Category:Letter type:ET
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Pages in category "Letter type:ET"
The following 200 pages are in this category, out of 353 total.
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- 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 02-0012, Annual 10 CFR 50.59 Evaluation Report
- 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 Owners 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 Owners 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 Corporations 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 06-0038, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application and Supplement to the Wolf Creek Generating Station License Renewal Application
- 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 Corporations Response to NRC Request for Additional Information Regarding 10 CFR 50.55a Request I3R-01
- ET 06-0044, Operating Corporations 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 07-0001, Operating Corporation - Response to Request for Additional Information Regarding the Review of the License Renewal Application
- 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 07-0011, Response to NRC Requests for Additional Information Related to License Renewal Application
- 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 07-0014, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
- ET 07-0016, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
- ET 07-0017, Response 64, to Master List for Audit Needs of NRC Request for Additional Information Re License Renewal Application
- ET 07-0018, Responses A24 - A30, A33 and A36 - A37 to Additional Information Needs Identified During Audit of NRC Request for Additional Information Related to License Renewal Application
- ET 07-0020, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
- 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 07-0023, Response to NRC Request for Follow-up Information Regarding Severe Accident Mitigation Alternatives, Related to License Renewal Application
- ET 07-0025, Revision to Commitment Due Date
- ET 07-0026, Response to NRC Requests for Follow-up Information Regarding Severe Accident Mitigation Alternatives for Wolf Creek Generating Station License Renewal Application
- ET 07-0028, Followup Response to NRC Requests for Additional Information Related to License Renewal Application
- ET 07-0029, Summary of Impact to Wolf Creek License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Error
- ET 07-0030, Revision to the Response Due Date for a Request for Additional Information for License Renewal Application Metal Fatigue Analysis
- ET 07-0031, Operating Corporation - Revision to the Aging Management Program, and Time-Limited Aging Analysis Questions and Responses Related to License Renewal Application
- ET 07-0032, Response to NRC Requests for Additional Information Related to License Renewal Application Time-Limited Aging Analysis Audit Question
- ET 07-0033, Followup Response to NRC Requests for Additional Information Related to License Renewal Application
- ET 07-0035, Summary of the Impact to Wolf Creek Generating Station License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Errors
- ET 07-0036, Corrected Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives
- ET 07-0037, Response to NRC Requests for Additional Information Related to License Renewal Application Time-Limited Aging Analysis Audit Question
- ET 07-0038, License Renewal Application, Amendment 3
- 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 07-0042, Followup Response to NRC Requests for Additional Information Related to License Renewal Application
- ET 07-0044, License Renewal Application Annual Update Information
- ET 07-0045, Operating Corporation - Response to Request for Additional Information Concerning Generic Letter 2003-01, Control Room Habitability
- ET 07-0046, Followup Response to NRC Requests for Additional Information Related to License Renewal Application Time - Limited Aging Analysis
- 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 08-0001, Summary of the Impact to License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Errors
- 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 08-0007, Followup Response to NRC Requests for Additional Information Related to License Renewal Application Time-Limited Aging Analysis
- 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 08-0019, Revision to the Response Due Date for a Request for Additional Information for Wolf Creek Generating Station License Renewal Application Metal Fatigue Analysis
- ET 08-0021, License Renewal Application, Amendment 6
- ET 08-0022, Response to Open Items Associated with the NRC Draft Safety Evaluation for the Application for License Renewal
- 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 08-0025, License Renewal Application Update Provided in Accordance with 10 CFR 54.21(b)
- ET 08-0026, Withdrawal and Resubmission of Submittal Containing Additional Information Regarding Main Steam and Feedwater Isolation System (Msfis) Controls Modification
- ET 08-0027, Correction to Summary of License Renewal Application, Amendment 6
- ET 08-0030, Response to NRC Requests for Additional Information Related to License Renewal Application - Closure of the Metal Fatigue Analysis Open Items
- 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 08-0033, Correction to Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application - Closure of the Metal Fatigue Analysis Open Items
- ET 08-0035, Main Steam and Feedwater Isolation System (Msfis) Controls Modification - Electromagnetic Compatibility Tests
- ET 08-0036, Supplement to Response to NRC Requests for Additional Information Related to Generating Station License Renewal Application, Closure of the Metal Fatigue Analysis Open Items
- 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 10-0010, 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 10-0078, Revision to Alliant Techsystems, Inc./Allegany Ballistics Laboratory American Centrifuge Program Classified Computer Network System Security Plans (TAC Nos. L33051 and L33052) - USEC
- ET 10-0079, Request for Foreign Ownership, Control, or Influence Determination in Support of the American Centrifuge Project - USEC Proprietary Information
- 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