Category:Letter type:ET

E

• ET 02-0001, Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request l2R-23
• ET 02-0002, Inservice Inspection Program Alternative for Limited Examination on Closure Head to Flange Weld on the Reactor Pressure Vessel, Relief Request l2R-25
• ET 02-0003, Inservice Inspection Program Alternative for Limited Examination on Austenitic Stainless Steel Piping Welds with Single Side Access, Relief Request 12R-26
• ET 02-0004, Inservice Inspection Program Alternative for Limited Examination on Carbon Steel Piping Welds, Relief Request 12R-27
• ET 02-0007, Response to NRC Regulatory Issue Summary 2001-21, Licensing Action Estimates for Operating Reactors, Dated November 16, 2001
• ET 02-0013, Supplemental Information for Revision to Technical Specification 3.9.4, Containment Penetrations.
• ET 02-0015, Changes to Technical Specification Bases - Revisions 6 Through 8
• ET 02-0016, Annual Report of ECCS Model Changes
• ET 02-0018, Response to NRC Bulletin 2002-01 Re Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
• ET 02-0019, Steam Generator Tube Plugging Report for Wolf Creek Generating Station
• ET 02-0020, Rev. 0, Cycle 13 Core Operating Limits Report
• ET 02-0021, Day Resonse for NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
• ET 02-0023, 30-Day Response for NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.
• ET 02-0029, Revision to Technical Specification Surveillance Requirements 3.3.1.2 and 3.3.1.3 Re Reactor Trip System Instrumentation
• ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves.
• ET 02-0033, Revision to Technical Specification 3.1.6, Physics Tests Exceptions - Mode 2.
• ET 02-0037, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
• ET 02-0046, Results of Eleventh Steam Generator Tube Inservice Inspection
• ET 02-0048, Supplemental Information for Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request L2R-23
• ET 02-0049, Containment Inservice Inspection Program First Interval, First Period Owner'S Activity Reports
• ET 03-0003, Response to Follow-up Questions Concerning the Results of the Eleventh Steam Generator Tube Inservice Inspection
• ET 03-0006, Implementation of the ASME Code for Operation and Maintenance of Nuclear Power Plants, Regarding the Check Valve Monitoring Program
• ET 05-0001, Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program
• ET 05-0002, Letter Dated April 19, 2005, Supplement to Exigent Request for Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Tube Surveillance Program.
• ET 05-0004, Steam Generator Tube Plugging Report
• ET 05-0005, Cycle 15 Core Operating Limits Report
• ET 05-0007, Request for Approval of Changes to the Reactor Coolant System Leakage Detection Instrumentation Methodology
• ET 05-0008, Operating Corporation 10 CFR 50.55a Requests for the Third Ten-Year Interval Inservice Testing (IST) Program
• ET 05-0013, Response to Request for Additional Information Regarding the Steam Generator Tube Inspection Summary Reports for the Fall 2003 Outage
• ET 05-0014, Request Number I3R-03 for the Third Ten-Year Interval Inservice Inspection Program - Request for Relief to Allow Use of Alternate Requirements for Snubber Inspection and Testing
• ET 05-0015, 60-Day Report for 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
• ET 05-0016, Response to Request for Additional Information Regarding Extensions of AC Electrical Power Distribution Completion Time
• ET 05-0018, Operating Corporation, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
• ET 05-0019, Supplemental Response to NRC Request for Additional Information Related to Bulletin 2003-01
• ET 05-0022, Response to Request for Additional Information, Reactor Coolant System Leakage Detection Instrumentation
• ET 05-0023, Inservice Inspection Program Second Interval, Third Period Owner'S Activity Reports
• ET 05-0025, Supplement to Revision to Technical Specifications - Extensions of AC Electrical Power Distribution Completion Times
• ET 05-0027, CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds
• ET 05-0028, Withdrawal of 10 CFR 50.55a Request I1R-51 for First Ten-Year Interval Inservice Inspection (ISI) Program
• ET 06-0001, Revision to Technical Specification 5.5.8, Inservice Testing Program to Adopt Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-479, Revision 0
• ET 06-0002, Revision to Technical Specification (TS) 3.3.1, Reactor Trip System (RTS) Instrumentation
• ET 06-0004, Revision to Technical Specification 5.5.9, Steam Generator Tube Surveillance Program
• ET 06-0009, Response to Generic Letter 2006-01
• ET 06-0010, Inservice Inspection Program Plan for the Third Ten-Year Interval and 10 CFR 50.55a Requests I3R-01, I3R-02, and I3R-04
• ET 06-0011, CFR 50.55a Requests I2R-34, I2R-35, I2R-36, I2R-37, and I2R-38 for the Second Inservice Inspection Program Interval
• ET 06-0012, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidate Line Item Improvement Process
• ET 06-0013, Withdrawal and Resubmittal of 10 CFR 50.55a Request 3PR-04 for the Third Ten-Year Interval Inservice Testing (IST) Program
• ET 06-0014, Notice of Intent to Upgrade to Digital Main Steam and Feedwater Isolation Valve Controls
• ET 06-0015, Supplement to Revision to Technical Specifications - Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
• ET 06-0016, Results of the Thirteenth Steam Generator Tube Inservice Inspection
• ET 06-0017, Response to RAI Regarding 10 CFR 50.55a Request Number I3R-03 - Request for Relief to Allow Use of Alternate Requirements for Snubber Inspection and Testing
• ET 06-0018, Additional Information Concerning Revision to Technical Specifications - Extensions of AC Electrical Power Distribution Completion Times
• ET 06-0021, Operating Corporation'S Response to Request for Additional Information Regarding 10 CFR 50.55a Request 13R-05 and Submittal of Revision 1 to 10 CFR 50.55a Request 13R-05
• ET 06-0022, Response to NRC Generic Letter 2006-03
• ET 06-0024, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation.
• ET 06-0026, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program.
• ET 06-0027, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-36
• ET 06-0029, CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5222
• ET 06-0030, Additional Information Related to Revision to Technical Specification (TS) 3.3.1 Reactor Trip System (RTS) Instrumentation
• ET 06-0032, Pre-Application Review - Main Steam and Feedwater Isolation System Controls Replacement
• ET 06-0034, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-37 and I2R-38
• ET 06-0035, Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove
• ET 06-0040, Supplemental Information Related to License Amendment Request to Extend Containment Isolation Valve Completion Times
• ET 06-0042, Response to the September 20, 2006 NRC Request for Additional Information Regarding 10 CFR 50.55a Request I3R-05
• ET 06-0043, Operating Corporation'S Response to NRC Request for Additional Information Regarding 10 CFR 50.55a Request I3R-01
• ET 06-0044, Operating Corporation'S Revised Commitment Regarding 10 CFR 50.55a Request I3R-05
• ET 06-0047, Response to Request for Additional Information Concerning the Results of the Thirteenth Steam Generator Tube Inservice Inspection
• ET 06-0048, Additional Information Related to the Relaxation Request from the First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below the J-Groove
• ET 06-0049, Response to Request for Additional Information Relating to Pre-Weld Overlay Examination of Pressurizer Nozzle to Safe-End Dissimilar Metal Welds
• ET 06-0051, Generation Station Cycle 16 Core Operating Limits Report
• ET 06-0053, Application for Technical Specification to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process
• ET 06-0055, Results of Ultrasonic Examinations of the Full Structural Weld Overlays on Pressurizer Nozzle Welds
• ET 06-0058, Response to Second NRC Request for Additional Information Regarding 10 CFR 50.55a Request I3R-01
• ET 07-0002, Inspection and Mitigation of Alloy 600/82/182 Pressurizer Butt Welds
• ET 07-0003, Response to NRC Request for Additional Information Regarding NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power
• ET 07-0004, Technical Specifications, Revisions, Changes to TS 3.3.2 for Msfis I&C Digital Upgrade and Changes to TSs 3.7.2 and 3.7.3 for MSIV and Mfiv Replacement
• ET 07-0005, Results of the Fourteenth Steam Generator Tube Inservice Inspection
• ET 07-0007, 90 Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
• ET 07-0008, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification
• ET 07-0012, Response to NRC Request for Additional Information on 10 CFR 50.55a Request to Use Alternative Ultrasonic Examination Method in Lieu of Radiography
• ET 07-0013, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation System Controls
• ET 07-0021, CFR 50.46 Annual Report of ECCS Model Changes
• ET 07-0022, Supplemental Information on Main Steam and Feedwater Isolation System Controls Modification
• ET 07-0025, Revision to Commitment Due Date
• ET 07-0036, Corrected Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives
• ET 07-0039, Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification
• ET 07-0040, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls
• ET 07-0041, Additional Response to NRC Letter Dated August 8, 2007, Regarding the Main Steam and Feedwater Isolation System Controls Modification
• ET 07-0043, Response to Request for Additional Information Related to License Amendment Request to Revise the Steam Generator Program
• ET 07-0045, Operating Corporation - Response to Request for Additional Information Concerning Generic Letter 2003-01, Control Room Habitability
• ET 07-0047, Withdrawal of 10 CFR 50.55a Request to Use Alternative Ultrasonic Examination Method in Lieu of Radiography
• ET 07-0050, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls
• ET 07-0053, Response to NRC Request for Additional Information on Response to Generic Letter 2007-01
• ET 07-0056, Request for Extension of Completion Date for Corrective Actions Associated with NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
• ET 08-0003, Operating Corporation Response to Request for Additional Information Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
• ET 08-0004, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 08-0005, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls
• ET 08-0006, Response to NRC Review of License Amendment Request to Revise the Steam Generator Program
• ET 08-0008, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 08-0009, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program for Interim Alternate Repair Criteria
• ET 08-0010, Withdrawal of License Amendment Request for a Permanent Alternate Repair Criteria in Technical Specification (TS) 5.5.9, Steam Generator (SG) Program.
• ET 08-0011, Revisions to Proposed Changes to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfivs)
• ET 08-0013, Response to Request for Additional Information Concerning the Results of the Fourteenth Steam Generator Tube Inservice Inspection
• ET 08-0014, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 08-0017, Additional-Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 08-0024, Operating Corporation - Supplemental Information Related to License Amendment Request for an Interim Alternate Repair Criterion to Technical Specification 5.5.9, Steam Generator (SG) Program
• ET 08-0026, Withdrawal and Resubmission of Submittal Containing Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 08-0031, Cycle 17 Core Operating Limits Report
• ET 08-0032, Submittal of Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 08-0035, Main Steam and Feedwater Isolation System (Msfis) Controls Modification - Electromagnetic Compatibility Tests
• ET 08-0037, Request for Extension of Completion Date for Corrective Actions Associated with NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
• ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr).
• ET 08-0039, Revision to TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, TS 3.7.2, Main Steam Isolation Valves (Msivs), and Addition of New TS 3.7.19, Secondary System Isolation Valves.
• ET 08-0041, Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.
• ET 08-0043, Submittal of Supplemental Information on Proposed Changes to Technical Specifications
• ET 08-0044, 10 CFR 50.55a Request 13R-06, Alternative to the Examination Requirements of ASME Section Xl for Class 1 Piping Welds Examined from the Inside of the Reactor Vessel
• ET 08-0045, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
• ET 08-0046, Completion of Corrective Actions Associated with Wolf Creek - NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
• ET 08-0047, Results of the Fifteenth Steam Generator Tube Inservice Inspection
• ET 08-0048, Response to Request for Additional Information Related to Revision to Technical Specifications Regarding Control Room Envelope Habitability in Accordance with Technical Specification Task Force (TSTF) 448, Revision 3
• ET 08-0049, Response to Request for Additional Information Related to Submerged Safety-Related Medium Voltage Power Cables
• ET 08-0053, Corporation Response to Request for Additional Information Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
• ET 09-0001, Cycle 17 Core Operating Limits Report, Revision 1
• ET 09-0005, Submittal of Requested Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 09-0007, Submittal of License Amendment Request for Deviation from Fire Protection Program Requirements
• ET 09-0008, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 09-0010, Pressure and Temperature Limits Report, Revision 1
• ET 09-0011, Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
• ET 09-0014, Response to Request for Additional Information Regarding 10 CFR 50.55a Request I3R-06
• ET 09-0016, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion
• ET 09-0018, Redacted Version of the Wolf Creek, License Amendment Request for Use of Fire-Resistive Electrical Cable
• ET 09-0019, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
• ET 09-0020, Response to Request for Additional Information Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
• ET 09-0023, Response to Request for Additional Information Related to License Amendment Request for a Permanent Alternate Repair Criterion to Technical Specification 5.5.9, Steam Generator Program
• ET 09-0024, Response to Request for Clarifications in Response to Application for Withholding Proprietary Information from Public Disclosure
• 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 09-0026, Notification of Deviation from EPRI Pressurized Water Reactor Secondary Water Chemistry Guidelines
• ET 09-0027, Request for Extension of Response for Additional Information Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
• ET 09-0030, Application to Revise Technical Specification 3.8.4, DC Sources - Operating, Surveillance Requirements (SR) 3.8.4.2 and SR 3.8.4.5
• ET 09-0031, Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-02
• ET 09-0033, Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements
• ET 10-0002, Resubmittal of Request for Exemption from Specific 10 CFR Par 73 Requirements
• ET 10-0003, Application to Revise Technical Specification 3.6.3, Containment Isolation Valves.
• ET 10-0005, Response to Request for Additional Information Related to License Amendment Request for Deviation from Fire Protection Program Requirements
• ET 10-0006, Supplement to Request for Extension of Response Date to NRC Request for Additional Information Regarding Responses to Generic Letter (GL) 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis...
• ET 10-0008, Ltr. Implementation of Beacon Power Distribution Monitoring System
• ET 10-0010, License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps
• ET 10-0011, Supplemental Information for Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Auxiliary Feedwater - Trip of All Main Feedwater Pumps
• ET 10-0012, Results of the Sixteenth Steam Generator Tube Inservice Inspection
• ET 10-0013, License Amendment Request to the Approved Fire Protection Program to Remove High/Low Pressure Interface Designation from the Pressurizer Power Operated Relief Valves and Their Associated Block Valves
• ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1
• ET 10-0015, Revision to Commitment Made in Licensee Event Report 2009-002-00
• ET 10-0017, Resubmittal of Enclosure Submitted with License Amendment Request for Deviation from Fire Protection Program Requirements
• ET 10-0019, CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1.
• ET 10-0021, Response to Request for Additional Information Regarding the Sixteenth Steam Generator Tube Inservice Inspection
• ET 10-0025, Application to Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology
• ET 10-0026, License Amendment Request for Deviation from Fire Protection Requirements - Reactor Coolant System Subcooling During Alternative Shutdown
• ET 10-0028, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
• ET 10-0029, Changes to License Condition 2.C(5) Re Fire Protection Criteria as Described in Updated Safety Analysis Report
• ET 10-0031, Response to Supplemental Information Request for License Amendment Request Deviation from Fire Protection Requirements - Reactor Coolant System Subcooling During Alternative Shutdown
• ET 10-0038, Response to Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation.
• ET 11-0001, Additional Information Related to Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
• ET 11-0002, Changes to License Condition 2.C(5)
• ET 11-0003, Correction to 10 CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1.
• ET 11-0008, (WCGS) - Results of the Seventeenth Steam Generator Tube Inservice Inspection
• ET 11-0010, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report for Large Break Loss-of-Coolant Accident Analysis Methodology
• ET 12-0001, Supplemental Information Related to Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report, for Large Break Loss-of-Coolant Accident Analysi
• ET 12-0002, License Amendment Request, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criteria
• ET 12-0006, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process
• ET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds
• ET 12-0012, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
• ET 12-0013, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
• ET 12-0015, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
• ET 12-0018, License Amendment Request to Increase Voltage Limit for Diesel Generator Load Rejection Surveillance Requirement
• ET 12-0020, Withdrawal of License Amendment Request to Revise Technical Specification 5.6.5, Core Operating Limits Report (Colr), for Large Break Loss-of-Coolant Accident Analysis Methodology
• ET 12-0022, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements - Volume Control Tank Outlet Valves
• ET 12-0023, 10 CFR 50.46 Thirty Day Report of ECCS Model Changes
• ET 12-0024, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds
• ET 12-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems.
• ET 12-0028, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
• ET 12-0029, Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No. EA-12-049)
• ET 12-0031, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.3 (Flooding) of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
• ET 12-0033, License Amendment Request (LAR) for Deviation from Fire Protection Requirements
• ET 13-0001, Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Flooding, of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
• ET 13-0004, Withdrawal of License Amendment Request for Deviation from Fire Protection Requirements
• ET 13-0009, Clarification of RAI Regarding License Amendment Request to Revise Technical Specification (TS) 3.8.1, AC Sources-Operating
• ET 13-0011, Response to RAI Regarding License Amendment Request for Deviation from Fire Protection Program Requirements for Volume Control Tank Outlet Valves
• ET 13-0012, Request for Review of Information to Support Resolution of Example 2 of Non-cited Violation 05000482/2011007-03, Failure to Ensure Post-Fire Safe Shutdown Components Remain Free of Fire Damage
• ET 13-0017, Operating Corporation Proposed Path to Closure of Generic Safety Issue - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance.
• ET 13-0021, Supplement to 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 (Seismic) of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
• ET 13-0023, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
• ET 13-0024, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification (TS) 3.8.1, AC Sources - Operating Surveillance Requirement 3.8.1.10
• ET 13-0025, Corporation'S Response to Request for Additional Information Regarding Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Level Instrumentation (Order EA-12-05
• ET 13-0026, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
• ET 13-0027, Operating Corporation'S First Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
• ET 13-0028, Application to Revise Technical Specifications to Replace a Methodology to TS 5.6.5, Core Operating Limits Report.
• ET 13-0029, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident - 1.5 Year Response for CEUS Sites
• ET 13-0030, Results of the Eighteenth Steam Generator Tube Inservice Inspection
• ET 13-0035, Fire Protection Program Re Alternative Shutdown Capability
• ET 13-0036, Submittal of Information Related to the Request for Notice of Enforcement Discretion for Technical Specification Limiting Condition for Operation 3.0.3, TS 3.8.4, DC Sources - Operating, TS 3.8.7, Lnverters - Operating, and TS 3.8.9,.