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List of results

• DCL-18-070, Diablo Canyon, Units 1 and 2, Transmittal of Technical Specification Bases, Revision 11  + (Diablo Canyon, Units 1 and 2, Transmittal of Technical Specification Bases, Revision 11)
• DCL-25-086, Diablo Canyon, Units 1 and 2, and Independent Spent Fuel Storage Installation - Proposed Revision to the Quality Assurance Program  + (Diablo Canyon, Units 1 and 2, and Independent Spent Fuel Storage Installation - Proposed Revision to the Quality Assurance Program)
• DCL-25-029, Diablo Canyon, Units 1 and 2: License Amendment Request 25-01: Application to Utilize Optimize ZIRLO for Improved Fuel Rod Cladding Performance  + (Diablo Canyon, Units 1 and 2: License Amendment Request 25-01: Application to Utilize Optimize ZIRLO for Improved Fuel Rod Cladding Performance)
• DCL-24-111, Diablo Canyon, Units 1&2, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3  + (Diablo Canyon, Units 1&2, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1)
• DCL-16-112, Diablo Canyon-2016-10 Post Examination Comments  + (Diablo Canyon-2016-10 Post Examination Comments)
• DCL-25-015, Diablo Cranyon, Units 1 and 2 - Response to Request for Additional Information for License Amendment Request 24-03, Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies  + (Diablo Cranyon, Units 1 and 2 - Response to Request for Additional Information for License Amendment Request 24-03, Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies)
• ML030760353  + (Diablo ISFSI - Memo from Dambly to Virgilio on Board Ruling on Standing and Contentions: Commission Denial of Petition for Suspension of Proceeding Based Upon Terrorism)
• DCL-2017-501, Diablo Power Plant - 2016 Annual Sea Turtle Report  + (Diablo Power Plant - 2016 Annual Sea Turtle Report)
• DCL-02-033, Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity  + (Diablo Units 1 & 2 Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity)
• DCL-14-030, Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 2013  + (Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 2013)
• ML111801096  + (Diablo, Units 1 and 2, Canyon, Palo Verde, Units 1,2, and 3, Generic Fundamentals Examination Results)
• ML16336A573  + (Diablo-2016-10 Draft Written Examination)
• ML082050608  + (Diabo Canyon Power Plant, Units Nos. 1 and 2 - Request for Additional Information Regarding Supplemental Response to Generic Letter 2004 - 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at P)
• ML20264B943  + (Diag of Station Htg Sys (Hot Water Htg Coil Details). Sheet 7)
• ML20264B945  + (Diag of Station Htg Sys (Hot Water Htg Coil Details). Sheet 8)
• ML20264B937  + (Diag of Station Htg Sys (Turbine Building Water Treatment Area). Sheet 4)
• ML20262G173  + (Diag:Control Rod Drive Hydraulic System - Reactor - Building Part 1 of 2)
• ML20262G438  + (Diag:Control Rod Drive Hydraulic System - Reactor Building Part 2 of 2)
• ML20195J394  + (Diagnosis of CONDENSATION-INDUCED Waterhammer.Case Studies)
• ML20195J401  + (Diagnosis of CONDENSATION-INDUCED Waterhammer.Methods and Background)
• ML20059H582  + (Diagnostic Actions)
• ML20151C961  + (Diagnostic Evaluation Rept 2 on 871130-880108)
• ML20148C651  + (Diagnostic Evaluation Team Managers Handbook,Dec 1994, Rev 1)
• ML20005E019  + (Diagnostic Evaluation Team Rept for Arkansas Nuclear One Units 1 & 2)
• ML20248C131  + (Diagnostic Evaluation Team Rept for Brunswick Steam Electric Plant,Units 1 & 2)

• ML17199T451  + (Diagnostic Evaluation Team Rept for Dresden Nuclear Power Station)

• ML20059N019  + (Diagnostic Evaluation Team Rept on Quad Cities Nuclear Power Station (930823-0903 & 20-30))
• ML20045B346  + (Diagnostic Evaluation Team Rept on South Tx Project Electric Generating Station. (930329-0409 & 0426-30))
• ML22124A243  + (Diagnostic Health Center of Anchorage - NRC Form 591M Part 1, Inspection Report 03020372/2022001)
• ML19024A071  + (Diagnostic Health Center of Anchorage, LLC; Void Letter; License 50-23214-01; Docket 030-20372; Control 610350)
• ML18347A724  + (Diagnostic Health Center of Anchorage, LLC, - NRC Form 591M Part 1, NRC Inspection 03020372/2018001)
• ML18305B362  + (Diagnostic Health Center of Anchorage, LLC; Amendment Request; License 50-23214-01; Docket 030-20372; Control 610350)
• ML25013A135  + (Diagnostic Health Center of Anchorage, LLC Expiration Notification Letter for License No. 50-23214-01)
• ML18215A215  + (Diagnostic Health Services - NRC Form 591M Parts 1 & 3, Inspection Report 03014235/2018001)
• ML19208C047  + (Diagnostic Instrumentation)
• ML22165A018  + (Diagnostic Laboratories, LLC 60-Day Expiry Notification for Lic. No. 41-31476-01)
• ML19221A200  + (Diagnostic Measurements Made at Facility Re Incore Thermocouples & Reactor Coolant Pressure Noise)
• ENS 56071  + (Diagnostic Misadministration)
• ENS 55870  + (Diagnostic Radiopharmaceutical Misadministration)
• ENS 55882  + (Diagnostic Radiopharmaceutical Misadministration)
• ML20098B001  + (Diagnostic Self Assessment)
• ML20071K931  + (Diagnostic Self Assessment (DSA) Implementation Plan)
• ML20098A998  + (Diagnostic Self Assessment, Supporting Documentation)
• ML20264B710  + (Diagram - Boric Acid Processing (Recycle Evaporator Package Oa). Sheet 3)
• ML20264B851  + (Diagram - Boric Acid Processing (Recycle Evaporator Package Ob). Sheet 6)
• ML20263G055  + (Diagram - Feedwater System)
• ML20263G052  + (Diagram - Main and Reheat Steam Systems. Revision Date Illegible)
• ML20024C564  + (Diagram 3 of Hypothetical Conditions at TMI-2 Assuming Early Block Valve Closure. Open Code Safety Calves Sys Losing Mass,Auxiliary Feedwater Off at 50% Level & High Pressurizer Level)
• ML20024C579  + (Diagram 4 of Hypothetical Conditions of TMI-2.Assuming Early Block Valve Closure. Core Uncovered & Damaged & Inventory Continues to Be Lost)
• ML20024C538  + (Diagram 5 of Small Break LOCA in B&W 205 FA Pwr. Sys Depressurizing,Sys Drainage Continues,Condensation Heat Transfer in Steam Generators & HPI Off Due to High Pressure & Level)
• ML20024C540  + (Diagram 6 of Small Break LOCA in B&W 205 FA Pwr. Primary Pressure Controlled by Secondary Side & Core Uncovered)