outage
- DCL-02-066, Supplemental Answers to NRC Order for Interim Safeguards and Security Compensatory Measures
- DCL-02-067, Comments of James E. Tomkins on Draft Report NUREG-XXX, Technical Assessment Generic Issue 186: Potential Risk & Consequences of Heavy Load Drops in Nuclear Power Plants.
- DCL-02-070, Dcl 02-070 Change 20 to Revision 18 of the Physical Security Plan.
- DCL-02-076, June 2002 Monthly Operating Report for Diablo Canyon Power Plant Units 1 and 2
- DCL-02-078, Response to NRC Regulatory Issue Summary 2002-09; Preparation and Scheduling of Operator Licensing Examinations
- DCL-02-079, Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report
- DCL-02-089, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes
- DCL-02-095, Response to NRC Requests for Additional Information Regarding License Amendment Requests 01-04 and 01-05
- DCL-02-096, Inservice Inspection Report for Eleventh Refueling Outage
- DCL-02-097, License Amendment Request 02-05, Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement
- DCL-02-098, Special Report 02-02 - Results of Steam Generator Inspections for Eleventh Refueling Outage
- DCL-02-105, Emergency Plan Implementing Procedure Update
- DCL-02-107, Report of Full Compliance with NRC Order for Interim Safeguards & Security Compensatory Measures
- DCL-02-108, Change 21 to Revision 18 of the Physical Security Plan for Diablo Canyon Units 1 & 2
- DCL-02-109, Day Response to NRC Bulletins 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
- DCL-02-112, Response to Second NRC Request for Additional Information Re License Amendment Request 01-04, Revision to Technical Specification 3.9.4 Containment Penetrations, and License Amendment Request 01-05, Revision to Tech..
- DCL-02-114, Commitment Change Summary Report, January - December 2001
- DCL-02-115, License Amendment Request (LAR) 01-08, to Modify Technical Specification 3.4.11 & Licensing Basis to Credit Automatic Actuation of Class One Power Operated Relief Valves (Porvs) Instead of Pressurizer Safety Valves (Psvs)
- DCL-02-116, Letter Regards Inservice Testing Program Plan, Revision 19
- DCL-02-117, Changes in Licensing Basis Compliance from 10 CFR 70.24 to 10 CFR 50.68(b)
- DCL-02-125, License Amendment Request 02-06 Revisions to Technical Specifications 3.3.1 Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.
- DCL-02-140, Emergency Plan Implementing Procedure Update
- DCL-02-143, November 2002 Monthly Operating Report for Diablo Canyon Power Plant, Units 1 & 2
- DCL-03-005, Change 22 to Revision 18 of the Physical Security Plan
- DCL-03-006, Twenty-Day Response to NRC Order for Compensatory Measures Related to Access Authorization
- DCL-03-007, Response to Request for Additional Information for Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) Physical Security Program and Associated Revised Request for Exemption to Two 10 CFR 73.55 Requirements
- 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.
- DCL-03-009, Inservice Inspection Program Plan, Revision 2, Drawings104628, Sheets 1 - 52
- DCL-03-011, License Amendment Request 03-01, Revision to TS 3.3.1, Reactor Trip System Instrumentation
- DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation
- DCL-03-017, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Method for Diablo Canyon Unit 2 Cycle 12
- DCL-03-019, Revision to TS 3.5.2 - Increase in Completion Time for Charging Pump During Unit 1 Cycle 12 from 72 Hours to 7 Days
- DCL-03-020, Response to NRC Request for Additional Information Regarding License Amendment Request 02-03, Spent Fuel Cask Handling
- DCL-03-022, Day Response to NRC Order Modifying Licenses (EA-03-009)
- DCL-03-023, Request to Use an Alternative Method of Determining Probability of Detection for Diablo Canyon Unit 2 Steam Generator 4 Tube R44C45 Indication
- DCL-03-024, Emergency Plan Implementing Procedure Update
- DCL-03-026, Emergency Request for Approval to Use an Alternative Method of Determining Probability of Detection for Steam Generator 4 Tube R44C45 Indication
- DCL-03-027, Response to Request for Additional Information on Emergency Request for Approval to Use an Alternate Method of Determining Probability of Detection for Tube R44C45 Indication
- DCL-03-029, Core Operating Limits Report
- DCL-03-032, February 2003 Monthly Operating Report for Diablo Canyon, Units 1 & 2
- DCL-03-033, Core Operating Limits Report for Unit 1 Cycle 12
- DCL-03-034, License Amendment Request 03-05 Revision of Technical Specification 3.7.10, Control Room Ventilation System, TS 3.7.12, Auxiliary Building Ventilation System, and TS 5.5.11, Ventilation Filter Testing Program.
- DCL-03-045, 30-Day Response to NRC Bulletins 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles & 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response to N
- DCL-03-048, Annual Radiological Environmental Operating Report
- DCL-03-049, 2002 Annual Radioactive Effluent Release Report
- DCL-03-054, Special Report 03-01: Results of Steam Generator Tube Eddy Current Inspections During Eleventh Refueling Outage
- DCL-03-056, Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement
- DCL-03-060, License Amendment Request 03-06, Revision to Technical Specification 3.8.1, AC Sources - Operating.
- DCL-03-061, License Amendment Request 03-07, Revision to Technical Specifications (TS) 3.8.1 AC Sources - Operating & 3.8.4 DC Sources - Operating Surveillance Requirements
- DCL-03-064, Answer, Response and Request for Clarification in Response to April 29, 2003 Order Requiring Compliance with Revised Design Basis Threat for Operating Power Reactors
- DCL-03-065, Answer, Response and Request for Clarification in Response to April 29, 2003, Order for Compensatory Measures Related to Training Enhancements on Tactical and Firearms Proficiency and Physical Fitness Applicable to Amend Nuclear Power Pla
- DCL-03-067, License Amendment Request 03-08 Revision to Technical Specification 3.5.1, Emergency Core Cooling Systems/Accumulator.
- DCL-03-068, May 2003 Monthly Operating Report for Diablo Canyon Units 1 & 2
- DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation
- DCL-03-073, Emergency Plan Implementing Procedure Update
- DCL-03-074, Inservice Inspection Report for Eleventh Refueling Outage
- DCL-03-075, Core Operating Limits Report Cycle 12
- DCL-03-076, Response to NRC Questions on 2R11 Steam Generator Tube Inspections
- DCL-03-077, Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling
- DCL-03-078, Response to NRC Request for Additional Information Regarding License Amendment Request 03-10, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Methods for Cycle 12.
- DCL-03-079, Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation, & Revised Reactor Coolant System Flow Measurement
- DCL-03-080, Response to NRC Request for Additional Information Regarding License Amendment Request 03-03, Revision to TS 3.5.2 - Increase in Completion Time for Charging Pump During Unit 1 Cycle 12 from 72 Hours to 7 Days
- DCL-03-083, June 2003 Monthly Operating Report for Diablo Canyon Power Plant, Units 1 and 2
- DCL-03-091, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes
- DCL-03-092, Response to NRC Request for Additional Information Regarding License Amendment Request 02-05, Revision to TS Table 3.3.1-1, Reactor Trip System Instrumentation & Revised Reactor Coolant System Flow Measurement
- DCL-03-095, Supplement 1 to License Amendment Request 03-05, Revision of Technical Specification (TS) 3.7.10, Control Room Ventilation System (Crvs). TS 3.7.12. Auxiliary Building Ventilation System (Abvs). TS 3.7.13
- DCL-03-096, Day Response to Request for Information on Generic Letter 2003-01, Control Room Habitability
- DCL-03-097, Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
- DCL-03-101, Response to NRC Request for Additional Information Regarding License Amendment Request 02-04, Revision of TS 5.6.6 - Reactor Coolant System Pressure & Temperature Limits Report
- DCL-03-102, Change 23 to Revision 18 of Physical Security Plan
- DCL-03-109, Supplemental Information to Support License Amendment Request 03-10, Revised Steam Generator Voltage-Based Repair Criteria Probability of Detection Method for Unit 2 Cycle 12.
- DCL-03-110, Commitment Change Summary Report, 01/01 - 12/31/02
- DCL-03-111, License Amendment Request 03-12 Revision to Technical Specifications 3.3.1, RTS Instrumentation, and 3.3.2, ESFAS Instrumentation, Enclosures 1 - 4
- DCL-03-113, Response to NRC Questions on 1R11 Steam Generator Tube Inspections
- DCL-03-114, Response to NRC Questions Regarding License Amendment Request 02-03, Spent Fuel Cask Handling.
- DCL-03-117, Change 24 to Revision 18 of the Physical Security Plan
- DCL-03-118, License Amendment Request 03-13 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
- DCL-03-119, Response to NRC Regulatory Summary 2003-14; Preparation and Scheduling of Operator Licenising Examinations
- DCL-03-122, Changes to Technical Specifications Bases, Revision 2
- DCL-03-126, Request for Exemption from 10CFR50.68, Criticality Accident Requirements for Spent Fuel Cask Handling
- DCL-03-128, Emergency Plan Implementing Procedure Update
- DCL-03-129, September 2003 Monthly Operating Report for Diablo Canyon Units 1 & 2
- DCL-03-133, Full Compliance with Order for Compensatory Measures Related to Fitness-For-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel, Dated 04/29/03 (EA-03-038)
- DCL-03-137, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1, 'Reactor Trip System (RTS) Instrumentation
- DCL-03-139, PG&E Response to NRC Questions on 2R11 Steam Generator Tube Inspections
- DCL-03-141, Special Report 03-03: Seismic Event of October 18, 2003
- DCL-03-142, Response to NRC Request for Additional Information Regarding License Amendment Request 03-06, Revision to Technical Specification 3.8.1, 'Ac Sources - Operating
- DCL-03-145, Emergency Plan Implementing Procedure Update
- DCL-03-148, October 2003 Monthly Operating Report for Diablo Canyon, Units 1 & 2
- DCL-03-149, Response to NRC RAI Regarding License Amendment Request 03-05, Revision of Technical Specification (TS) 3.7.10, TS 3.7.12, TS 3.7.13, and TS 5.5.11
- DCL-03-150, Transmittal of Response to NRC RAI Regarding Potential Boron Dilution Events with a Loaded Multi-Purpose Canister in the DCPP Spent Fuel Pool
- 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
- DCL-03-152, Response to NRC Request for Additional Information Regarding License Amendment Request 01-08, Credit for Automatic Actuation of Pressurizer Power Operated Relief Valves; Pressurizer Safety Valve Loop Seal Temperature.
- DCL-03-162, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1, 'Reactor Trip System (RTS) Instrumentation'
- DCL-03-165, 90-Day Response to NRC Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System.
- DCL-03-166, 180-Day Response to Request for Information Pursuant to Generic Letter 2003-01, Control Room Habitability.
- DCL-03-169, Emergency Plan Implementng Procedure Update
- DCL-03-170, November 2003 Monthly Operating Report for Diablo Canyon Units 1 and 2
- DCL-03-172, Full Compliance with Order for Compensatory Measures Related to Access Authorization, EA-02-261
- DCL-03-173, License Amendment Request 03-19 for Revision to Technical Specifications 3.3.3, Post-Accident Monitoring (PAM) Instrumentation and 3.6.8, Hydrogen Recombiners
- DCL-03-177, Response to NRC RAI Regarding License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report.
- DCL-03-178, Response to NRC Request for Additional Information Regarding License Amendment Request 03-07, Revision to Technical Specifications (TS) 3.8.1 AC Sources - Operating & 3.8.4 DC Sources - Operating Surveillance Requirements.
- DCL-03-179, Response to NRC Request for Additional Information Regarding License Amendment Request 03-06, Revision to Technical Specification 3.8.1, 'Ac Sources - Operating.
- DCL-03-183, License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, Steam Generator (SG Tube Surveillance Program, and 5.6.10, SG Tube Inspection Report, for 4-Volt Alternate Repair Criteria for SG Tube Repair
- DCL-03-184, Special Report 03-04; San Simeon Earthquake of December 22, 2003
- DCL-04-001, Response to NRC RAI Regarding License Amendment Request 03-13, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process.
- DCL-04-002, Inservice Testing (IST) Program Plan, Revision 20
- DCL-04-003, December 2003 Monthly Operating Report for Diablo Canyon
- DCL-04-008, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1. 'Reactor Trip System (RTS) Instrumentation'.
- DCL-04-010, Change 25 to Revision 18 of the Physical Security Plan
- DCL-04-013, License Amendment Request 03-17, Common Stars Amendment, Implementation of WCAP-14333 and WCAP-15376, RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
- DCL-04-014, Transmittal of Semi-Annual Fitness-for-Duty Performance Report for Period of July - December 2003
- DCL-04-015, January 2004 Monthy Operating Report for Diablo Canyon, Units 1 and 2
- DCL-04-016, Inservice Inspection Relief Request for ASME Code Case N-579
- DCL-04-017, Supplement to 2003 10 CFR 50.46 Annual Report of Emergency Cooling System Evaluation Model Changes, Unit 2 Beloca Analysis
- DCL-04-018, Special Report 04-01: Results of Steam Generator Tube Eddy Current Inspections During the Eleventh Refueling Outage
- DCL-04-019, Voltage-Based Repair Criteria Benchmarking and EOC-12 Projections
- DCL-04-021, Units I and 2, Twenty-Day Response to First Revision of NRC Order Modifying Licenses (EA-03-009)
- DCL-04-022, Supplement 1 to License Amendment Request 01-08, Credit for Automatic Actuation of Pressurizer Power Operated Relief Valves
- DCL-04-027, February 2004 Monthly Operating Report for Diablo Canyon, Units 1 and 2
- DCL-04-028, License Amendment Request 04-01, Revised Steam Generator Voltage-based Repair Criteria Probability of Detection Method
- DCL-04-029, Response to NRC RAI Regarding License Amendment Request 02-06, Revisions to Technical Specifications 3.3.1, 'Reactor Trip System (RTS) Instrumentation' and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) ....
- DCL-04-031, Supplement to Special Report 03-04: San Simeon Earthquake of December 22, 2003
- DCL-04-037, Exigent License Amendment Request 04-02 Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.
- DCL-04-038, Annual Technical Specification 5.6.1 Report
- DCL-04-040, Supplement to Exigent Amendment Request 04-02 Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
- DCL-04-043, Notification of Bankruptcy Settlement
- DCL-04-044, March 2004 Monthly Operating Report for Diablo Canyon Units 1 and 2
- DCL-04-046, CFR 50.59 Report of Changes. Tests, and Experiments for the Period January 1, 2002, Through December 31, 2003
- DCL-04-049, Response to NRC Request for Additional Information Regarding License Amendment Request 03-12, Revision to Technical Specifications 3.3.1. 'Rts Instrumentation,' and 3.3.2. 'Esfas Instrumentation'
- DCL-04-050, Annual Radioactive Effluent Release Report - Data Files
- DCL-04-051, Units I and 2, 2003 Annual Radiological Environmental Operating Report
- DCL-04-052, Supplemental Information Regarding Response to NRC Bulletin 2002-02. Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
- DCL-04-053, Annual Nonradiological Environmental Operating Report
- DCL-04-054, Supplemental Response to the April 29. 2003. Orders to Pacific Gas & Electric Company
- DCL-04-055, Supporting Information for License Amendment Request (LAR) 03-07. 'Revision to Technical Specifications (TS) 3.8.1 'Ac Sources - Operating' & TS 3.8.4 'Dc Sources - Operating' Surveillance Requirements.
- DCL-04-057, Response to NRC Request for Additional Information Regarding License Amendment Request 03-16. Revised Wedge Region Exclusion Zones for Steam Generator Tube Alternate Repair Criteria.
- DCL-04-058, Use of Encryption Software for Electronic Transmission of Safeguards Information
- DCL-04-060, April 2004 Monthly Operating Report for Diablo Canyon Units 1 and 2
- DCL-04-066, Response to NRC Request for Additional Information Regarding License Amendment Request 03-12, Revision to Technical Specifications 3.3.1, 'Rts Instrumentation,' and 3.3.2, 'Esfas Instrumentation.'
- DCL-04-067, Commitment Change Summary Report, January 1, 2003, Through December 31, 2003
- DCL-04-070, Response to NRC Request for Additional Information Regarding License Amendment Request 03-15, Steam Generator Tube Repair Using Leak Limiting Alloy 800 Sleeves and Revision to Technical Specification Table 5.5.9-2, 'Steam
- DCL-04-071, Update to the Seismicity Evaluation of the December 22, 2003 San Simeon Earthquake
- DCL-04-082, Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Program, 60-Day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations
- DCL-04-085, Response to NRC Requests for Additional Information Regarding Physical Security Plan Sections 1 Through 19 Per NRC Secured Facsimile Dated June 22. 2004 and NRC Letter Dated June 28. 2004
- 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.
- DCL-04-090, Response to NRC Regulatory Issue Summary 2004-10; Preparation and Scheduling of Operator Licensing Examinations
- DCL-04-092, Response to Nrc'S Request for Additional Information Regarding the Plant Physical Security Plan. Training and Qualification Plan Per NRC Letter Dated July 9. 2004
- DCL-04-094, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes
- 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
- DCL-04-096, Emergency License Amendment Request 04-03, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems
- DCL-04-097, Response to NRC Request for Additional Information Regarding Emergency License Amendment Request 04-03, Revision to Technical Specification 3.6.6. 'Containment Spray and Cooling Systems'
- DCL-04-101, Response to Nrc'S Request for Additional Information Re Plant Safeguards Contingency Plan & Section 9.4.1 of the Physical Security Plan, Per NRC Letter Dated July 23, 2004
- DCL-04-102, Response to Nrc'S Request for Additional Information Re Plant Physical Security Plan and Safeguards Contingency Plan - Closeout of Open Items
- DCL-04-104, Response to NRC Request for Additional Information Regarding License Amendment Request 04-01, 'Revised Steam Generator Voltage-based Repair Criteria Probability of Detection Method for Plant.
- DCL-04-105, Response to July 8, 2004, NRC Request for Additional Information Re License Amendment Request 04-01, Revised Steam Generator Voltage-based Repair Criteria Probability of Detection Method.
- DCL-04-109, Response to NRC Request for Additional Information Regarding License Amendment Request 03-12. Revision to Technical Specifications 3.3.1, 'Rts Instrumentation,' and 3.3.2, 'Esfas Instrumentation.
- DCL-04-110, Response to August 30. 2004, NRC Request for Additional Information Regarding License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, 'Steam Generator (SG) Tube Surveillance Program,' and 5.6.10. 'Steam Generator (SG)
- DCL-04-111, Inservice Inspection Report for Diablo Canyon Unit 1 Twelfth Refueling Outage
- DCL-04-112, Special Report 05-02: Results of Steam Generator Tube Eddy Current Inspections During Twelfth Refueling Outage
- DCL-04-113, Update of the Diablo Canyon Power Plant Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan
- DCL-04-115, August 2004 Monthly Operating Report for Diablo Canyon Units 1 and 2 and Corrected June and July Data Sheets
- DCL-04-117, Response to August 24, 2004, NRC Request for Additional Information Reqarding License Amendment Request 04-01, Revised Steam Generator Voltage-based Repair Criteria Probability of Detection Method for DCPP Units 1 and 2.
- DCL-04-118, License Amendment Request 04-04 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil, Starting Air, and Turbocharger Air Assist.
- DCL-04-120, ISFSI - 10-Day Response to NRC Letter, Dated September 10. 2004, Implementation Status of Independent Spent Fuel Storage Installation Interim Compensatory Measures.
- DCL-04-122, Final Update of the Diablo Canyon Power Plant Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan
- DCL-04-123, License Amendment Request 04-06 Removal of Technical Specifications 5.6.1, Occupational Radiation Exposure Report, and 5.6.4, Monthly Operating Reports
- DCL-04-124, Withdrawal of License Amendment Request 03-15, Steam Generator Tube Repair Using Leak Limiting Alloy 800 Sleeves and Revision to Technical Specification Table 5.5.9-2, 'Steam Generator (SG) Tube Inspection.'
- DCL-04-126, Incorporation of NRC Security Plan Review Team Comments of the Diablo Canyon Power Plant Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan
- DCL-04-130, Response to NRC Request for Additional Information Regarding 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 Press
- DCL-04-131, Response to Request for Additional Information Regarding License Amendment Request 04-05, Revision to Technical Specification Requirements for Handling Irradiated Fuel in the Primary Containment.
- DCL-04-132, September 2004 Monthly Operating Report for Diablo Canyon Units 1 and 2
- DCL-04-134, Incorporation of NRC Security Plan Review Team Comment of October 13, 2004 Into the Plant Physical Security Plan
- DCL-04-139, Incorporation of NRC Security Plan Review Team Comment of October 15. 2004, Into the Plant Physical Security Plan