Category:Amendment
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Pages in category "Amendment"
The following 200 pages are in this category, out of 2,194 total.
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- 1CAN012002, License Amendment Request: Revise Loss of Voltage Relay Allowable Values
- 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure
- 1CAN061902, Supplemental Change Related to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues
- 1CAN070603, License Amendment Request to Support the Use of Metamic@ Polson Insert Assembles in the Spent Fuel Pool
- 1CAN080601, License Amendment Request Regarding the Relocation of Inverter Y-28 and Panel C-540 Requirements from TSs to TRM
- 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
- 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
- 1CAN120301, ANO, Unit 1 - Supplement to Amendment Request to Add a New Control Room Emergency Ventilation System Surveillance Requirement
- 1CAN121301, Clarification of Proposed Change to Technical Specification 2.1.1.1 Reactor Core Safety Limits
- 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
2
- 2CAN020601, License Amendment Request to Modify Technical Specification Surveillance Requirement 4.6.1.1.a
- 2CAN030806, Supplemental to License Amendment Request, Technical Specification 3.1.1.4, Moderator Temperature Coefficient
- 2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
- 2CAN042401, Request to Revise Typographical Errors in Arkansas Nuclear One, Unit 2 Technical Specifications
- 2CAN050304, Arkansas, Unit 2, License Amendment Request to Change Containment Spray System Surveillance
- 2CAN050702, License Amendment Requesting, Technical Specification 3.1.1.4, Moderator Temperature Coefficient
- 2CAN050901, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit
- 2CAN050902, License Amendment Request to Revise Technical Specification 6.6.5, Core Operating Limits Report
- 2CAN061003, Arkansas Nuclear One, Unit 2 - License Amendment Request, Technical Specification Change to Extend the Type a Test Frequency to 15 Years
- 2CAN070503, Arkansas, Unit 2 - License Amendment Request to Add Cask Loading Restrictions
- 2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
- 2CAN090202, Arkansas Unit 2, Application for Amendment to License NPF-6 to Amend Technical Specifications to Extend Allowable Outage Time (AOT) for Emergency Diesel Generators (Edgs) from 72 Hours to Maximum of 14 Days
- 2CAN090502, Arkansas, Unit 2 - License Amendment Request to Allow One-Time Extension of Containment Spray System Allowable Outage Time
- 2CAN090504, Arkansas, Unit 2 - License Amendment Request to Modify Technical Specification 3.1.1.5, Minimum Temperature for Criticality
- 2CAN092501, Request to Revise Typographical Errors in Technical Specifications
- 2CAN100701, License Amendment Request - Technical Specification Changes Regarding Mode Change Limitations and Associated Bases Using the Consolidated Line Item Improvement Process
- 2CAN100703, Unit 2 License Amendment Request for Technical Specification Change Associated with Replacement of Containment Sump Buffer
- 2CAN101401, Arkansas, Unit 2 - License Amendment Request Supplemental Adoption of Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186)
- 2CAN121705, Exigent License Amendment Request Allowance to Exclude Exercise of Control Element Assembly 4 with Respect to Surveillance Requirement 4.1.3.1.2 for the Remainder of Cycle 26
3
- 3F0108-14, License Amendment Request 298, Revision 0: Application to Modify Improved Technical Specifications for Replacement Steam Generators
- 3F0204-05, License Amendment Request No. 279, Revision 0, Application for Technical Specification Improvement to Eliminate Requirements for Post-Accident Sampling System for Babcock & Wilcox Reactors Using the Consolidated Line Item
- 3F0307-08, License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process
- 3F0515-01, License Amendment Request 317, Revision 0, Revision to Improved Technical Specifications Administrative Controls Section to Establish Permanently Defueled Technical Specifications
- 3F0703-04, License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
- 3F0704-03, License Amendment Request 285, Revision 0, Deletion of One-Time Use Footnotes
- 3F0904-02, License Amendment Request No. 284, Revision 0, Application for Technical Specification Improvement to Relax Requirement for Hydrogen Monitors Using the Consolidated Line Item Improvement Process
- 3F1006-02, License Amendment Request 293, Revision 0 Revised Improved Technical Specification (ITS) 3.7.7, Nuclear Services Closed Cycle Cooling Water (SW) System
- 3F1007-01, License Amendment Request No. 275, Revision 0, Application for Technical Specification Change TSTF-374, Revision to ITS 5.6.2.14 and Associated Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process
A
- A144306, Response to RAI Concerning Safety Limit Minimum Critical Power Ratio (SLMCPR) Change, License Amendment Request: AR A1443067
- AEP-NRC-2009-18, License Amendment Request for Adoption TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
- AEP-NRC-2009-45, License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System
- AEP-NRC-2010-12, Exigent License Amendment Request Regarding Containment Distributed Ignition System
- AEP-NRC-2016-78, Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and
- AEP-NRC-2018-26, Application to Revise Technical Specifications to Adopt TFTF-529, Revision 4, Clarify and Use Application Rule
- AEP-NRC-2018-66, Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology
- AEP-NRC-2019-33, Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-421
- AEP-NRC-2019-39, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition
- AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues
- AEP-NRC-2020-72, License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency
- AEP-NRC-2021-24, Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation
- AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System
- AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
B
- B18610, Application for Amendment to NPF-49 to Modify Technical Specification Requirements for Missed Surveillances in Specification 4.0.3 & Modify Associated Technical Specification Bases
- B18807, Response to a Request for Additional Information, License Basis Document Change Request 2-1-02 Limiting Safety System Settings & Instrumentation
- BSEP 02-0124, Application for Amendment to Licenses DPR-71 & DPR-62 to Revise Technical Specifications Section 3.1.7 to Reflect Modifications as Result of Transition to GE14 Fuel Design
- BSEP 02-0159, Application for Technical Specification Change Regarding Elimination of Post Accident Sampling System Requirements
- BSEP 03-0150, Request for License Amendments Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process
- BSEP 05-0094, Request for License Amendments - Appendix J Leakage Rate Testing Instrumentation Accuracy, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program
- BSEP 05-0102, Request for License Amendment Revised Main Steam Isolation Valve Leakage Limit
- BSEP 07-0080, Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation
- BSEP 08-0082, Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
- BSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report
- BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report
- BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements
- BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3
- BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time
- BSEP-07-0064, Request for License Amendments, Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program
- BVY 04-098, Technical Specification Proposed Change No. 263 - Supplement No. 14 Extended Power Uprate - Response to Request for Additional Information
- BVY 05-086, Technical Specifications Proposed Change No. 263 - Supplement No. 34 Extended Power Uprate - Additional Information
- BVY 05-088, Technical Specification Proposed Change No. 263 - Supplement No. 35 Extended Power Uprate - Response to Request for Additional Information
- BVY 05-094, Technical Specification Proposed Change No. 266, Revision to Control Rod Operability, Scram Time Testing and Control Rod Accumulators - Response to Request for Additional Information
- BVY 05-101, Proposed Technical Specification Change No. 263 - Supplement No. 41 Re Extended Power Uprate - Condensate and Feedwater Transient Response Engineering Analysis
- BVY 08-001, Technical Specifications Proposed Change No. 273 Instrumentation Technical Specifications
- BVY 08-059, Technical Specifications Proposed Change No. 280 Relocation of Reactor Building Crane Technical Specifications
- BVY 08-066, Submittal of Corrected Technical Specification Page
- BVY 09-012, Submittal of Proposed License Amendment for Technical Specifications No. 282, Revision of Drywell Vacuum Breaker Surveillance Requirements
- BVY 09-029, Technical Specifications Proposed Change No. 283 Change to Requirements for Performing 10 CFR 50, Appendix J, Type a Test
- BVY 09-051, Technical Specifications Proposed Change No. 285 Revision of High Radiation Area Controls
- BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
- BVY 10-059, Technical Specifications Proposed Change No. 294, Elimination of Provisions Allowing HPCI and RCIC Suctions to Be Aligned to the Suppression Pool
- BVY 12-018, Technical Specifications Proposed Change No. 299 Recirculation System Discharge Bypass Valve Change
- BVY 14-049, Technical Specifications Proposed Change No. 309, Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition - Supplement 3
C
- CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)
- CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)
- CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)
- CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)
- CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)
- CNL-15-133, Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)
- CNL-16-051, Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)
- CNL-16-077, For Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information
- CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision
- CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2
- CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
- CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)
- CNL-17-149, Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
- CNL-18-062, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1
- CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)
- CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)
- CNL-19-105, Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)
- CNL-19-116, Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)
- CNL-20-004, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01)
- CNL-20-008, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28)
- CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)
- CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)
- CNL-22-008, And Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)
- CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)
- CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)
- CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche
- CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)
- CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)
- CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
- CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-
- CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)
- CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)
- CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)
- CNL-25-001, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
- CNL-25-038, Application to Revise Technical Specifications to Adopt TSTF-597-A, Eliminate LCO 3.0.3 Mode 2 Requirement
- CNL-25-041, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line.
- CNL-25-068, TVA Fleet Application to Revise Technical Specifications to Adopt TSTF-596-A, Revision 2, Expand the Applicability of the Surveillance Frequency Control Program (Sfcp), and to Adopt for the Watts Bar Nuclear Plant, Only, TSTF-374-A, Revis
- CNL-25-088, Application to Revise Technical Specifications to Adopt TSTF-592-A, Revision 2, Revise Automatic Depressurization System (ADS) Instrumentation Requirements (BFN TS-558)
- CNL-26-018, Application to Revise Technical Specifications to Adopt TSTF-602-A, Revision 0, Revise the Ventilation Filter Testing Program to Permit Alternate Challenge Agents..
- CNRO-2022-00015, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling Using the Consolidated Line-Item Improvement Process
- CP-200800124, Supplement to License Amendment Request (LAR) 07-004 Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt
- CP-200900262, License Amendment Request (LAR) 09-001, Administrative Revision to Operating Licenses and Technical Specifications
- CP-200900492, License Amendment Request (LAR) 09-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
- CP-200900748, Comanche Peak - License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria
- CP-201400632, License Amendment Request (LAR) 14-001, Revision to TS 3.8.1, AC Sources - Operating, for a 14-Day Completion Time for Offsite Circuits
- CP-202000016, Editorial Correction to License Amendment Request (LAR) 19-002 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
- CP-202000388, (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water
- CP-202100394, Supplement to License Amendment Request (LAR) 20-006
- CP-202100694, (CPNPP) - NRC Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
- CP-202200075, Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
- CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
- CP-202200380, (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications
- CP-202300293, (CPNPP) - License Amendment Request Proposing Changes to Technical Specifications to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days
- CP-202400472, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules
- CP-202500207, Application to Revise Technical Specifications to Adopt TSTF-432, Change in Technical Specifications End States (WCAP-16294)
- CPSES-200203192, Request for Additional Information Re License Amendment Request (LAR) 01-012, Steam Generator Tube Repair Using Leak Tight Sleeves
- CPSES-200300266, License Amendment Request 02-06, Revision to Technical Specifications Associated with DC Electrical Power Systems
- CPSES-200400148, Submittal of Revised Contractor Report Related to License Amendment Request 03-03, Revision to Technical Specification (TS) 5.5.9 Steam Generator Tube Repair Using Leak Limiting Alloy 800 Sleeves
- CPSES-200401839, License Amendment Request 02-07 Revision to Technical Specification (TS) 3.8.1 Surveillance Requirement Mode Restriction
- CPSES-200401863, License Amendment Request LAR 04-05 Change to Technical Specification 3.7.10, Control Room Emergency Filtration/Pressurization System
- CPSES-200601634, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators
- CPSES-200602131, License Amendment Request 06-011, to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process
- CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
- CY-04-227, Supplemental Information-Changes to Selected Radiological Requirements and Organizational Titles in Technical Specifications
D
- 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-03-067, License Amendment Request 03-08 Revision to Technical Specification 3.5.1, Emergency Core Cooling Systems/Accumulator
- 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-03-173, 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-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-04-013, 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-04-037, Exigent License Amendment Request 04-02 Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
- DCL-04-089, 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-05-018, License Amendment Request 05-01 Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program, and 5.6.10, Steam Generator Tube Inspection Report. to Allow Use of the W* Alternate Repair Criteria
- DCL-06-061, License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449)
- DCL-07-093, Diablo Canyon, Units 1 & 2 - License Amendment Request 07-02, Revision to Technical Specification 3.5.4, Refueling Water Storage Tank
- DCL-08-008, License Amendment Request 08-01, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program
- DCL-09-032, License Amendment Request 09-03, License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26
- 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)
- DCL-17-076, Revision to Technical Specifications to Adopt Technical Specifications Task Force TSTF-547, Revision 1, Clarification of Rod Position Requirements (License Amendment Request 17-01)
- DCL-20-063, Pacific Gas & Electric Co - License Amendment Request 20-02, Non-Voluntary License Amendment Request to Revise Technical Specifications
- DCL-21-019, Supplement to License Amendment Request 20-03 Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
- DCL-22-011, License Amendment Request 22-02 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections
- DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
- DCL-24-070, 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
- DCL-24-111, 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 and 3.3.2
- DCL-24-119, License Amendment Request 24-08 Application to Revise Technical Specifications to Adopt TSTF-541
- DCL-25-094, License Amendment Request 25-07, Revise Technical Specifications to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, Using the Consolidated Line Item Improvement Process
- DCL-26-005, License Amendment Request 26-02 Application to Revise Technical Specifications to Adopt TSTF-585, Revise LCO 3.0.3 to Require Managing Risk
E
- ENOC-09-00009, Entergy Nuclear Operations, Inc. - License Amendment Request; Proposed Adoption of TSTF-511 Regarding Elimination of Technical Specification Work Hour Restrictions
- ET 05-0001, Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program
- ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report
- ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating
- ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
G
- GNRO-2003/00025, License Amendment Request, Proposed Changes to Primary Containment and Drywell Isolation Instrumentation Requirements, Ldc 2003-033
- GNRO-2003/00044, Supplement to Amendment Request Removal of Mode Restrictions for Surveillance Testing of the Division 3 Battery
- GNRO-2003/00053, Application for Technical Specification (TS) Improvement to Revise TS 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process
- GNRO-2004/00013, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process, LDC-2003/102
- GNRO-2006/00036, License Amendment Request, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process (TSTF-372)
- GNRO-2007/00004, License Amendment Request, Request for a Technical Specification Change to Allow Use of Control Rod Assemblies with Different Control Material
- GNRO-2007/00050, Supplemental Information for Licensing Amendment Request Pertaining to Control Room Envelope Habitability
- GNRO-2008/00013, License Amendment Request, Technical Specification Surveillance Requirements for Diesel Generator Slow Start Testing
- GNRO-2009/00062, License Amendment Request to Revise Minimum Critical Power Ratio Safety Limits
- GNRO-2014/00050, Correction of Technical Specification Typographical Error
- GNRO-2015/00002, Grand Gulf, Unit 1 - Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request
- GNRO-2015/00002, Response to Electronic Request for Additional Information Regarding Modification of Technical Specification (TS) 3.8.4, DC Sources Operating Surveillance Requirements (Srs) 3.8.4.2 and 3.8.4.5. Amendment Request Dated 12/9/2014
- GNRO-2019/00028, Supplement to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
- GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
- GO2-02-111, Amendment Request to Revise Minimum Emergency Diesel Generator Output Voltage Specified in Technical Specification Limiting Condition for Operation 3.8.1
- GO2-02-192, Request for Amendment to TS 4.2.1 and 5.6.5.b, Corrections to Original Submittal
- GO2-04-137, Request for Amendment to Technical Specifications for One-Time Extension of Containment Leak Rate Test Interval
- GO2-05-184, Supplement to the License Amendment Request for a One-Time Extension to Technical Specification 3.7.1
- GO2-06-061, Request for Amendment to Technical Specifications Surveillance Requirements for the Suppression Chamber-to-Drywell Vacuum Breakers and the Drywell-to-Suppression Chamber Bypass Leakage Test
- GO2-07-109, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level
- GO2-07-111, License Amendment Request for Proposed Changes to Columbia Technical Specifications: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves
- GO2-07-116, Request for Amendment to Technical Specification to Modify Requirements Regarding Control Room Envelope Habitability Using the Consolidated Line Item Improvement Process (CLIIP)
- GO2-07-123, License Amendment Request to Technical Specifications Associated with Condensate Storage Tank Level
- GO2-08-071, License Amendment Request for Adoption of TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities
- GO2-08-124, License Amendment Request for Proposed Changes to Columbia Technical Specification 3.3.3.1; Change Group 1 Primary Containment Isolation Valves Reactor Water Level Isolation Signal from Level 2 to Level 1