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Category:Letter type:TMI
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Pages in category "Letter type:TMI"
The following 200 pages are in this category, out of 258 total.
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- TMI-02-066, Submittal of 2011 Radiological Environmental Monitoring Program Report
- TMI-09-003, Supplemental Information to the Three Mile Island Unit 1 Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
- TMI-09-005, 10 CFR 54.21(b) Annual Amendment to Three Mile Island Nuclear Station, Unit 1, License Renewal Application
- TMI-09-006, Response to NRC Request for Additional Information Related to License Renewal Application
- TMI-09-008, Response to Request for Additional Information Request for Exemption from 10 CFR 50, Appendix R Section Iii.G Fire Protection of Safe Shutdown Capability.
- TMI-09-009, Future Correspondence Concerning the License Renewal Application and a Revision to the License Renewal Commitment List
- TMI-09-011, Submittal of Decommissioning Report
- TMI-09-013, Annual Report
- TMI-09-027, Revision to Response for RAI B.2.1.30-1
- TMI-09-029, Supplement to License Amendment Request for: Oyster Creek Technical Specification Change Request No. 336, Three Mile Island Unit 1 Technical Specification Change Request No. 330, Deletion of Technical Specification Requirements for Review
- TMI-09-031, Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability.
- TMI-09-036, Request to Use a Provision of a Later Addenda of the ASME Boiler and Pressure Vessel Code, Section XI
- TMI-09-037, Supplement: Technical Specification Change Request No. 86 Deletion of Sections 6.5, Review and Audit
- TMI-09-038, Response to Request for Additional Information Related to Technical Specification Change Request No. 343: Application for Technical Specification Change to Reflect Steam Generator Replacement
- TMI-09-040, License Renewal Updated Environmental Information
- TMI-09-041, License Renewal Updated Environmental Information
- TMI-09-050, Company (EGC) Review of the Safety Evaluation Report with Open Items
- TMI-09-051, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan
- TMI-09-052, Submittal of Changes to Technical Specifications Bases
- TMI-09-054, Draft Outlines (Folder 3)
- TMI-09-057, Response to Request for Additional Information Related to Technical Specification Change Request No. 342: Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods
- TMI-09-058, License Renewal Application, Supplemental Updated Environmental Information
- TMI-09-059, 10 CFR 50.46 Report
- TMI-09-064, Updated Appendix A.5 License Renewal Commitment List
- TMI-09-073, Supplement to Technical Specification Change Request (Tscr) No. 342: Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods
- TMI-09-082, Response to Request for Additional Information Related to License Amendment Request No. 326 to Adopt TSTF-490-A, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical....
- TMI-09-086, Submittal of Concerning Unsatisfactory Laboratory Performance Tests
- TMI-09-088, Post Exam Comments and Technical References (Folder 1)
- TMI-09-090, Update 8 of the Post-Defueling Monitored Storage Safety Analysis Report
- TMI-09-097, Supplement to Combined 2008 Annual Radioactive Effluent Release Report
- TMI-09-099, Submittal of Revision 12 of the Post-Defueling Monitored Storage Quality Assurance Plan
- TMI-09-100, Supplement to Technical Specification Change Request (Tscr) No. 342: Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods
- TMI-09-101, Submittal of the Fourth Ten-Year Interval Inservice Testing Program, Revision 1, for September 23, 2004 Through September 22, 2014
- TMI-09-105, Response to June 25, 2009, Public Meeting Between the U.S. Nuclear Regulatory Commission and the Pressurized Water Reactor Owners Group (PWROG) Related to PWROG Topical Report BAW-2374, Revision 2
- TMI-09-107, Response to Request for Additional Information Regarding Generic Letter 2004-02
- TMI-09-109, Supplement to Technical Specification Change Request (Tscr) No. 342: Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods
- TMI-09-115, Issuance of the Core Operating Limits Report for Cycle 17, Revision 6
- TMI-09-134, Request for Extension of the Implementation Period for License Amendment Request No. 326 to Adopt TSTF-490-A, Rev. 0, Deletion of E Bar Definition & Revision to Reactor Coolant System Specific Activity....
- TMI-09-137, Response to Request for Additional Information Concerning Technical Specification Change Request (Tscr) No. 342: Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods
- TMI-09-139, Response to Request for Additional Information Concerning Technical Specification Change Request (Tscr) No. 342: Control Rod Drive Control System Upgrade and Elimination of the Axial Power Shaping Rods
- TMI-09-142, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02
- TMI-09-143, Notification of Deviation from EPRI 1016555, Secondary Water Chemistry Guidelines Revision 7, NEI 03-08 Needed Guidance
- TMI-09-148, Response to Request for Additional Information Re License Amendment Request No. 326 to Adopt TSTF-490-A, Rev. 0
- TMI-10-003, Submittal of Cycle 18 Core Operating Limits Report, COLR TMI 1, Revision 7
- TMI-10-004, Summary of Analysis Results to PWROG Topical Report BAW-2374, Revision 2
- TMI-10-008, Submittal of 2009 Annual Operating Report
- TMI-10-010, Three Mile, Unit 2 - Biennial 10 CFR 50.59 and Pdms SAR Report
- TMI-10-011, Submittal of Decommissioning Funding Status Report
- TMI-10-014, Inspection Results of Alloy 600/82/182 Pressurizer Butt Welds
- TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
- TMI-10-023, Response to Request for Additional Information Re Request for Exemption from 10 CFR 50, Appendix R, Section Iii.G, Fire Protection of Safe Shutdown Capability
- TMI-10-029, Biennial 10 CFR 50.59 and Commitment Revision Reports for 2008 and 2009
- TMI-10-030, Annual Radiological Environmental Operating Report
- TMI-10-031, Combined 2009 Annual Radioactive Effluent Release Reports
- TMI-10-035, Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves
- TMI-10-040, Cycle 18 Startup Report
- TMI-10-046, Submittal of Changes to Technical Specifications Bases
- TMI-10-052, CFR 50.46 Report
- TMI-10-053, Request to Extend the Inservice Inspection Interval for Reactor Vessel Weld and Internal Examinations - Relief Requests RR-09-01 and RR-09-02
- TMI-10-054, Technical Specifications Change Request (Tscr) No. 348 Relocation of Equipment Load List from TS 4.5.1.1 B, Sequence and Power Transfer Test, to the Updated Final Safety Analysis Report
- TMI-10-069, Supplement to Cycle 17 Refueling (T1R18) Inservice Inspection (ISI) Summary Report
- TMI-10-072, Response to Request for Additional Information, Application for Technical Specifications Change Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program
- TMI-10-079, Submittal of Relief Requests Associated with the Fourth Inservice Inspection Interval
- TMI-10-080, Response to Request for Additional Information, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled
- TMI-10-084, 10 CFR 50.46 30-Day Report Re Results of the Most Recent Small Break LOCA Analysis
- TMI-10-095, (TMI-1) Renewed Operating License No. DPR-50 Docket No. 50-28 - Revision of Scheduling Operator Examinations
- TMI-10-100, Submittal of Relief Request RR-10-02 Re Weld Overlay of the Pressurizer Spray Nozzle to Safe-End & Safe-End to Elbow Dissimilar Metal Welds
- TMI-10-101, Three Mile, Unit 1, Supplemental Information Request - Fourth Inservice Inspection (ISI) Interval Relief Request I4R-02
- TMI-10-102, Submittal of Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection (Lsi) Interval
- TMI-10-111, Submittal of Relief Requests Associated with the Fourth Inservice Inspection (ISI) Interval - Relief Request I4R-01
- TMI-11-007, Response to Request for Additional Information Concerning Relief Requests Associated with the Fourth Inservice Inspection Interval
- TMI-11-012, 2010 Annual Report
- TMI-11-017, Submittal of Relief Request RR-11-01 and RR-11-02
- TMI-11-026, Decommissioning Funding Status Report
- TMI-11-030, Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds
- TMI-11-056, Response to Request for Additional Information, Proposed Technical Specification Changes Regarding Relocation of Equipment Load List from Technical Specifications to a Licensee Controlled Document
- TMI-11-058, Combined 2010 Annual Radioactive Effluent Release Report
- TMI-11-059, 2010 Environmental Monitoring Program Report for 01/01 - 12/31/2010
- TMI-11-060, Response to a Request for Additional Information - Relief Request RR-10-01 Concerning Control Rod Drive Housing Examinations Associated with the Third Inservice Inspection Interval
- TMI-11-062, Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds
- TMI-11-064, Submittal of Changes to Technical Specifications Bases
- TMI-11-068, Comments on Draft Director'S Decision
- TMI-11-075, Response to Request for Additional Information Related to Technical Specification Change Request No. 351 Maximum Allowable Power with Inoperable Main Steam Safety Valves
- TMI-11-077, Supplemental Response to Request for Additional Information Related to Technical Specification Change Request No. 351: Maximum Allowable Power with Inoperable Main Steam Safety Valves.
- TMI-11-078, Response to Request for Additional Information - Submittal of Relief Request RR-10-02 Concerning the Weld Overlay of the Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds
- TMI-11-080, Request, Procedure to Be Implemented 12/07/10 to Return to Records Management Department
- TMI-11-084, Response to Request for Additional Information Concerning Relief Requests Associated with the Fourth Inservice Inspection (ISI) Interval
- TMI-11-086, Submittal of 10 CFR 50.46 Annual Report
- TMI-11-090, Supplement to Exelon Cyber Security Plan
- TMI-11-103, License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes
- TMI-11-115, Update 9 of the Post-Defueling Monitored Storage Safety Analysis Report
- TMI-11-128, Response to Request for Additional Information - Relief Request RR-11-01 and RR-11-02
- TMI-11-147, Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 13
- TMI-11-153, Response to Request for Additional Information Related to the Decommissioning Funding Status Report
- TMI-11-157, Cycle 19 Core Operating Limits Report, COLR TMI 1, Revision 8
- TMI-11-158, Submittal of Relief Request PR-05 Associated with the Fourth Inservice Testing (IST) Interval
- TMI-11-166, Closeout of Commitment Associated with Relief Request RR-1 0-02 Concerning the Weld Overlay of Pressurizer Spray Nozzle to Safe-End and Safe-End to Elbow Dissimilar Metal Welds and Completion of Inspection.
- TMI-11-171, Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications
- TMI-12-001, Correction of Steam Generator Tube Gap Size.
- TMI-12-006, Submittal of Decommissioning Funding Status Report
- TMI-12-013, Annual Report
- TMI-12-016, T1R19 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments
- TMI-12-025, Fitness for Duty Performance Data Reports - Annual 2011
- TMI-12-027, License Amendment Request to Revise Steam Generator Program Inspection Frequencies and Tube Sample Selection
- TMI-12-033, Special Report - Accident Monitoring Instrumentation Inoperability
- TMI-12-042, CFR 50.46 30-Day Report
- TMI-12-044, Special Report - Radioactive Gaseous Process and Effluent Monitoring Instrumentation
- TMI-12-045, Emergency Response Data System Data Point Library Changes
- TMI-12-047, (TMI-1), Biennial 10 CFR 50.59 and Commitment Revision Reports for 2010 and 2011
- TMI-12-048, Supplemental Information to the License Amendment Request to Revise Steam Generator Program Inspection Frequencies and Tube Sample Selection
- TMI-12-064, Supplemental Response to Request for Additional Information Related to the Proposed Administrative Changes to the Technical Specifications
- TMI-12-065, Operating License No. DPR-50 and Possession Only License No. DPR 73, Combined 2011 Annual Radioactive Effluent Release Report
- TMI-12-068, Submittal of Changes to Technical Specifications Bases
- TMI-12-069, Submittal of Inspection Plan for Reactor Internals
- TMI-12-070, Relief Request PR-05 Associated with the Fourth Inservice Testing (IST) Interval
- TMI-12-071, Transmittal of Steam Generator Tube Inspection Report
- TMI-12-072, (TMI-2) - Biennial 10 CFR 50.59 and Pdms SAR Report
- TMI-12-079, 10 CFR 50.46 Annual Report
- TMI-12-108, Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 14
- TMI-12-112, Notification of Intent to Submit a Post-Shutdown Decommissioning Activities Report
- TMI-12-125, Response to Request for Additional Information Related to the Decommissioning Funding Status Report
- TMI-12-137, Request to Use a Provision of a Later Addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants
- TMI-12-142, Response to NRC Request for Additional Information (RAI) Concerning TMI-1 Physical Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan
- TMI-12-148, Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02
- TMI-12-152, Submittal of End of Interval Relief Request RR-12-01
- TMI-12-157, Submittal of Relief Request RR-12-02 Concerning the Installation of a Full Structural Weld Overlay on the Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds and Alloy 600 Safe-End
- TMI-12-158, Three Mile, Unit 1, Submittal of Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval
- TMI-12-168, Submittal of Relief Requests Associated with the Fifth Inservice Testing (IST) Interval
- TMI-12-169, Request for Amendment to Eliminate Certain Technical Specification Reporting Requirements
- TMI-12-181, Response to Request for Additional Information - 10 CFR 50.46 30-Day Report
- TMI-12-182, Response to Request for Additional Information Regarding 2011 Steam Generator Tube Inspection Report
- TMI-12-183, Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds
- TMI-13-007, Decommissioning Funding Status Report
- TMI-13-009, Response to Request for Additional Information - Relief Request RR-12-02 Re Installation of Full Structural Weld Overlay on Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds & Alloy 600 Safe-End
- TMI-13-018, 2013 Emergency Preparedness Biennial Exercise Scenario
- TMI-13-020, Supplemental Information - Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial Rt NDT Values for Linde 80 Welds
- TMI-13-022, Response to Request for Additional Information - Request to Use a Provision of a Later Addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants
- TMI-13-033, Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Report
- TMI-13-034, 2012 Annual Report
- TMI-13-038, Relief Request RR-12-02 Concerning the Installation of a Full Structural Weld Overlay on the Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds and Alloy 600 Safe-End
- TMI-13-040, Revision 14 of the Post-Defueling Monitored Storage (Pdms) Quality Assurance Plan for TMI-2
- TMI-13-041, Post-Shutdown Decommissioning Activities Report Submittal
- TMI-13-043, Response to Request for Additional Information - Relief Request VR-01 Associated with the Fifth Inservice Testing (IST) Interval
- TMI-13-048, Response to Request for Additional Information - Submittal of End of Interval Relief Request RR-12-01
- TMI-13-050, Re-issue of Update 9 of the Post-Defueling Monitored Storage Safety Analysis Report
- TMI-13-055, Response to Request for Additional Information - 10 CFR 50.46 30-Day Report
- TMI-13-057, Three Mile, Units 1 and 2, Combined 2012 Annual Radioactive Effluent Release Report
- TMI-13-064, Submittal of Changes to Technical Specifications Bases
- TMI-13-068, Response to Request for Additional Information - Relief Request PR-01 Associated with the Fifth Inservice Testing (1st) Interval
- TMI-13-069, Submittal of Inspection Plan for Reactor Internals
- TMI-13-071, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
- TMI-13-073, CFR 50.46 Annual Report
- TMI-13-093, Withdrawal of the Three Mile Island Nuclear Power Station, Unit 1, Technical Specification Change Request 352, Revise Technical Specification 3.14.2 and the Licensing Basis Flood Hazard Contained in the Updated Final Safety Analysis Repor
- TMI-13-095, Response to Request for Additional Information - Overall Integrated Plan in Response to Commission Order Modifying License Requirements for Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)
- TMI-13-105, Update 10 of the Post-Defueling Monitored Storage Safety Analysis Report
- TMI-13-150, Response to Request for Additional Information - 10 CFR 50.46 30-Day Report
- TMI-13-155, Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 9
- TMI-13-156, Response to Request for Additional Information on Post-Shutdown Decommissioning Activities Report
- TMI-13-161, Submittal of Inspection Plan for Reactor Internals. Areva Report ANP-2952Q1NP Enclosed
- TMI-13-168, Closeout of Commitments Associated with Relief Request RR-12-02 Concerning the Installation of a Full Structural Weld Overlay on the Lower Cold Leg Letdown Nozzle Dissimilar Metal Welds and Alloy 600 Safe-End
- TMI-14-002, Draft - Outlines (Folder 2)
- TMI-14-011, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima....
- TMI-14-015, Decommissioning Funding Status Report
- TMI-14-022, Biennial 10 CFR 50.59 and Pdms Report for the Years 2012 and 2013
- TMI-14-023, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Permonth, Using the Consolidated Line Item Improvement Process
- TMI-14-029, T1R20 Refueling Outage Inservice Inspection (ISI) Owner'S Activity Report and Attachments
- TMI-14-042, Response to Request for Additional Information Regarding Request for Amendment to Eliminate Certain Three Mile Island Nuclear Station, Unit 1 Technical Specification Reporting Requirements
- TMI-14-049, Combined 2013 Annual Radioactive Effluent Release Report
- TMI-14-050, Updated Final Safety Analysis Report (Ufsar), Revision 22, Fire Hazards Analysis Report (Fhar), Revision 26, UFSAR and Fhar Reference Drawings
- TMI-14-051, 2013 Radiological Environmental Monitoring Program Report
- TMI-14-052, Notification of Implementation of License Renewal Activities in Preparation for Entrance Into Period of Extended Operation for Unit 1
- TMI-14-053, Biennial 10 CFR 50.59 and Commitment Revision Report for 2012 and 2013
- TMI-14-055, Submittal of Changes to Technical Specifications Bases
- TMI-14-058, (TMI-1) - Steam Generator Tube Inspection Report
- TMI-14-066, 10 CFR 50.46 Annual Report
- TMI-14-069, Submittal of the Fifth Ten-Year Interval Inservice Testing Program
- TMI-14-074, Response to Request for Additional Information Related to the Fall 2013 Steam Generator Inspections
- TMI-14-102, Request for Enforcement Discretion for Technical Specification (TS) 3.3.2, Emergency Core Cooling, Reactor Building Emergency Cooling and Reactor Building Spray Systems
- TMI-14-118, Submittal of Relief Request RR-14-01 Concerning Alternative Root Mean Square (Rms) Depth Sizing Requirements
- TMI-14-136, Response to Request for Additional Information - Submittal of Relief Request RR-14-01 Concerning Alternative Root Mean Square (Rms) Depth Sizing Requirements
- TMI-15-014, TMI - Response to Warning Communication South Carolina Radioactive Waste Transportation Permit 4498-37-14-X
- TMI-15-027, Cycle 20 Core Operating Limits Report, COLR TMI 1, Revision 10
- TMI-15-029, 2014 Annual Report
- TMI-15-036, Decommissioning Funding Status Report
- TMI-15-038, Response to Request for Additional Information Regarding Report Dated December 22, 2014, Submitted Pursuant to 10 CFR 50.46
- TMI-15-048, Submittal of the Update to the Fifth Ten-Year Interval Lnservice Testing Program
- TMI-15-049, Submittal of Changes to Technical Specifications Bases
- TMI-15-057, Changes to Emergency Response Data System (ERDS)
- TMI-15-062, Special Report - Radioactive Gaseous Process and Effluent Monitoring Instrumentation
- TMI-15-063, 10 CFR 50.46 Annual Report
- TMI-15-064, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process
- TMI-15-065, Notice of Transfer of Transmission Assests
- TMI-15-072, Supplement to License Amendment Request - Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limts
- TMI-15-076, Submittal of TMI White Paper-TMI Bwst Cleanup Path Issue
- TMI-15-086, Supplement to License Amendment Request - Temporary Restoration of Borated Water Storage Tank Cleanup and Recirculation Operation
- TMI-15-093, Revision to Post-Shutdown Decommissioning Activities Report
- TMI-15-102, Clarification of Commitment Regarding Resolution of Generic Letter 2004-02
- TMI-15-123, Cycle 21 Core Operating Limits Report, COLR TMI 1, Revision 11
- TMI-15-133, Part 21 Notification Due to Breaker Defect
- TMI-15-134, Revision 16 of the Post-Defueling Monitoring Storage (Pdms) Quality Assurance (QA) Plan