GDC 9
type: Ontology
creation date: 2025-12-10T01:33:34-05:00
imports: http://semantic-mediawiki.org/swivt/1.0

GDC 9
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wiki page sort key: GDC 9

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ML16034A372
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NRC 2016-0030, License Amendment Request for H: Alternate Repair Criteria for Steam Generator Tube Sheet Expansion Region
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CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates
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ML16075A301
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ML15110A009
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BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure
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ML17286A013
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ML15160A427
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ML15154A477
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NL-13-145, Proposed License Amendment to Adopt TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection Indian Point Unit Nuclear Generating Unit Nos. 2 and 3
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ML14087A013
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ML13039A200
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RNP-RA/13-0030, Revision to License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Section and Application of Permanent Alternate Repair Criteria
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page: https://kanterella.com/RNP-2DRA/13-2D0030-2C_Revision_to_License_Amendment_Request_for_Revision_to_Steam_Generator_Program_Inspection_Frequencies_and_Tube_Sample_Section_and_Application_of_Permanent_A…
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NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
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page: https://kanterella.com/NRC_2013-2D0005-2C_License_Amendment_Request_252-2C_Technical_Specification_5.6.5-2C_Reactor_Coolant_System_-28RCS-29_Pressure_and_Temperature_Limits_Report_-28PTLR-29
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RNP-RA/12-0057, License Amendment Request for Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection and Application of Permanent Alternate Repair Criteria (H*)
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page: https://kanterella.com/RNP-2DRA/12-2D0057-2C_License_Amendment_Request_for_Revision_to_Steam_Generator_Program_Inspection_Frequencies_and_Tube_Sample_Selection_and_Application_of_Permanent_Alternate_R…
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ML040620036
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ML18060A401
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ML18150A387
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DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
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page: https://kanterella.com/DCL-2D17-2D038-2C_Diablo_Canyon_Power_Plant-2C_Units_1_-26_2-2C_Revised_Updated_Final_Safety_Analysis_Report-2C_Rev._23-2C_Chapter_5-2C_Reactor_Coolant_System
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wiki page sort key: DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System

DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 10, Steam and Power Conversion System
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page: https://kanterella.com/DCL-2D17-2D038-2C_Diablo_Canyon_Power_Plant-2C_Units_1_-26_2-2C_Revised_Updated_Final_Safety_Analysis_Report-2C_Rev._23-2C_Chapter_10-2C_Steam_and_Power_Conversion_System
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wiki page sort key: DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 10, Steam and Power Conversion System

L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems
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page: https://kanterella.com/L-2D2016-2D198-2C_Redacted_Turkey_Point-2C_Units_3_-26_4-2C_Updated_Final_Safety_Analysis_Report-2C_Chapter_9-2C_Auxiliary_and_Emergency_Systems
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L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
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page: https://kanterella.com/L-2D2016-2D198-2C_Redacted_Turkey_Point-2C_Units_3_-26_4-2C_Updated_Final_Safety_Analysis_Report-2C_Chapter_4-2C_Reactor_Coolant_System
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DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 8
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NL-15-169, Browns Ferry, Units 1, 2, and 3, Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped)
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NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System
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page: https://kanterella.com/NL-2D14-2D121-2C_Indian_Point-2C_Unit_2-2C_Updated_Final_Safety_Analysis_Report_-28Ufsar-29-2C_Revision_25-2C_Chapter_4_-2D_Reactor_Coolant_System
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NL-14-001, Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair
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page: https://kanterella.com/NL-2D14-2D001-2C_Indian_Point-2C_Unit_2_-2D_Proposed_License_Amendment_for_Alternate_Repair_Criteria_for_Steam_Generator_Tube_Inspection_and_Repair
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BVY 10-071, Technical Specifications Proposed Change No. 293 Revised Reactor Vessel Pressure-Temperature Limitation Curves
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page: https://kanterella.com/BVY_10-2D071-2C_Technical_Specifications_Proposed_Change_No._293_Revised_Reactor_Vessel_Pressure-2DTemperature_Limitation_Curves
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ML101890217
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ML060720248
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NRC 2008-0034, License Amendment Request 257, Technical Specifications 5.5.8 and 5.6.8, Steam Generator Program & Steam Generator Tube Inspection Report, Interim Alternate Repair Criteria (Iarc) for Steam Generator Tube Repair
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ML20024E288
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NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 4 - Reactor Coolant System - Design Basis
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RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
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NRC 2006-0090, License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report
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NRC 2006-0061, LAR Public Version, License Amendment Request 248; Technical Specification 5.5.8, Steam Generator Program
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L-06-088, Supplement to License Amendment Request Nos. 324 & 196 Steam Generator Tube Integrity
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ML061370687
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RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions
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ML060720272
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ML043060235
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RNP-RA/03-0139, Submittal of 90-day Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
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03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators
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ML031640004
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