Category:Miscellaneous
Jump to navigation
Jump to search
(previous page) (next page)
Pages in category "Miscellaneous"
The following 200 pages are in this category, out of 5,161 total.
(previous page) (next page)0
- 0CAN010503, Special Report
- 0CAN020305, Fitness-for-Duty Performance Data for Period July - December 2002
- 0CAN020403, Transmittal of Fitness-for-Duty Performance Data for Period Ending December 31, 2003
- 0CAN020505, ANO, Units 1 and 2 - Transmittal of Fitness-for-Duty Performance Data for Period July - December 2004
- 0CAN020602, Fitness-for-Duty Performance Data for the Period July - December 2005
- 0CAN021204, Units 1 and 2, Third Five-Year Surveillance of the First Ventilated Storage Cask
- 0CAN021403, Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report
- 0CAN021501, Spent Fuel Storage Radioactive Effluent Release Report for 2014
- 0CAN030701, Drug Testing Laboratory Performance Report
- 0CAN031001, Units 1 & 2, Unsatisfactory Laboratory Testing Report
- 0CAN031404, ANO, Units 1 & 2 - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Nttf)Review of Insights from the Fukushima
- 0CAN040505, Units 1 and 2, Drug Testing Laboratory Performance Report
- 0CAN050903, Annual 10 CFR 50.46 Report for Calendar Year 2008 Emergency Core Cooling System Evaluation Changes
- 0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes
- 0CAN080401, Fitness-for-Duty Performance Data for the Period January - June 2004
- 0CAN080601, Arkansas - Fitness-for-Duty Program Performance Data for the Period January - June 2006
- 0CAN100901, Units 1 & 2, Unsatisfactory Laboratory Testing Report
- 0CAN101003, 10 CFR 50.59 Summary Report and Commitment Change Summary Report
- 0CAN121602, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3
- 0CAN121901, Summary of Lost Specimens Investigation Report
1
- 1CAN010301, Arkansas, Unit 1, Once Through Steam Generator Inservice Inspection Report
- 1CAN031305, Cycle 24 COLR, Revision 6
- 1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values
- 1CAN041105, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05 Relief Request ANO1-R&R-016
- 1CAN091001, 10 CFR 50.46 Report - Significant Change in Peak Cladding Temperature
- 1CAN091601, Submittal of Initial Examination Completion of Post-Examination Analysis
- 1CAN100203, Supplemental Response to NRC Bulletin 2002-02 for Arkansas Nuclear One, Unit 1
2
- 2CAN011003, Submittal of Us Dept. of Commerce, Bureau of Industry and Security. Additional Protocol Report
- 2CAN011202, Additional Protocol Report
- 2CAN011703, Submittal of Additional Protocol Report
- 2CAN040806, 60-Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R19
- 2CAN060504, Unit 2, Submittal of Report to Provide Information Re Replacement Valve Disc Manufactured by Crane-Aloyco
- 2CAN070804, Cycle 20 Startup Report
- 2CAN091103, CFR 50.59 Summary Report
- 2CAN091302, Updated Seismic Walkdown Report
- 2CAN100802, CFR 50.59 Summary Report for Period Ending October 6, 2008
- 2CAN110502, CFR 50.59 Summary Report
3
- 3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR
- 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re
- 3F0508-14, NRC Commitment Change Report - May 2008
- 3F0511-02, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models
- 3F0512-01, NRC Commitment Change Report - May 2012
- 3F0602-05, Response to Request for Additional Information #263, Revision 0, Relocation of Reactor Coolant System Parameters to Core Operating Limits Report & 20 Percent Steam Generator Tube Plugging
- 3F0616-02, Nrg Commitment Change Report - June 2016
- 3F0702-11, Reporting Required by Environmental Protection Plan
- 3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3
- 3F0910-01, CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis
- 3F1102-08, Sea Turtle Mortality Report Submitted to the U. S. National Marine Fisheries Service
- 3F1205-03, Special Report 05-01: Once-Through Steam Generator (OTSG) Notifications Required Prior to Mode 4
- 3F1205-04, 10 CFR 50.46 Loss-Of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report
- 3F1207-03, Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station.
- 3F1209-11, 10 CFR 50.46 Loss-of-Coolant Accident Evaluation Model Change and Peak Cladding Temperature Change Report
- 3F1211-14, Summary of Changes to Evaluation Models and Peak Cladding Temperature for Large Break Loss of Coolant Analysis and Small Break Loss of Coolant Analysis
A
- AEP-NRC-2009-25, Small Break Loss-of-Coolant Accident Evaluation Model Reanalysis
- AEP-NRC-2012-38, Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation
- AEP-NRC-2012-83, Communications Assessment Requested by Nuclear Regulatory Commission Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulation 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3.
- AEP-NRC-2012-86, Flooding Walkdown Report in Response to the 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding for the D.C. Cook Nuclear Power Plant
- AEP-NRC-2012-87, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Appendix C, Page C-437 Through C-486
- AEP-NRC-2014-15, 30 Day Report of Changes to or Errors in an Evaluation Model
- AEP-NRC-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
- AEP-NRC-2018-21, 30-Day Report of Changes to or Errors in an Evaluation Model
- AEP-NRC-2018-36, Notification of Initial Renewable Operating Permit
- AEP-NRC-2020-28, CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations
- AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report
- AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in
B
- BSEP 05-0018, Occupational Radiation Exposure Report for 2004
- BSEP 05-0110, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
- BSEP 05-0137, Core Operating Limits Report, Revision 2, Cycle 15
- BSEP 06-0075, Groundwater Questionnaire
- BSEP 06-0095, Report of 10 CFR 50.59 Evaluation and Commitment Changes
- BSEP 08-0121, Submittal of Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors
- BSEP 09-0022, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation
- BSEP 10-0097, Report of 10 CFR 50.59 Evaluations and Commitment Changes
- BSEP 11-0038, Renewed Facility Operating License and Cycle 20 Core Operating Limits Report
- BSEP 12-0127, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
- BSEP 12-0128, Special Report - Technical Requirements Manual Section 3.4, Accident Monitoring Instrumentation
- BSEP 13-0030, Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
- BSEP 14-0007, 1707-01-F03, Rev. 3, Operability Assessment (CR#2013-8241)
- BSEP 14-0093, Report of 10 CFR 50.59 Evaluations and Commitment Changes
- BSEP 14-0101, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors
- BSEP 14-0131, Expedited Seismic Evaluation Process Report in Response to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident
- BSEP 15-0004, Enclosure 3 - Areva Operability Assessment. (CR #2014-7395)
- BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D
- BVY 03-069, Fitness-for-Duty Program Performance Report for Period January - June 2003
- BVY 05-018, Fitness-for-Duty Program Performance Report for the Period July - December 2004
- BVY 05-066, Comments Regarding License Amendment No. 223
- BVY 05-078, Fitness-for-Duty Program Performance Report for the Period January - June 2005
- BVY 05-089, Entergy Nuclear Northeast - Proof of Financial Protection
- BVY 06-016, Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 2005
- BVY 06-019, Vermont Yankee, Extended Power Uprate - Regulatory Commitment Information Regarding Steam Dryer Monitoring and Fiv Effects
- BVY 06-025, Regulatory Commitment Change Schedule for Installation of Capacitor Banks
- BVY 06-031, Revision 1 to Steam Dryer Monitoring Plan
- BVY 06-033, Cycle 24 10 CFR 50.59 Report
- BVY 06-068, Cycle 25 Startup Test Report Following Power Ascension and Testing
- BVY 07-004, Emergency Response Data System (ERDS) Data Point Library Update
- BVY 07-079, Update of Aging Management Program Audit Q&A Database
- BVY 12-081, Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
- BVY 13-090, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask
- BVY 14-011, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima ...
- BVY 14-011, Vermont Yankee, Revision to Flooding Walkdown Report - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from
- BVY 14-085, Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)
- BVY 15-018, Transmittal of Biennial 10 CFR 50.59 Report
- BVY 15-049, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask
- BVY 19-020, 72.48 Summary Report for the Reporting Period March 2, 2017 Through March 2, 2019
- BW230054, Attachment 2: MDMP Deviation Form
- BYRON 2002-0033, Regulatory Commitment Change Summary Report
- BYRON 2002-0129, Generator Inservice Inspection Summary Report
- BYRON 2003-0025, Regulatory Commitment Change Summary Report
- BYRON 2004-0119, Report of Changes, Tests and Experiments
- BYRON 2004-0120, Issuance of Reactor Coolant System Pressure and Temperature Limits Reports
- BYRON 2005-0035, Regulatory Commitment Change Summary Report for 2004
- BYRON 2006-0016, 2005 Regulatory Commitment Change Summary Report
- BYRON 2006-0053, Annual Radiological Environmental Operating Report, Rev 4 to CY-BY-170-301, ODCM Table of Contents Through Technical Requirements Manual, Rev 1
- BYRON 2008-0096, Submittal of Supporting Documentation for September 16, 2008 Regulatory Conference, Root Cause Investigation Report Content and Format, Page 45 of 73 Through End
- BYRON 2008-0119, Day Response to First Revised NRC Order EA-03-009, Issuance of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.
- BYRON 2009-0041, 2008 Regulatory Commitment Change Summary Report
- BYRON 2011-0018, Regulatory Commitment Change Summary Report
C
- CCN:22-15, (Pbaps), Units 1, 2, and 3 - Annual Commitment Revision Report for the Period 01/01/21 Through 12/31/21
- CNL-13-117, 10 CFR 50.46 - Combined Annual and 30-Day Report
- CNL-14-010, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, 3.0.3-1 (Requests 3b, -3a, 4b, 6b); B.1.34-8; B.1.34-9; A.1-2; Tables 3.3.1, 3.3.2-11, and
- CNL-14-013, Highlights of Improvements to the Sequoyah Nuclear Plant IPEEE Seismic Analysis Results and Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding...
- CNL-14-033, Second Six-Month Status Report and Revised Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses Re Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
- CNL-14-129, Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Browns Ferry Nuclear Plant
- CNL-14-130, Third Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) for Sequoyah Nuclear Plant
- CNL-14-210, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.
- CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
- CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc
- CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information
- CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 3
- CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results
- CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory
- CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program
- CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information
- CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information
- CNL-18-060, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions
- CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)
- CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval
- CNRO-2002-00042, Arkansas Unit 1 Control Rod Drive Mechanism Fracture Mechanics Analysis
- CNRO-2005-00023, Response to Request for Additional Information Supporting Request for Alternative W3-R&R-003 Proposed Alternative to ASME Requirements for Weld Repairs
- CNRO-2006-00023, Request for Alternative CEP-PT-001 Visual Examination of Vent and Drain Connections During System Leakage Tests
- CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee
- CNRO-2006-00043, Request for Alternative GG-ISI-002, Request to Use ASME Code Case N-716
- CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L
- CNS-14-045, Commitment Change Evaluation Report for 2013
- CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations
- CNS-15-031, Commitment Change Evaluation Report for 2014
- CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations
- CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants
- CNS-17-022, Summary of 10CFR 50.54(q) Evaluation
- CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.
- CP-200800213, Response to Request for Additional Information
- CP-200800609, Pressurizer Weld Overlay 60 Day Report and Results of the Final Pdi/Ut Examination of Weld Overlays
- CP-200800612, Commanche Peak, Units 1 & 2 - Transmittal of Revised Pressure and Temperature Limits Report
- CP-200800805, Report of Unusual or Important Environmental Event, Operating License, Appendix B, Environmental Protection Plan (Non Radiological) - Mortality of Avian Species
- CP-200900010, Core Flux Maps Data, Cycle 11
- CP-200900127, Guarantees of Payment of Deferred Premiums
- CP-200900474, Property Damage Insurance, Summary Report
- CP-200901404, Core Operating Limits
- CP-201101169, CFR50.59 Evaluation Summary Report 016, 10CFR72.48 Evaluation Summary Report 001, and Commitment Material Change Evaluation Report 010
- CP-201101257, Submittal of Operator Licensing Examination Data
- CP-201301238, Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report
- CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
- CP-201401027, 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 012
- CP-201401268, Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report
- CP-201600093, Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 013
- CP-201700033, Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path
- CP-202000462, Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 016
- CP-202200247, (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 017
- CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements
- CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018
- CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation
- CPSES-200200258, Transmittal of Second-Half 2001 Fitness-For-Duty Program Performance Data for Comanche Peak Steam Electric Station, Units 1 and 2
- CPSES-200202892, 10CFR50.59 Evaluation Summary Report 0010 and Commitment Material Change Evaluation Report 0005
- CPSES-200400172, Submittal of Post Irradiation Examination (Pie) Results of Fuel Cladding Following Cycle 7 Operation with Elevated Ph
- CPSES-200401956, Transmittal of First-half 2004 Fitness-for-duty Program Performance Data
- CPSES-200500378, Transmittal of Second-Half 2004 Fitness-for-Duty Program Performance Data
- CPSES-200500969, Technical Specification 15-Day Report for Steam Generator Tube Plugging
- CPSES-200501777, Request for Use of Higher Assigned Protection Factors Pursuant to 10 CFR 20.1705 with Use of French Designed Air Supplied Respirator Equipment
- CPSES-200501798, Transmittal of First-Half 2005 Fitness-For-Duty Program Performance Data
- CPSES-200502282, Technical Specification Reports for Steam Generator Meeting C-3 Category and 15-day Tube Plugging and Repair
- CPSES-200600154, Transmittal of Unit 2 Inservice Inspection Program Plan, Revision 2
- CPSES-200600301, Guarantees of Payment Deferred Premiums
- CPSES-200600312, Eleventh Refueling Outage (1RF11) Steam Generator Twelve Month Report
- CPSES-200601738, Transmittal of First-Half 2006 Fitness-For-Duty Program Performance Data
- CPSES-200700454, Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data
- CPSES-201001000, Operator Licensing Examination Data, Form 536
- CY-12-009, Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance
- CY-14-004, Independent Spent Fuel Storage Installation Nuclear Liability Insurance Coverage
- CY-14-021, Post Shutdown Decommissioning Activities Report (Psdar), Revision 4
- CY-16-002, ISFSI - Revision 5 of the Post-Shutdown Decommissioning Activities Report
D
- 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-02-049, 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2000, Through December 31, 2001
- DCL-02-065, Special Report 02-01: Results of Steam Generator Tube Eddy Current Inspections During Tenth Refueling Outage
- DCL-02-098, Special Report 02-02 - Results of Steam Generator Inspections for Eleventh Refueling Outage
- DCL-05-086, Submittal of 10 CFR 50.46 Annual Report for 2004 of Emergency Core Cooling System Evaluation Model Changes
- DCL-05-093, Pressure and Temperature Limits Report. Revision 6
- DCL-05-147, Special Report 05-02; Results of Steam Generator Tube Eddy Current Inspections During Unit 2 Twelfth Refueling Outage
- DCL-05-154, Requests NRC Authorization for 10 CFR 50.55a Request No. NDE-SGW for Diablo Canyon Unit 2 for Duration of Unit 2 Second Inspection Interval
- DCL-06-050, 10 CFR 50.59 Report of Changes, Tests, and Experiments for Period January 1, 2004, Through December 31, 2005
- DCL-06-100, Special Report 06-02 - Results of Steam Generator (SG) Tube Inspections for Diablo Canyon Power Plant Unit 2 Thirteenth Refueling Outage